ML20085L073
| ML20085L073 | |
| Person / Time | |
|---|---|
| Site: | Oregon State University |
| Issue date: | 06/30/1991 |
| From: | Andrea Johnson Oregon State University, CORVALLIS, OR |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9111010210 | |
| Download: ML20085L073 (225) | |
Text
{{#Wiki_filter:RADIA110N (TNIER 4 8 Oni:cos Smr UNivrnsity Radiann Center A100 Curalbs, Oregon 97331 SW3
%,cthonc $03 737 2'L41 I au $03 737 N80 October 23,1991 U.S. Nuclear Regulatory Commission ATTENTION: Docur ent Control Desk Washington, D. C. 20555 Gentlemen:
Reference:
Oregon State University TRIGA Reactor (OSTRn, Docket No. 50-N3, License No, R 106 In accordance with section 6.7,e of the OSTR Technical Specifications, we are hereby submitting the Annual Report of the Oragon State University Radiation Center and TRIGA Reactor for the period July 1,1990 through June 30,1991, Please note that we are e'so using this letter of transmittal to send copies of tb9 current report to Mr. A! Adams, Project Manager, USNRC, Washington, D.C.; to Mr. Don Carlsca, Division of Reactor Inspection & j Safeguards, USNRC, Washington, D.C.; and to the USNRC's Region V office. This year's annual report continues to include significantly more information about the l entire Radiation Center rather than concentreting primarily on the reactor. Because the report addresses a number of different interests, it is rather lengthy, but we have incorporated a short executive summary which highlights the Center's activities and accomplishments over the past year. I hope you will find this summary helpful. 1 As a brief introduction to this year's annual report, I am most plaased to point out that the Radiation Center experienced another busy ana successful year. The reactor continued l to be a focal point of our operation as refleuttd by the fact that it was used approximately 95% of the available 45-hour work week. This represents a 5% increase in use over last year and further growth willlikely require the implementation of a second-shif t. Ef forts to increase the availability of the reactor within the limits of our present operating schedule resulted in a 157% increase in the number of hours when four users were being supported by a single reactor run. The net result of this overallincrease in use was an 18% growth in total reactor hours devoted to teaching and research. In addition to the reactor, almost all other aspects of the Radiation Center's program expanded during the past year. For example,62 OSU classes were accommodated in Center teaching facilities, which represents a 24% increase over last year. Additionally, there was a 36% increase in the number of institutions using the Radiation Center and a 325% increase in the total number of uses of Radiation Center facilities, which was our biggest increase ever. 910630 s 91110,to210
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USNRC October 23,1991 Scholarly publications involving a contribution by the Radiation Center continued to total over 100, and there were 47 presentations at professional meetings where the Center supported the development of the research data being reported. The new cobalt-60 irradiator highlighted in last year's report was well received by our users arid enabled us to perform considerably higher dose gamma irradiations in much shorter time intervals. As in previous years, the Radiation Center hosted a large number of visitors and continued to provide diversified technical support to a number of state agencies. In summing up the past year's accomplishments,it is safe to say that our staf f is very encouraged and grateful that our program has gone well and that we have been able to make a positive contribution to many of OSU's goals. Along with this, we view our growing assistance to other universities within (and outside) the Oregon State System of Higher Education, and to a number of state and federal agencies, as an indication of the university's reputation for scholarly and technical excellence. We hope you will find our report to be of interest. Should there be any questions, please let me know. Cordially,
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A. .J .nson Direc or AGJ:jrs--a:\usnrc Enclosure cc w/ enclosure: Non Power Reactor, Decommissioning, and Environmentel Projects Directorate, USNRC, Washington, D.C., ATTN: Mr. Al Adams (1 copy) i Division of Reactor Inspection & Safeguards, USNRC, Washington, D.C., ATTN: Mr. Donald Carlson (1 copy) Regional Administrator, USNRC, Region V, Walnut Creek, CA (1 copy) USNRC, Region V, Walnut Creek, CA, ATTN: Mr. Phil Qualls (1 copy); ATTN: Mr. Leroy Norderhaug (1 copy) cc w/out enclosure: l D. Stewart-Smith, Oregon Department of Energy l T. V. Anderson, OSTR Reactor Supervisor, OSU S. E. Binney, Chairman, OSTR Reactor Operations Committee B. Dodd, OSTR Reactor Administrator, OSU l J. F. Higginbotham, Senior Health Physicist,03U l C. S. Pratt, Health Physicist, OSU
w ANNUAL REPORT OF THE OREGON STATE UNIVERSITY RADIATION CENTER AND TRIGA REACTOR Ju y ' , ' 990 - June 30,1991 nr d rDI'
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i Annual Report of the Oregon State University Radiation Center and TRIGA Reactor July 1,1990 Juno 30,1991 To satisfy the requirements of: A. U.S. Nuclear Regulatory Commission, License No. R-106 (Docket No. 50-243), Technical Specification 6.7(e). B. Task Order No. 3, under Subcontract No. C84110499 (DE AC07-76 ERG 1953) for University Reactor Fuel Assistance-AR-67-88, issued by EG&G Idaho, Inc. C. Oregon Department of Energy, ODOE Rulo No. 30 010. Edited by: B. Dodd, Reactor Administratur With contributions from: T. V. Anderson, Reactor Supe visor
,,,, R. Conrady, Neutron Activation Analysis Specialist S. M. Cordell, Radiation Protection Technologist D. L. Cramer, Office Coordinator D. K. Dalton, Administrative Assistant J. F. Hi 0ginbotham, Senior Health Physicist J. F. Hopkins, Office Specialist A. G. Johncon, Director D. S. Pratt, Health Physicist J. R. Smith, Office Specialist S. P. Smith, Scientific Instrument Technician Submitted by:
A. G. Johnson Director, Radiation Center Radiation Center Oregon State University Corvallis, Oregon 97331-5903 Telephone: (503)737-2341 Fax: (503) 737-0480 October 1991
Annual Report of the Oregon State University Radiation Center and TRIGA Reactor Table of Contents E020 PART I OVERVIEW A. Ackr.owledgements . . . . . . ... ... .... .. ........... .... . 1-1 B, Executive Summary . . ....... ......... . . ......... ..... 12 C. Introduc tion . . . . . . . . . . . . . . . . . . . . . . . . . ... ........ . .... .1-5 D. Overview of the Radiation Center ....... ....... ..... ......... 1-6 E. Summary of OSTR Envi.onmental and Radiation Protection Data . . . . ,. .. 1-9
- 1. Liquid Ef fluents Released . . . . . . . . . . . . . . . . .. . .......... 19
- 2. Airborne Effluents Released .... .. .. .... ... . . . . . 1-10
- 3. Solid Waste Released . ... .. ......... .
4.
.... .. .. . . . 1-10 Radiation Exposure Received by Personnel . . . ... .. .. .. ..... 1-11 5.
Number of Routine Onsite and Offsite Monitorin0 Measurements and Samples . ... ........ . ....... . .... .. . . . . l- 12 F. History . . . . . . . . . ...... ...., ......... . . .... .. . 113 PART 11 PEOPLE A. Faculty . . . . . . . . . ......... .. ......... .... . ..... ... . ll 1 B. Visiting Scientists and Special Trainees .
... .. ......... .... . ll-4 C. OSU Graduate Students . ....... . .. ..... ...... . . . . 11- 5 D. Business, Administrative and Clerical Statf . . . . . . . . . . . .. .. .. . . . ll- 6 E. Reactor Operations Staf f ..... . ..... . . .... ..... ... . 11- 6 F. Radiation Protection Staf f . . . . . . ..... ... .
........... 11- 6 G. Scientific Support Staf t ...... ... ..... ..... . . ,. .. 11 7 H. OSU Radiation Safety Office Staf f . ..... ........ ........ ......
11- 7
- 1. Committees .... .......... .... ............. . .. .. .... II.7
- 1. ReacMr Oparations Committee . . . .
... .. . ....... . . ll-7
- 2. Radiation Safety Committee . .. ........... ..... .. . .. Il-8
- 3. Radiation Center Safety Committee 4
..... . ..... .... ,.. . . ll-8 Rodiation Center TOM Team . . . ....... ... . . . . . . . . . 11 - 8 .
' ~ ~ ~
\ Plan PART 111 - FACILITIES 111 1 A. Research Reactor . . . . ..... .. . ..... ... .. ... ....
- 1. Description . . . . . . ....... .. ... .. . ........ .. , lil-1
- 2. Utilization . . . . . ... ..... ....... ......... .. . . . . 111 5
- a. Instruction .. ...... .. ........ . .. ... . . . . . . . . . Ill 6
- b. Research . ....... ... ... .. ... ..... .... . . . til-6 B. Analytical Equipment .. .... ..... .. ... . . . . . . . . . . . . . 111- 1 1
- 1. Description . . . . . . . . . . . . .. .. . .. ... . .. . . . . . . . . 111- 1 1
- 2. Utilization . . . . . . . . . . . . ... .. ........ . . . . . . . . . . . . 111- 1 1 C. Radioisotope Irradiation Sources . . . .. ........ .. ... . . . 114- 1 5
- 1. Description . . . .. .... ................. ........ . . . 111- 1 5
- 2. Utilization . . . . ......... . . . .... . .. ... . . . . Ill 15 D. X-Ray Machine . . . . . . . ... ........ ............. ... 111- 2 0
- 1. Description . . . . . ...... . ......... .. . .... . . . . 111- 2 0
- 2. Utilization . . . ... . .. .. .... .. . ... . . . til 20 E. Laboratories and Classrooms . . ... .. . ....... .. . . . . . . 111-21
- 1. Description ....... . .. .. .. . . ..... .... 111 21
, lll-22
- 2. Utilization . . . . . . . ..... .. ...... . . .. ....... .
F. Instrument Repair anci .stion Facility . . . .... ... . ..... . . . 111- 2 5
- 1. Description . . ... .. .................. .... ... . 111- 2 5
- 2. Utilization . . .. ... . .............. . . ..... . . Ill 25 G. Libraries . . . . . .. ...... ....... . ..... . . . . . . . . . . . . Ill 2 6
- 1. Description . . ....., .. . ..... .. . ... ...... . 111- 2 6
- 2. Utilization . . . . ... .. .... ... .. .. . ............ 111- 2 7 PART IV - REACTOR A. Operating Statistics ..... ....... ...................... ... IV-1 B. Experiments Perf ormed . . . . . . . . ........................ . . . . . IV-10 C. Unplanned Shutdowns . . . , . ........... . . . . . . . -. . . . . . . . . . . . . . I V - 1 2 D. Changes to the OSTR Facility, to Reactor Procedures, and to Reactor Experiments Performed Pursuant to 10 CFR 50.59 ...... .. .. IV-14 1, 10 CFR 50.59 Changes to the Reactor Facility . . . . ........ .. . IV-14
- 2. 10 CFR 50.59 Changes to Ractor Procedures . . . . . . .. . . . . . . . . . I V- 3 5
- 3. 10 CFR 50.59 Changes to Reactor Experiments . . . . . . ... ...... IV-50 E. Survellance and Maintenance . . .... .... .. . ..... . . . . . . . . IV 51
- 1. Non-Routine Maintenance . . .... . . .. .. ... ........ ..IV-51
- 2. Routine Surveillance and Maintenance ......... . .. ,,.. . . . . IV-5 2 F. Repoitable Occurrences ....... ..... ..... ... .. . . . . . . . . . . IV 5 3
P_m PART V - PROTECTION A. Introduction . . . . . . . . . . . . . ........ . .. . ... .... . . . . . . V- 1 B. Environmental Releases . ................ ..... ... .... ...... V-3
- 1. Liquid Ef fluents Released . . . . . . . . .......... ... ........... V-3
- 2. Airborne Ef fluents Released . . .. . . .. .... .. .. V-3
- 3. Solid Waste Released . . . . . . . ....... ....... ......... .... V-6 C. Personnel Doses ... .. .... .... . ... .. ..... ..... .. ... V-8 D. Facility Survey Data . . . . . . . . . . . . ....... . ........ .... . . . V 11
- 1. Area Radiction Dosimeters . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V- 1 1
- 2. Routine Radiation and Contamination Surveys .. . . .... . . . V- 16 E. Environmental Survey Data .......... .... ... .......... . V-18
- 1. Gamma Radiation Monitoring .... . ... . . ... . . V-18
- 2. Soil, Water, and Vegetation Surveys . . . . . . ....... .. . .. V-24 F. Radioactive Material Shipments ....... .. ...... ........... V-28 G. References .... .... . . . . . . .. . . . V-31 PART VI - WORK A. Summary .......... .... . .. . .. ... . . .... . . . . . VI- 1 B. Teaching . . . . . . . . .. .. . . ... .. . .. ....... .. . . VI- 1 C. Research and Service . . . . .. . ... ... . .... . .. . . VI-1
- 1. Neutron Activation Analysis . . . . ..... ..... .. ... VI-36
' 2. Forensic Studies . .. .. . .. ... ... .... . VI-37
- 3. Irradiations . . . . . . . . . .. . . . .. .. VI-37
- 4. Radiological Emergency Response Services . . . .......... . . VI-37 5 Training and instruction . . . . ....... . .. . . . . . . . VI 38
- 6. Radiation Protection Services . .. ..... ... . ....... . VI-39
- 7. Radiological instrument Repair and Calibration ............. . . . . . VI-4 0
- 8. Consultation . . ... .. .. . . .. .... . . . . . . . . . . VI-41 PART Vil - WORDS A. Publications in Print . ... . ... .. .. ... ......... . Vll-1 B. Theses ............. ... .. ... .. . .. . . . . Vll-10 C. Reports Submitted for Publication . . ... . . . ......... ... . Vll11 D. Documents in Preparation . . . . . . . . . . .... . . Vll-12
- 1. Publications . . . . . .. ... . .. . . . .. .. . .. . Vll-12
- 2. Theses ... ... .. .... .... ..... .. .. . Vil-13 E. Presentations .... . . . . . .. ... .. . . . Vil-14 F. Public Relations ..... ... . . . . .... . . . . Vll-19 1 __ _ _ - - _ _ _ _ - _ _ _ _ - _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ - _ _ . ___~
LIST OF TABLES labla 111!Q 1M20 lli. A.1 OSU Courses Using the OSTR ...... . . . ,,. ... . . . Ill-7 Ill. A.2 OSTR Teaching Hours .... ..................... . . . Ill-8 Ill.A.3 OSTR Research Hours . . . . ... .. ....... . ...... .. 11110 lit B.1 Radiation Center Spectrometry Systems: Gamma, Low Energy Photon, Alpha . . . . . . . . . . . ....................... . lll-12 lil.B.2 Radiation Center Liquid Scintillation Counting Systems .. .. . . Ill-13 Ill.B.3 Radiation Center Proportional Counting Systems . . . . . . . . . . . . t il- 14 til.C.1 Budd
- Co Irradia*.or Use . . . . . . . . .... ... . .. . . . . Ill-18 Ill.C.2 Gammacell 220
- Co irradiator Use . . . . . . . . . . . . . .. . . . . lll-19 til.E.1 Student Enrollment in Nuclear Engineering and Nuclear Science Courses Which Are Taught or Partially Taught at the Radiation Center ... .. .. .. ........... . . . . . . til-23 IV.A.1 OSTR Operating Statistics (Using the FLIP Fuel Core) .. ..... . IV 2 IV.A.2 OSTR Operating Statistics with the Original (20% Enriched)
Standard TRIGA Fuel Core .. .... .. .... ....... . ..IV-4 IV.A.3 Present OSTR Operating Statistics . ......... ............IV-5 IV.A.4 OSTR Use Time in Terms of Operational Functions . . . . . . . .. ..IV-G IV.A.5 OSTR Use Time in Terms of Specific Use Categories . . . . . ......IV-7 IV.A.6 OSTR Multiple Use Time . . . . . . . .... ...... .. .... .. .IV-8 IV.B.1 Use of OSTR Reactor Experiments . . . . . . ... .......... . . IV 11 IV.C.1 Unplanned Reactor Shutdowns (Scrams) .. . ...... . . . . . . IV 13 - V.A.1 Radiation Protection Requirements and Frequencies . . .......... V-2 , s V.B.1 Monthly Summary of Liquid Effluent Releases to the Sanitary ,, Sewer . . . . . . ................. .. .. ... . . . . . . . V-4 4 1 9 f
LIST OF TABLES (Continued) Inh!.a lil!c faQD V.B.2 Monthly Summary of Gaseous Effluent Releases . . .... .. . . V-5 V.B.3 Annual Summary of Solid Waste Generated and Transferred . .......... ..... .. . ... ..... .... V-7 V.C.1 Annual Summary of Personnel Radiation Doses Received . . ... . V-10 V.D.1 Total Dose Equivalent Recorded on Area Dosimeters Locatori Within the TRIGA Reactor Facility ..... ..... ..... . . V-13 V.D.2 Total Dose Equivalent Recorded on Area Dosimeters Located Within the Radiation Center .. .. . ... . . .. . . V-14 V.D.3 Annual Summary of Radiation Levels and Contamination Levels Observed Within the Reactor Facility and Radiation Center During Routine Radiation Surveys .. .... .. . . . .. . V-17 V.E.1 Total Dose Equivalent at the TRIGA Reactor Facility Fence . . . . . V-21 V.E.2 Total Dose Equivalcot at the Off-Site Gamma Radiation Mcnitoring Stations . . .....,...... . .... .,, V-23 V.E.3 Annual Average Concentration of the Total Not Beta Radioactivity (Minus 3H) for Environmental Soil, Water, and Vegetation Samples . . . . . . . . . . ......... ... .. .... ... V-26 V.E.4 verage LLD Concentration and RanDe of LLD Values for Soil. Water and Vegetation Samples . , , . . . . . . . . . . . . . . . . . . . . . . V-27 V.F.1 Annual Summary of Radioactive Material Shipments Originating From the TRIGA Reactor Facility's NRC License R-106 ..... .. V-29 V.F.2 Annual Summary of Radioactive Material Shipments Originating From the Radiation Center's State of Oregon License ORE-0005 3 . . . . . ... ...... ................. V-30 VI.C.1 institutions and Agencios Which Utilized the Radiation Center . . ... . .......... . . . . . ..... . . . VI-3 VI.C.2 Graduate Student Thesis Research Which Utilized the Radiation Center ...... .... . .. .. ....... . VI-7
LIST OF TABLES (Continued) Inble Ihla EASA VI.C.3- Listing of Major Research and Service Projects Performed or in-Progress at the Radiation Center and Their Funding Agencies . . . . . VI 14 VI.C.4- Summary of the Types of Radiologicalinstrumentation Calibrated to Support the OSU 'IRIGA Reactor and the Radiation Center ....................................IV-42 VI.C.5 Summary of Radiological Instrutnentation Calib ated to Support Other Agencies . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VI-43 . Vll.F.1 Summary of Visitors to the Radiation Center . . . . . . . . . . . . . . Vll 20 M 4 k
I LIST OF FIGURES Elgitta Iltle Eng.t I.D.1 Floor Plan of the Radiation Center . . . . . . . . . . . . . . . . . . . . . . . . .18 lit. A.1 Cutaway View of Standard TRIGA Mark 11 Core Arrangement . .. . lll 2 Ill.A.2 Horizontal Section of TRIGA Mark 11 Reactor . . . . . . ... ..... . 111- 3 Ill.A.3 Vertical Section of TRIGA Mark 11 Reactor .... ..... . . . . . . . 111-4 80 Ill.C.1 Budd Co Irradiator (Vertical Section) ...... .... . . . . . . . 111-16 ill.C.2 Gammacell 220
- Co irradiator . . . . . .. . .. .. . 111- 1 7 IV. A.1 OSTR Annual Energy Production vs. Time (Annual Reporting Period) . . ................ ... ....... ... . lV 9 IV.E.1 Monthly Surveillance and Maintenance (Sample F arm) . . . . . .IV-54 IV.E.2 Quarterly Surveillance and Maintenance (Sample Form) . . . . . . . . . IV- 5 5 IV.E.3 Semi-Annuai Surveillance and Maintenance (Sample Form) . . . . IV 57 '
IV.E.4 Annual Surveillance and Maintenance (Sample Form) . ........IV-59 V.D.1 TRIGA Facility and Radiation Center Area Dosimeter Locations . . . . . . . . . ...............................V-12 b.E.1 Area Radiation Monitor Locations for the TRIGA Reactor, and on the TRIGA Reactor Area Fence . . . . . . . . . . . .,,. . . , . V- 19 V.E.2 Monitoring Stations for the OSU TRIGA Reactor . ......... . . V-2 2
PAlT; o g , - OVERVIEW m - _ p_
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K Institutions served by the Radiation Center during 1990-91
- Single Use
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- ' i i
i PARTI 1 OVERVIEW t
- A. AC10<dat019ala l During this reporting period, many individuals and organitations helped the Radiation l Contor succeed, in recognition of this, the staf f of the OSU Radiation Centor and TRIGA i
+
Reactor would like to offer their appreciation to all of thoso who 'ontributed to the information and events contained in this report. To the University administration who tor.aistently supported our program; to those who provided our funding, particularly the ! stato cf Oregon and the U.S. Department of Enorgy; to our regulators; to the researchers, the students and others who used our facilities and services; to the OSU Physical Plant, who patiently provided invaluable assistance through the:r engineering, maintenanco, and other supporting p*ograms; to the OSU Security and University Police i who are always flycro when wo nood thorn; and to the OSU Department of Printing, who f consistently produco a quality product; wo most earnestly say thank you. ! As a final noto of gratitudo. the staf f would liko t.> hlghlight the talents and the toleranco ! of our secretarial staff, who performed admirably duiing the preparation of this report. b b 1 i i 5 P Er+vem-,.-.w,m, . - - , --,-.m.,,m.mm-m,.-..-.-..,_.-mo.,,wr3,,,-..=------.e-,#.,.#- 1-,...e,-.-rr.-e~s ,,e,y a -,,-..m,--,.me-,,-,,.oe .r-. ,,-.--~r-
_ _ _ . . _ . _ _ .._ _ __._.-._ .____.._.m.__. _. ~ i.3 B. faccuthnAunmen l , For the past soveral years the Radiation Contor's annual report included an exocutive sumtnary where our most noteworthy achiovernents for the reporting petiod woro highlighted, in prepar;ng such an oxocutivo sumrnary, one is always faced with the f necessity of compiling and assossing key performance data in order to obloctively determino whether or not the program is mooting its goals. Numbers alone do not toll 1 the entito story, but they are one way to convoy the increasing level of activliy which is 9ccurring at the Radiation Contor. All of us at the Contor ato very grateful that our ; operation has gono so well over the past year. The program remains healthy and vigorous and wo ero committed to having it continue in this monnor, [ t The staff at the Radiation Contor is very aware that our success is closely tied to the important support we rLcolve from many different individuals and organizations. - Therefore, before wo summarire our achievements, we would like to express our ; appreciation to overvone who contributed to our program. In particular, wo wish to thank the university's administration for their continued financial and administrativo support and for their encouragement. We are also rnost grateful to the U.S. Departmont
- of Energy for their very valuable support through the University Reactor Sharing Program +
and for their financial assistanco in helping us modernire equipment essential to tho - operation of the univeisity's reactor. We would also like to extend our appreciation to i the many other organizations who funded research and technical services carried out at the Centor. The resources obtained through all of those channels continue to croato valuable opportunitics for numerous students and researchers who use the uniquo f acilities present at the Radiation Contor. l One of the Conter's most visible and important programs is the TRIGA research reactor, We are pleased to roport that the reactor romained very busy over the past year and was used an average of about 95% of the availablo 45 hour work wook. This is 5% greater. than last year and further growth willlikely require the implomontation of a second shif t. - However, in order to increase the availability of the reactor within the limits of our- :!
. present operating schedulo, we continue to encourage simultaneous use of the reactor
- by more than one researcher. As a result, use of the reactor to accomrnodato more than one project at a Ol ven time proved to be a popular mode of operation, and there was a 157% increase in the number of hours when four users were being supported by a j e,.. .. . , + + , - 1 . p4w-+,
I3 rdngle reactor run. On top of this, a consistently high losel of reactor uso resulted in an 18% overall growth in total reactor bours devoted to teaching and research. Whenlooking specifically at teachin0 applications, use of Raaiation Center f acilitios also continued to bo high, as illustrated by the 62 OSU classes which were accommodated at the Center, This is a 24% increaso over last year, Additionally, about one-half of those classes used tho teactor and about 52% of the reactor': total operatin0 hour s were in direr
- support of such classos. This is a 27% increase over the previous year.
Growthin the volume of research performed at the Radiation Center was mso prominent again this year. Several Loy indicators of this expanded research of fort are the number of individual Radiation Center picjacts accommodated, which increased 15%; the number of f unded research projects, whichincreased by 19%: and the number of f aculty using the Contor for their investigations, which increased by 7%. Research over the past year continued to employ the many applications of neutton activation analysis, and expanded into several now and exciting ateas. For example, the Center is accommodat-ing an innovativo prograin for the College of Votorinary Medicino involvin0 microbial degradation of toxic wastes, a now cancer therapy program for Ore 00n Hoolth Sciences University and a unique world-class f acility funded by the Westin0houso Corporation for design and testing of their ncw Model AP 600 reactor system, The Center's now 7000 curio cobalt-60 gamma irradiator also proved to be a valuable addition to our research capabihties. As expected, the now irradiator enabled the Radiation Center to poriorm considerably hi0her doso gamma irradiations in much shorter time intervals and was used for 1579 hours of irradiations wh!ch would have been virtually impossib;e with the older irradiator. However, because the gamina radiation levels in tho older irradiator are now lower, it moots a unique requirement that cannot easily be met with the new device and consequently the older irradiator showed a 48% increase in the number of irradiations performed. Scholarly publications involving a contribution by the Radiation Center continu6d to total over 100, and thoto were 47 presentations at professional meetin0s where the Contor supported the development of the research data being reported. Considering the publications currently in print, those presently submitted f or publication, end those in the
l4 final stages of preparation, there have boon 109 total articios generated during the 1990 91 reporting period which involved a contribution by the Radiation Contor. I As a result of this past year's performanco, wo believe that the OSU Radiation Contor I has again enhanced its imago as a regionally and national ly ocognized instructional and research facility. We are gratified by the fact that the number of institutions using the Contor continuos to increase each year. This year tho increase in user institutions was a strong 36%; however, our largost growth occurred in the total number of uses of Radiation Contor f acilities, which increased by 325%, our biggest increaso over. While such growth is definitely good,it is very important to note that the increased uso did not reduce the availability of any Radiation Contor f acilities, particularly the reactor, to OSU students or roscarchers. , Other services of forod by the Radiation Conter, such as tours, where we hosted a largo e number of visitors; f orensic support ior law enf orcement programs; emorgency responso and other technical assistance to State of Oregon agencios: and instrument repair and , cEbration for OSU and other schools within the stato system of higher education, continued to bo heavily used. Regarding this latter activity, the Radiation Contor { showed a 68% increase in the number of radiation detection instruments repaired and/or calibrated for radiation users on the OSU campus. We are especially pleased to be able to of for this support to the_OSU community since thoso calibrations are both a stato and federallicenso requirement and are unavailable anywhere else in Oregon. As a final note, we feel that it is very important to point out that thoto woro no items of regulatory noncomplianco and no emorgencios or security events relating to tho l Radiation Contor during this reporting period. Furthermore, all of the increased use of the Radiation Contor and reactor was accomplished with no increase in personnel radiation exposure or any impact on the environment. The comprehensive radiation ' ' protection program at the Radiation Conter once again showed that the Contor and the reactor can be operated safely and within the international goal of kooping personnol dosos and releases of radionuclidos as low as reasonably achievablo (ALARA).
l5 C. Initndunilan
- The current annual report of the Oregon State University Radiation Contor and TRIGA Reactor follows the usual format by including information rolating to the entito Radiation Conter (other than just the reactor. However, the information is still presented in such a mannar that data or, the reactor rnay be examined separately if desired, it should be noted that all annual data given in this report cover the period from July 1,1990 l through June 30,1991. Cumulative reactor operating data in this report relato only to -
the FLIP-fueled core. This covers the period from August 1,1970 through Juno 30, ! 1991. For a summary of data on the reactor's original 20% onriched coro the reader is referrod to Tablo IV.A.2 in Part IV of this report, or to the 1976 77 annual report if a more comprohonsive review is noodod.
?
In addition to providing generalinformation about the activitios of the Radiation Contor, this report is designed to meet the reporting requirements of the U.S. Nucloor Regulatory 4 Commission, the U.S. Department of Energy, and the Oregon Department of Energy.
- Because of this, the report is divided into soveral distinct parts so that the roador may casily find the foctions or interost. '
I l
+
6 Y I-9
l6 D, .Qyttview_oLitin Rodallon_Cenlet r The Radiation Center is a unique facility which serves the entiro OSU Campus, all other ; institutions within the Oregon Stato System of Higher Education, and many other , collegus and ut,lvorsitios throughout the nation. The Contor also regularly providos special services to stato and federal agencies, particularly agencios dealing with law enfofcoment, energy, health, and environmental quality, and ronders assistance to Oregon industry, in addition, the Radiation Contor providos permanent office and laboratory space for the OSU Department of Nuclear Engineering, tho OSU Radiation Safety program, the Instituto of Nuclear Science and Engincoring, and for the OSU nuclear chemistry, radiation chemistry, and geo and cosmochemistry programs. Thoto is no other university f acility with the combined capabihties of the OSU Radiation Contor in the western half of the United States. Located in the Radiation Conter are major items of specialized equipment and unique teaching and rosearch 1acilities, Those include a TRIGA Mark ll research nuclear rcactor; two cobalt 60 gamma irradiators; a 300 kVp X ray generator; a number of state of the-art computer based gamma radiation spectromotors and associated germanium
/
detoctors; a neutron radiography facility capablo of taking still or very high spood radiographs; and a variety of instruments for radiation measuromonts and monitoring. Spocialized facilities for radiation work inciudo teaching and research laboratories with i up to-date instrumentation and related equipment for performing noutron activatior analysis and radiotracer studios; laboratories for animal and plant experiments involving radioactivity; a facility for repair and calibration of radiation protection instrumentation; and ' facilities for packaging radioactivo materials for shipment to national and international destinations. Figuro I.D.1 shows the layout of theso facilities at the Radiation Center, , The Radiation Center staff regularly providos direct support and assistanco to OSU teaching and research programs. Areas of exportiso commonly involved in such offorts iriclude nucl6ar engineering, nuclear and radiation chemistry, noutron activation analysis, neutron radiography, radiation effects on biological systems, radiation dosimetry, production of short lived radioisotopes, radiation shielding, nuclear instrumentation, ' emergency response, transportation of radioactive materials, instrument calibration, radiation health physics, radioactive waste disposal, and other related areas.
l l+7 l l 1 ! In addition to formal academic and research support, the Center's staff providos a wido l variety of other services including public tours and public instructional pro 0 rams, and i
- profer.sional consultation associated with the feasibility, desigri, sufoty, and execution I of experiment,s using radiation and radioactivo motorials, 4
r 6 e f I C t r I i R l i b o 1 , r b
l8 Figuro I.D.1 rioor Plan of the Radiation Ceriter l
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I l9 E. SumnWY_nLQEltLEn:dtenmentaLoniBadiatismRolestion. Data
- 1. Linui1Efflutailfic!ane11Soo TahlvXIL1)
- a. Total estimated quantity of radioactivity ,
relcared (to the sanitary sower)"' S.89 x 104Curios l i
- b. Detectablo radionuclides in the liquid wasto 8H, #8Na, "Co, "Zn, !
76So, '"Tc, "*Co i
- c. Estimated averago concentration of released radioactivo inatorial at the point of releaso 0.38 x 10 ' Cl/cc
- d. Percent of applicablo MPC for released _
liquid radioactive material at the point 5.0%* t ofroloax 0. 2 % 4 {
- o. Total volur' of liquid of fluent released, including diluont, which containod an OSTR -
contribution"' 3634 gallons (1) The OSU operational policy is to subtract only detector background from our watet analysis data and not background radioactivity in the Corvallis city water. (2) _ Based on values listed in 10 CFR 20, Appendix B, Tablo 2, Column 2. (3) _ Based on values listed in 10 CFR 20, Appendix B, Table 1, Column 2, applicable to sewer disnaiej. (4) Total volume of offluent plus diluont does not take into consideration the additional mixing with the over 7,500,000 gallons per year of liquids and sowago normally discharged by the Radiation Contor complex into the same sanitary sewer system. I
110
- 2. Airborno Effluents fieleased (Scu_Intde_Y.JL7)
- c. Total cstimated quantity of radioactivity released 5.5 Curies
- b. Detectable radionuclidos in the gaseous wasto"8 At (T" = 1.83 hr)
- c. Estimated avera00 atmosphoric diluted concentration of argon-41 at the point of relonso 3.6 x 10* Cl/cc
- d. Percent of applicablo MPC for diluted concentration of argon 41 at the point of roloaso 0.9%
- c. Total estimated roloaso of radioNtivity in particulate forrn with half lives greater than 8 days'28 Nono
- 3. Solid _Wasto Released (Seo Tablo vJL3)
- a. Total amount of solid wasto packaged and disposed of 38 ft3 b .- Detectable radionuclidos in the solid wasto r'Na, d'Sc, 6"Co, "Fe,
'*C o, **2n, So , S b, ist i,is7Cs, OLa,' '6'Eu -
- c. Total radioactivity in the solid wasto 7.9 x 104Curios (1) Routino gamtna spectroscopy analysis of the gaseous radioactivityin the stack dischargo indicated that it was virtually all argon-41.
(2) _' Evaluation of the detectable particulato radioactivity in the stack dischargo confirmod its origin as naturally occurring radon daughter products, predominantly load 214 and _ bismuth-214, which are not associated with reactor operations. l
l-11 L
- 4. Sadidon Exopw.ic_Betelved by_EctMencilEenlab!0._VSJ)"' +
- a. Facility Operating Personnel (mrom) [
(1) Averago whole body 9 ; (2) Average extremities 40 i (3) Maximum whole body 105 (4) Maximum extremitios 540 , i
- b. Koy Facility liesearch Personnel I i
(1) Average whole body 1 ; (2) Average extremities 5 (3) Maximum wholo body 15 (4) Maximum extremitios 60
- c. Physical Plant Maintenance Personnel ;
(1) Avorage whole body <1 j (2) Maximum whole body 10 ;
- d. t.aboratory Class Students (1) Avorage wholo body 0 (2) Average extremities - 0 (3) Maximum whole body 0 -;
(4)- Maximum extremities 0 i
- e. Campus Police and Security Personnel ,
(1) Average whole body 0 (2) Maximum whole body 0
- f. Visitors i (1) . Average whole body <1 (2) Maximum whole body 10 4
- (1). "O" indicates that each of the beta-gamma dosimeters during the reporting period was. ,
less than the vendor's gamma doso reporting throshold of 10 mrem or that each of tho . neutron dosimeters was less than the vendor's threshold of 30 rnrom, as applicable. ; s
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I (a) Bota gamma dosimotor measutomonts 136 (b) Noutron dostmotor measuromonts 40 !
- -)
(2) Radiation and Contamination Survey l Measutomonts (Soo Tai. 9 V.D.3) -6000 ; I
- b. Environmental Survey Data (1) Gamma Radiation Monitoring (Sco Tables V.E.1 and V.E.2) 1 (a) Onsito monitoring ;
- OSU TLD monitors - 108 +
- Radiation Detection Co. TLD monitors 72 ;
- Monthly pR/hr measuromonts 108 ,
(b) Of faitu monitoring
- OSL' TLD monitors 264 l
- Radiation Detection Co. TLD monitors 104 !
Monthly pR/hr measutomonts 252 j (2) Soil, Water and Vegotation Surveys (Sco Table V.E.3) (a! Soit samples 16 ; (b) Water samplos 16 ; (c) _Vogotation samplos 56 ) I L r P l-
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113
- l l
F. Lii$10tY l A brief ctvonology of the key dotus and events ir. the history of the 05U Ranunion Center and the TRIGA reactor is given below: June 1964 Completion of the first phase of the Radiation Cen'er, consisting of 32,397 squato fert of offico and laboratory space, July 1964 Transfer of the 0.1 W AGN 201 reactor to the Radiati6n Comer. This reactor was initially housed in the Mechanical Enginecong Donortrnerit and first went criticalin January of 1959. Oct.1906 Completion of the second phase of the Radiation Center, consisting of 9.950 squato foot of space for the TRIGA reactor and associated laboratories and offices. March 1967 Initial criticality of the Oregon Stato TRIGA Hoactor (OSTR). The reactor was licensed to oporute at a maximum steady stato power level of 250 kW, and was fueled with 20% enriched fuel. , August 1969 OSTR licensed to operato at a maximum steady state power of 1 MW, but could do so only for short periods of timo duo to lace, of cooling capacity. June 1971 OSTR cooling capacity upgraded to allow continuous operation at 1 MW. Apnl 1972 OSTR Site Certificate issued by the Oreann Energy Facility Sitin0 Council. Sept.1972 OSTR area fence installed. Dec.1974 AGN 201 reactor permanently shut down. March 1976 Completion of 1600 square feet of additional space to accommndate the rapidly expanding nuclear en0:nectin0 program. July 1976 OSTR refooled with 70% enriched FLIP fuel. July 1977 Completion of a second 1600 square foot of space to bring the Radiation Center complex to it? -orrent total of 45,553 square foot. Jan.1980 Major upgrado of the electronics in the OSTR control consolo.
l.14 t July 1980 AGN 201 seactor decommissioned and space released ior unrestricted !
!= uso. -
l June 1982 Shipment of the original 20% enriched OSTR fuoi to Westinghoust, 4 Hanford Corporation. , , Dec.1988 AGN 201 componon's transferred to Idaho Stato University for uso in their AGN 201 teactor program. I Dec.1989 OSTR licensed power increased to 1.1 MW. June 1990 installation of a 7000 Ci"Co Gammacellirradiator. i l I , I I t
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i i PART11 PEOPLE lhis part contains a listing of all people who were residents of the Haduition Conter or who worked a significant arnount of timo at the Center dunna this reporting period. Sections A, B and C list tho academic staf f, trainees and students, while sections D through G give the Radiation Center's operating staf f. Section H shows the OSU Radiation Safety Of fico stall and section I provides the composition of committees involvmg Center porsonnel, It should be noted tlat not all of the f aculty and students who used the Radiation Center for their teaci....a and research are listed in this part. Suminary information on these peopfu is given in Tablo VI.C.1, and individual names and projects oro listed in Tables VI C,2 and VI.C.3. A. Eoculty
' Johnson, Arthur G.
Director, OSU Radiat;on Center Director, OSU institute of Nuclear Scienco and Engineenny Professor of Nuclear Engineenna Pad Radiation Health Bilich, Dan K. Research Assistant College of Veterinary Medicino
- Dinnoy, Stephen E Associate PNfossor of Nuclear Engineenna Chairman, O~TR ricactor Operations Committeo
'Conrady, Michael R.
Research Assistant Neutron Activation Analysis Specialist
'Cordoll, Sharon M, Research Assistant Radiation Protection Technologist Daniels, Malcolm Professor of Chemistry
' Reactor users for research and/or teaching.
l
._ _ . . _ . - - _ . _ _ . - _ ~ ~ . - . _ _ _ . . _ . _ . _ - _.._ . _ __ _ _ _ _ ._..
ll-2
'bodd, Brian ,
Reactor Adminktrator ! Psofessor of Nuclear Engineering Hart, Lucas P, Roscarch Associato, Chom13try
'Higgin'uotham, Jack F. !
Senior Health Physicist - Assistant Professor of Nuclear Enginocting Klein, Andrew C. ;
- Associato Professor of Nuclear Engineering ;
'Loveland, Walter D.
Professor of Chemistry MacVicar, Robert President EmSr?.us, OSU Makl, Leonard M. Profonsor of Nuclear Engineering (Visiting)
'Pastorek, Christine instructor of Chemistry ,
Popovich, Milost. l Vice Presider.t Emeritus, OSU
'Pratt, David S.
Roscarch Assistant Health Physicist .; i Royot,, Joso N, Assistant Professor of Nuclear Engineering
'Ringle, John C.
Professor of Nuclear Engineering Associate Dean of the Graduate School, OGU ,
' Robinson, Alan H.
- Head, Department'of Nuclear Engineering
- Professor of Nuclear Engineering
*Roactor users for research and/or teaching, i
n . _ ...- -,_ _ . . - . _ _ _ _ _ _ . _ _ . _ . _ . . , _ _ . . , , - - . _ _..,_.._..._.,_,..._-.s.~ . . - . . , . , _ . , , . . . - . _ , _ . _ _ _
. . _ - _ . _ . _ _ . . _ . . _ _ _ - _ ___ _. ..~._.__.m. , _ . _ . _ . . _ _ _ . - _ . . _ - . _ _ . _ _ .
1 ll 3 J Smith, Sheile K. Research Assistant I Co:lege of Veterinary Medicine ! Schmitt, Roman A. l Professor of Chemistry i Srivastava, Alek Rosearch Associate Chemistry l l Wachenhoini, Daniel E. ! Research Associate l College of Veterinary Medicine
~
Walker, Robert J. !
- Research Assistant i Gooch<4 mist Wang, Chih H.
Director Emeritus, Radiation Center , Professor ?.meritus, OSU j Young, Roy A. Professor Emeritus, OSU '
-i
?
E i i
*Roactor users for research and/or teaching .
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. B. Yhltinc Scienti tis and SnedaLDalaens !
Advisor or P.oscarch Nanni Field (Af filiadon] _ ProarantQileclot ! Dehm, Marten Nuclear Chemistry W. D. Loveland r (Swedon) ! t
- Collins, Derek Oregon Episcopal School J. F. Higginbotham I (Portland, Oregon) i r
i
*Llodtko, James D. Visiting Associate Professor A. G. Johnson i (Portland Commurdty Collogo) ,
3 Srivastava, Alok Chemistry W. D. Lovoland [ (India) > Suckow, Molissa L. Saturday Academy Montorship A. C. Klein Proprom, McNary High School i ($alem, Oregon)- ; Yanoz, Ricardo Cho ristry - W. D. Loveland I (Swedon) : i I t i l t
- 1. -;
,. *Roactor users for research and/or teaching. L e
- 1. i . .:. - -- -.: - - ..- ------------------l
t it.5 - i i C. RSAL0ntduate.S.tudmis i Dogroo ! NDmo ELQQLM1 ficM M xikot l i Abdul Hamid, Shahab A. MS Nuclear Engr. A. C. Kloin ' Ahn, Harry MS Nuclear Engr. J. N. Royos
- Al Baroudi, Homan PhD Nuclear Engr. A. C. Klein i Al Khollowl, Abdulluh S. PhD Nucioar Engt. A. C. Klein j Ala, Abbas PhD Nuclear Engr. J. N. Royos }
Anand, Ajay PhD Nuclear Engr. S. E. Binney l
*Baik, Soung Hyuk MG Radiation Health J. F. Higginbotham j Bostick, Kent C. MS Nuclear Engr. A. C, Klein i Bukar, Kyari s. MS Nuclear Engr. A. H. Robinson !
Cho, Byung-Oh MS Nucloor Engr. A. H. Robinson l Eichenborg, Thomas W. MS Nuclear Engr. J. N. Royos j Fu, Yingxian PhD Chemistry M. Danicls Giosbrecht, Stephen E. MS - Nuclear Engr. J. F. Higginbotham
'Grook, Kovin PhD Nuclear Engr. A. H. Robinson !
Groene, Kenneth PhD Nuclear Engr. A. H. Robinson r Gulshan-Arn, Zubaida MS Nuctoa: Engr. A. C.- Klein ! Hicks, Thomas MS Radiation Health B.Dodd !
'Kalns, John E. . PhD Nuclear Engr. J.N.Royou !
Kicstler, William C. MS Nuclear Engr. A. C. Klein ; King, John - PhD Nuclear Engr. J N. Royos Lafi, Abd Y. PhD- Nuclear Engt. J. N. Royos i Loo, Hsing H. MS Nucloor Engr. A. C. Klein : Lewis, Bryan R. MS Nuclear Engr. A. C. Klein ;
'Liu, Yung Gang PhD Chemistry R. A. Schmitt i Ma, Chang Chun PhD Nuclear Engr. J. N. Royos i Marks, Timothy S. MS Nuclear Engr. A. C. Klein
'Martsolf, Stovon W. MS Radiation Health S. E. Binney -
Milos, Todd L. MS Nuclear Engr. S. E. Binnoy Pauley, Keith MS Nuclear Engr. A. C. Klein Pawlowski, Ronald MS Nuclear Engr. A. C. Klein Piopmier, Edward H. PhD Pharmacy J. W. Ayres '
'Pratt, David MS Radiation Health J. F. Higginbotham l
'Saleh, Hassan PhD Nuclear Engr. S. E. Binney
'Schilk, Alan J. PhD Chemistry R. A. Schmitt :
Snuggerud, Ross D. MS Nuclear Engr. A, C. Klein ! 2ahm, Lanco MS Nuclear Engr. A. C. Klein ) i- ; i l i
- Reactor users for research and/or teaching.
. - - - , , - ~ ~ - ,,---.---, --,_ - - --- ~~~ ---,,---,- ~ n-~ . -- . .-,n~,--,c
_ _ ._.__._....____.._,__m ._. _-_.. _ . _ _ .____ _ _ - _ _ ._._ -. t
- 1. 0 D. Rusinclub.Adalu!!ittAllVMRiCICdCALSinif Director, Radiation Centor . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A. G. Johnson Business Manager . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . S. C. Campbell !
Administrativo Assistont , . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . D. K. Dalton Of fico Specialist s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . J. F. Hopkins J. R. Smith C u st od ia n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . M. L. Bonad Offico Coordinator (Nuclear Engincorin0) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . D. L. Crarner Word Processing Specialist (Nuclear En0i ncoring) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . R. A. Koon - E. HeatinLQDolAllons Einli Principio Security Of ficer . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A. G. Johnson Reactor Administrator, Senior Reactor Operator . . . . . . . . . . . . . . . . .... D.Dodd i Reactor Supervi,sor, Senior Roactor Operator . . . . . . . . . . . . . . . T. V. Anderson Senior Reactor Operator s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . S. E. Binnoy A. D. Hall J. F. Hl0ginbotham F. Bodiation Protection.S1Dif Sonlor Health Physicist . . . . . . . . . . . . . . . . . . . . , . . . . . . . . . J. F. Hi O0i nbotham Health Physicist . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . D. S. Pra t t Radiation Protection Technologist . . . . . . . . . . . . . . . . . . . . . . . . . S. M. Cordoll Health chysics Monitors (Studentr) , , . , , . . . . . . . . . . . . . . . . . . . J. Andreason C. Grior V. Moacham - C.Rak A. Roberts E. Rockott B. Tharakan
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II 7 G. Sticalific_Swnoitatnif Senior Neutron Activation Analyst . . . . . . . . R. A. Schtnitt Neutron Activation Analysis Specialist . M. R. Conrady Geochemist . . . . . . . . . . . . . . . . . R. J. Walker Neutron Activation Analysis Techniciann (Students) .. .. L. Forsythe V. Lan0er J. MacLean A. Mathis D. Princehouse E. Schuef ort M. Streck Scientific Instrument Technician . . .. . .. S. P. Smith H. QSVllD1!IQ1[Rn Sp{ sly _,DjfkpJia(( Rrdiation Safety Officer . . . . . R. H. Fartner Radiation Specialists . . . .... D. L. Harlan E, F. Forrer Socrotary ...... ........... . .... K. L. Miller I. C9fDm!1.1CfG
- 1. 'iciclor Dnerations CormDilitQ Romo MMinlips S. E. Binney, Chairman . . . ... . . . . . . . . . . . . . Nuclear EngineerinD
~
D. L. Amort . . . ... . .. . ... Electrical and Cornputer EngineerinD T. V. Anderson . . .. . ... . .. .. . . . . . Radiation Conter B. Dodd ........ ... . ... Radiation Center and Nuclear EngineerinD
- 1. F. Higd botham . ,.... .. .. Radiation Conter and Nuclear EngineerinD
. .. G. Johnson .... .......... Radiation Center and Nuclear Engineering J. C. Ringle . . . . .. ..... .. Nuclear Engineering and Graduato School A. H. Robir. son ........ .. ..... . . . . . . . . . . . . . Nuclear Engineerin0 R. A. Schmitt ... .. .. .. ., . .. Chemistry and Radiation Center W. H. Warne s . . . . . . . ...... ..... . . Mechanical EngineerinD l
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i 11 8 i
- 2. Radiation Safety Coalmitten.101U)
Nama AfIthetiRD ; J. Higginbotham, Chairman . . . . . . . Radiation Centor and Nuclear Engineering R. Farmer, Soc'otary & RSO . . . . . . . . . . . . . . . . . . . Radiation Safoty Of fico . R . C olli e r . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Oceanography l T. Dreher . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Agricultural Chemistry i D. K esz ler . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Che mist r y j S. Radosevich . . . 4 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Forest Science ; C. Rivin . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Botany and Plant Pathology : G. Rohrmann . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Agricultural Chemistry , C. Schreck . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Fisheries and Wildlif e
- 3. Radiation Center Safety Committoo ,
Hamft AffiliatioD ; W. D. Loveland, Chairman . . . . . . . . . . . . . . . . . . . . . . ....... Chemistry T. V. Ander son . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Radiation Contor S. C. Campbell . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Radiation Contor M. h. Conrady . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Radiation Contor J. F. Higginbotham . . . . . . . . . . . . . Radiation Contor and Nuclear Engincoring . A. G. Johnson . . . . . . . . . . . . . . . Radiation Conter and Nuclear Engincoring S. P. Smit h - . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Radiation Centor
- 4. [tadiation Conter TOM Team Name AffiliatioD B. Dodd, Team Leador . . . . . . . . . . Radiation Contor and Nuclear Engineerin0 J. DeMott, Facilitator . . . . . . . . . . . . . . . . . . . . . . . . . . J. DoMott Company T. V. Anderson . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Radiation Contor S. C. Campbell . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Radiation Centor i M. R. Conrad y . . , . -. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Radiation Center D. S. Pratt . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . - Radiation Contor R. J. Walker . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Radiation Contor P
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r i i . PARTlli FACll.lTIES A. ROMatslLRsK101
- 1. DncuvLion The Oregon State University TRIGA Reactor (OSTR)is a water coolod, switnming pool 1ype of rescarch roactor which uses uranium /rirconium hydrido fool olomonts in a circular grid array. The reactor core is surrounded by a ring of graphito which serves to reflect neutrons back into the core. The core is situated near tPo bottom of a 22 foot doop water filled tank, and the tank is surrounded by a concreto bioshield which acts as a radiation shield and structural support. Soo Figuros III.A.1, Ill. A.2 and Ill. A.3.
The reactor is licensed by the U.S. Nuclear Regulatory Commission to operato at a maximum steady stato power of 1.1 MW, and con also be pulsed up to a peak power of about 3000 MW. The OSTR has a number of different irradiation facilities includin0 a pneumatic transfer tube, a rotating rack, o thormai column, four beam ports, two samplo-holding (dummy) fuel elements for specialin coro irradiations, and a cadmiurn lined in-coro irradiation tube for experiments requiring a high energy noutron flux. The pneumatic transfer facility enables samplos to be inserted and removed from the coro in a few seconds. Consequently, this thcility is normally used for noutton activation analysis involving short lived radionuclidos. On the other hand, tho l rotating rack is used ior much lonDer irradiation of samplos (e.g., hours). The rack consists of a circular array of 40 tubular positions, each of which can hold two i sample tubos. The rotation of the rack onsures that each sample will receive the same amount of irradiation, l l l l
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111 5 The reactor's thermal column consists of a large stack of graphite blocks which slow down neutrons from the reactor core in order to increase thermal neutron activation of samples. Graphite blocks are removed from the thermal column to enable samples to be positioned inside for irradiation. 6 . , The beam ports are tubular penetrations in the reac'or's main co'1 crete shield ,
- which enable neutron and gamma radiation to stream from the coto when a beam port's shield plugs are remuved. Two of the OSTR's beam ports are permanently configured for neutron radiogrcphy while the other two may be used for a variety of experiments.
'If samples whico are to be irradiated iequire a large neutron fluence, especially from higher energy neutrons, then such samples may be inserted into a dummy fuel element. This device will then be placed into one of the core's inner grid positions which would normally be occupied by a fuel element. ,
The cadmium-lined in-core irradiation tube enables samples to be irradiated in a high flux region near the contar of the core. The cadmium lining in the facility eliminates thermal neutrons and .thus nrmits sample exposure to epitherrnal neutrons only. The cadmium-lirvi end of this air-filled aluminum irradiation tube is inserted into an inner Orid pc . ion of the reactor core which would normally be occupied by a fuel elemt r- >
- 2. Utilization The two main uses of the OSTR are instruction ~and research. During this reportirig c - pericd, the reactor was in use an average of 42 hours during a typical 45-hour
- work week. Hence, the reactor was used approximately 93 af the available time.
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l lil 6 i
- a. Instruction l
)
Instructional use of the reactor is twofold. First, it is used significantly for classes in nuclear engineering, radiation protection, and chemistry at both the graduate and undergraduate levels to demonstrate numerous principles which have been presented in the classroom. Basic neutron behavior is the same in small reactors as it is in large power reactors, and many demonstra- , tions and instructional experiments can be performed using the OSTR which cannot be carried out with a commercial power reactor. Shorter-term demonstration experiments are also porformed for many undergraduate students in physics, chemistry and birlogy classes, as woli as for visitors l from other universities and col!eges, frcm high schools and from public groups. The second instructional application of the OSTR involves education of reactor operators, operations mensoerc and radiation health physicists. The OSTtt is in a unique position to provido such education since curricula must include hands-on experience at an operating reactor and in associated laboratories. The many types of educational programs that the Radiation Center provides are moro fully described in Part VI (section VI.C.5) of this report, During this reporting period the OSTR accommodated 23 different OSU academic classes, in addition, portions of classes from other Oregon universities were also supported by the OSTR. The OSU teaching programs. uti" zed 569 hours of reactor time. Tables Ill.A.1 and Ill.A.2 as well as Table Ill.E.1 provide detailed information on the use of the OSTR for instruction and training.
- b. Research The OSTR is a unique and valuable tool for a wide variety of research applications, and serves as an excellent sourco of neutrons and/or gamma radiation. The most popular experimental technique requiring reactor use is
--, --.. -- _ - _ . .-. . - .. .~ . _- . . . - _ _ ,
lll-7 Tablo Ill. A.1 OSU Courses Using the OSTR Course Number Course Name NE 111 Nuclear Engineering Orientation NE 113 Nuclear Engineering Orientation I NE 233 Nuclear Radiation Detection and Measurement NE 457 Nuclear Reactor Experiments NE 479 Design Projects (Nuclear Engineering) NE 480 Field Practices in Radiation Protection (Undergraduate) NE 484 Radiation Protection Engineering NE 503 Thesis (Nuc! car Engineering) NE 580 Ficid Practices in Radiation Protection (Graduate) CH 219 General Chemistry Laboratory CH 419 Radioactive Tracer Methods CH 462 Experimental Chemistry Il CH 503 Thesis (Chemistry) CH 505 Reading and Conference CH 519 Advanced Radioactive Tracer Methods CH 576 Activation Analysis G 503 Thesis (Geology) H 344 Man, Health, and Environment J 390 Journalism Reporting OC 503 Thesis (Oceanography) PH 313 Energy Alternatives PH 503 Thesis (Physics) Summer Short Course Civil Engineering
111 8 - Table Ill.A 2 OSTR Teaching Hours Anma Cumulative Values LDescription a ues for FLIP Core-(hours) Departmental 414 3,218 Nuclear Engineering 374 Chemistry 30 Health & Human Performance 3 Journalism 3 Civil Engineering 2 Physics") 2 Geology") Oc.eanogrepity m 4 Special Classes and Projects (2' 155 -590
' Total Teaching Hours ('AH 569 3,808 (1) Some use hours by these departments are not shown under " Teaching Hours," but are
- reflected under Thesis Research, both funded and unfunded.
(2) ' A variety of educational classes were conducted which involved one-time meetings for
- orientation or support purposes. These included: high scnool science classes, new =
ctudent programs support, reactor operator orientation and training, community college classes and classes from other universities; (3) See Table Ill.E.1 for classes and student enrollment. (4) See Table IV.A.5 for a summary of all reactor uso categories. (5) Total teaching hours reflect all time the reactor was in use for teaching, and because of this the total hours include tirne the reactor itself may not actually have been in operation,
- _ _._ . .m . . _ _- . . _ . . . - . _ _ _ . _ _ . _ . . . . ~ . - . . _ . _ . . _ . _ . _ _ . _ . - - . _ - .
ill 9 [
' neutron activation analysis (NAA), This is a particularly sensitive' method of elemental analysis which is described in more detail in Part VI (section VI.C.1). Part lit.B provides a listing of equipment used in NAA at the
- Radiation Center.
The OSTR's irradiation facilities provide a wide range of neutron flux levels and neutron flux qualities, which are sufficient to meet the needs of most researchers. This is true not only for NAA, but also for other experimental techniques such as fission track dating of geological and anthropological-
- rnaterials. ,
During this reporting period, the OSTR accommadated 121 funded research projects which utilized 1,027 hours of reactor time. and 12 unfunded research projects which utilized 83 hours of reactor time. Details of the reactor's use specifica!!y for research are given in Tah!e !!! A.3. Additional g - information regarding reactor use for research, thesis and service can be found in Tables VI.C.1 through VI.C.3. In those tables OSTR use is indicated with an asterisk.
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- OSTR Research Hours !
Cumulative Values
. Types of Rasearch .- Annual Values for FLIP Core thours)
(hours) OSU Research 240 6,483 OfI-Campus Research 870 4,490 , i Total Research Hoursox2) 1,110 10,973 i k (1) Total research hours statistics: (a) 92% (10?? hours) of the tota! research hours were user-funded by federal, state, or_ other organizations. (b) 8%-(83 hours) of the total research hours wero uset-unfunded studies in , support of graduate thesis research or other academic investigations. Reactor costs for this research were absorbed (funded) by the OSU Radiation Center.
. (2)- OSTR operating hours in support of OSU teaching and research programs approximately equal the hours the OSTR operated for 'off-campus research projects. Of the eff-campus research hours OSTR recorded, nearly 5% (approximately 40 hours) weie in .
L.- direct support of research being conducted at the University of Oregon. i-t 2 l l l .- l ..
- lli 11 B. AnchticnLEm!!ar11s111 -
- 1. Descriotion The R'adiation Contor has a great variety _ of radiation detection instrumentation.
- Much of this equipment involves the latest in counting technology as represented by the eleven state of the-art gamma ray' spectrometers with their associated computers and Ge(U) or intrinsic Germanium detectors. Tables Ill.D.1 through lit.B.3 provido a brief listing of typicallaboratory counting devices present at the Center. :Much additional equipment for uso in the classroom, and an extensivo -
inventnry of portable radiation detection instrumentation are also available.
- 2. Utilization
. Radiation Center nuclear instrumentation receives intensivo use in both teachin0 and research applications. In addition, sen* ice projects also use those systerns and tho' combined use otton results in 24 hour per day schedules for many of the analytical instruments. Use_of Radiation Center equipment extends beyond that located at the Center and instrumentation is commonly made available on a.!oan
- basis to OSU researchers in other departments, t
w - --
. . - . . - - . . ~ .
l J ill.12 Tablo Ill.B.1 Radiation Contor Spectrometry Systems: Gamma, Low Energy Photon, Alpha Roi, Ef fic. Room System -(%) 9100 Adcam 1,8k Ortoc, Ortec HP Go 26.8
~B100 Adcarn 2,8k Ortec, PGT Go(Li)- 13.0 B100 Adcam 3,8k Ortoc., Canberra Go(Li) -19.4 B100 Adcam 4,8k Ortec, Ortec HP Ge 28.8 Ficat Adcain 5,8k Ortoc, Backup Analyzer N/A
- - C126 Aco 1 4k Ortec, Nal(TI) 3x3 N/A ,
C123 Ace 2. 4k Ortcc, PGT Ge(Li) 1 847 C126 2 K. ND60, Nal(TI) 3x3 - N/A A138 H.P. Scaler, Nal(TI) 2x2 N/A A146- Ace,4k Ortoc, Ortoc HP Go 30.0 A146 Ace,4k Ortec, Ortec Go(Li) 27.0 C134 4x4 k ND Micro MCA, PGT Ge(Li) 16.2 C134 4x4 k ND Micro MCA,- PGT Ge(Li) 19.3 C134 4x4 k ND Micro MCA, PGT LEP N/A-C134 4x4 k ND Micro MCA, Canberra LEP N/A' C126 Ace 3,4k Ortoc,576A Alpha Spoetromotor N/A
. . _ . _ . . . . - . _ _ . . . _ . _ _ . . . . , . ~ . _ _ _ _ . . . ~ . _ . . _ . _ _ _ _ . - . . _ . - . . _ . , _ - . . . .._... . ._
111- 1 3 1
-Tablo Ill B.2 Radiation Conter Uquid Scintillation Counting Systems
- Room' . -
System C126- Beckman, Betamate C126 Beckman, Botamate C126 Beckman, Betamate C126 Beckman, Betamate B136 - Beckman, LS 7500 0100 Se6 tie, Deits '300 + J f T e a
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1 til 14 F Table Ill.B.3 l Radiation Center Proportional Counting Systems \ r-- - - - - - - - - - Room System C126 NMC 1 PCS C126 NMO 2, PC5 C126 NMC 3, PCS A138 NMC, PCC 11T and DS 2 A138 NMC Auto Counting System w/ IBM XT
m , _ _ _ . _ . _ _ . . . _ . _ _ _ _ . _ _ _ _ _ - _ _ _ .. -. _ _ _ _ .. . w 11115
-C. Radi9hDigagJrradiation Sources
- 1. Descriotion - ,
The Radiation Center is equipped with two '0Co irradiation.f acilities: an older Budd irradiator and a Gammacell 220 irradiator. These two irradiators complement each other and ase capable of_ delivering high doses of gamma radiation over a range of dose rates to a variety of matorials. Typically, the irradiators are usod by researchers wishing to perform mutation and other biological effects studies, studies in the area of radiation chemistry, dosimeter testing, sterilization of food materials, soils, sediments and other media, gamma radiation dannage studies, and other such applications. In addition to the
- Co irradiator, the Center is also equipped with a variety of smaller
- Co, *Cs, ,
*Ra, plutonium-beryllium, and other isotopic sealed sources of various curie levels which are available for use as irradiation sources. ,
- 2. Utilization
- During this reporting period there was a diverse group of projects using the
- Co irradiators. These projects included the irradiation of a variety of biological cells as well as the irradiation of flowers and seeds. -In addition, the irradiators were used for radiation dosimeter analysis, sterilization of soveral media, and materials evaluation Data showing uses of the Budd irradiator for this reporting period are given in Table Ill.C.1. Table Ill.C.2 provides use' data for the Gammacell 220 irradiator.-
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- 11116_ . ,, . i Table Ill.C.1 Budd Co Irradiator Use (90 Ci: 7/1/90) ,
Purpose of-: . Doso Rango _ Number of Uso Timo 4 Irradiation . Samplos - (rads) - Irradiations l (hours) . Botanical ~ 5.0 x 10' ,.- -Studios Onion flowers to 4 3 74 6 1.1 10 Biological Sploon cells 2.5 x' 103 30 14 Studies - Dosimoter - TLDs, other 1.4 x 10 1 Analysis to 144 241 dosimeters 3.0 x.10 4 i-: TOTALS --, --- 178 292 I
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11119 i Table Ill.C.2 Garnmacell 220 " Co irradiator Use (6900 Ci: 7/1/90) Purpose of Dose Range Number of Use Time Irradiation Samples (rads) Irradiations (hours) Shrimp, fish cells, wood 1 x 10" t1 ckr, blood Stori:ization 57 310
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to serum, colla-4.3 x 10 7 gen, sea water, goat tissue ~ 2,5 x 10' Botanical Studies Bean seeds to 5 0.2 8.0 x 10 Dosimeter TLDs 3 x 10* 1 0.1 Analysis 1 Golf balls, 1 x 10' Material Evaluation gemstones, to 22 1.269 wood, concrete 1.5 x 10 9 TOTALS --- -- 85 1,579 mm
.J
11120 .D. X:8av Machina
- 1. l DescrlD1100 A General Electric Maxitron 300 kVp X-Ray generator is located in the Radiation Center. This device is situated in a shielded room which is large enough to -
-accommodate a wide variety of experiments. The machine is capable of operating at .300. kVp and 20 rnA, and devices for calibrating the beam intensity are availablo.
- 2. Utilization The X-Ray machine continued to be used as a radiation source where students -
could pertorm state-required radiation survoys of a fixed X-ray machine installation and carry out other safety checks required for such a facility.
. ~ - , . - - - . . _ ~ . - - . - - - - . ~ - . . - . - . . . - - - - - . - - _ . . -
111 21 . E.- 1,Aboratorien and Claserooma
- 1. Dnnfjotion- ,
- The Radiation Center is equipped with a number of different radioactive material laboratories designed to accommodate classes offered by various OSU acadomic departments or off campus groups, -
Instructional faciities avaitablo at the Conter include a laboratory especially { equipped for teaching radiochemistry and two nuclear instrumentation teaching laboratories equipped with modular sets of counting equipment which can be [ configured to accommodate a variety of experiments involving the measurement ; of many types of radiation. The Center also has two student computer rooms-equipped with microcornputers and terminals which are linked to other computers. both on and off campus. ; in addition ?to_ those dedicated instructional facilities, many other research
. laboratories and pieces of specialized equipment are regularly used for teaching.
In particular, classes are teut inely given access to appropriate state-of-the-art gamma spectroscopy equipment located in Center laboratories. A number of ; L classes also regularly use the reactor and the reactor bay as an integral part of their instructional coursework. There are two classrooms in the Radiation Center which are capable of holding . about 35 students each. In addition, there are two smaller conference rooms-
~
suitable for graduate classes and thesis examinations. As a service to the student -
. body, the Radiation Center also provides a student study room / lounge as well as an office area for the student chapter of the American Nuclear Society.
L
--This reporting period saw the continued development of a new thermal hydraulics laboratory in the space previously used by the AGN reactor. This laboratory is l being used by a member of the nuclear engineering faculty and involves the 1.
L construction of several scale loops to meet the research needs of the nuclear , ' industry. i
l:lll;221
- 2. .Mt_ilization All of the laboratories and classrooms are used extensively during the academic year. For example, a listing of 62 courses accommodated at the Radiation Center-during this reporting period along with their enrollments are given in Table Ill.E.1, Table Ill.A.1 gives a separate listing of the 23 classes specifically accommodated +
by the reactor during the reporting period, in addition, several laboratories are used for research projects throughout the year, 4 f I' l I.
111- 2 3 Table ill E 1 Student Enrollment in Nuclear Engineeving and Nuclear Science Courses Which Are Taught or Partially Taught at the Radiation Center Number of Students
- Course Credit Course Title Fail Wir.ter - Spring 1990 1991 1991 Nuclear Engineenna Courses NE 111' 3 Introduction to Nuclear Engineering 22 -
NE 112 3 Introduction to Nuclear Engineering - 25 - NE 113' 3 Intro. Nuclear Engineering & Cump. - - 21 NE 231 3 Nuclear & Radiation Physics 23 NE 232 3 Nuclear & Radiation Physics 22 NE 233' 3 Nuclear Radiation Detection & Instrumentation - 22 NE 341 3 Nucicar Materials - 28 NE 361 3 Nuclear Reactor Systems - 18 ' NE 38) 3 Principles of Radiation Safety 15 - - NE 400 1-S - Projects 1 2 2 NE 407 1 Nuclear Engineering Serrinar 12 14 16 NE 410 1 12 Internship -- 1 - NE 414 3 Nuciear Rules & Regulations - 29 NE 429 3 Engineermg Design in the Real World - 12 - NE 454 ' 3 Nuclear Reacwr Analysis 12 -- - NE 455 3 Nuclear Reactor Analysis -- 11 -- NE 456 3 Nuclear Reactor Analysis - - 11 NE 457 *
- 3 Nuclear Reactor Laboratory - -
10 NE 467 - 4 Nuclear Reactor Thermal Hydraulics 11 - - NE 471 3 Nuclear Power Systems Design 12 - NE 472 3 Nuclear Power Systems Design -- 12 - NE 473 3~ Nuclear Reactor Design -- -- 12 NE 479 1-4 Individual Design Project .5 1 3 NE 480' 1-3 Field Practice Radiation Health 4 2 1 NE 484 * ' -3 Applied Radiation Saf ety - 14 -- NE 486 - 3 Radiation Dosimetry ~ -- -
.7' "NE 501 1-15 Research - -- 1 NE 503 1 15- Thesis 9 10 9 NE 505 1-15 Reading & Conference 1 3 3 NE 507 - 1 Seminar -2 4- 3 NE 510- 1 12 Internship 1 - -
NE514 3 Advanced Nuclear Rules & Regulations - - 2
'OSTR used occasionally for demonstration and/or experiments.
OSTR used heavily.
._ - - . . - - . _ ~ _ - . - - - - -~ - -- - -- -. . - - - - - 11124 Table lit.E.1 (Continued) Number of Students l Course Credit Course Title Fall Winter Spring j 1990 1991 1991 l NE 530 3 Fusion Technologt 8 - - NE 537 3 Applications of Nuclear Techniques 3 - - NE 539N 3 Neutron Interaction Physics - 7 - NE 549 3 Low Level Waste Management - 11 - NE549* 3 Radioactive Waste: Technical & Social Issues - - 8 NE 554 3 Advanced Nuclear Reactor Analy.is 3 - NE555 3 Advanced Nuclear Reactor Analysis -- 3 - NE 556 3 Advanced Nuclear Reactor Analysis -- - 4 NE 567 4 Advanced Nuclear Reactor Theory 1 - -- NE671 3 Advanced Nuclear Power Systems Design 2 - NE 572 3 Advanced Nuclear Power Systems Design - 3 - NE$73 3 Advanced Nuclear Power Systems Design - - 3 NE 580' 13 Advanced Field Practice Radiation Health - 2 1 NE 584 3 Advanced Applied Radiation Safety - 1 - NE 586 3 Advanced Radiation Dosimetry - - 4 NE 603 1 16 Thesis (Nuclear Engineenng) 3 3 3 NE 656 3 Adv3nced Particle Physics for Reactor Analysis - -- 5 Chemistry Courses CH 219' 2 General Chemistry Lab 25 - -- CH 419 4- Radioactive Tracer Methods 4 - - CH 462' 3 Experimental Chem;stry 11 Laboratory - 12 - CH 503' 1-16 Thesis (Chemistry) 1 1 1 CH 505' 1 Reading ard Conference - 5 - CH519" 4 Advanced Radioactive Tracer Methods- 3 - - CH 576 4 Activation Analysis - 5 - Other Courses G 503* 1-16 Thesis (Geosciences) 3 3 3 H 344* 3 Introductinn to Environmental Science - 40 40 J 390' 3 Reporting
- - 1 OC 503' 1-16 Thesis (Oceanography) 1 1 1 PH 313' 3 Energy Alternatives -- -
30 PH 503' 1-16 Thesis (Physics) 1 1 1
OSTR used occasionalty for demonstration and/or experiments.
OSTR used heavily.
- Taught Summer Term.
_ _ _ _ _ . _ _ . . _ . . - . _ - _ - _ . _ - _ _ . _ m . . _ . _ _ , - _ . _ _ _ _ _ _ _ . .
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F. In51wment Renpir and Calibration Facility , _1. Descriotion
.The Radiation Center has a facihty for the sepair and calibration of essentially all ,
types of radiation monitoring instrumentation. This includes instruments for the detection and measurement of alpha, betc., gamma and neutron radiation, and encompasses both high range instruments for measmin0 intense radiation fields
- and low range instruments used to measure environmentallevels of radioactivity.
The Center's instrument calibration capability is described more completely in Sectior. k..i 7 of this oport.
- 2. .titilization The Center's instrument repair and calibration facility is used regularly throughout
- each year and is absolutely essential to the continued operation of the many different programs carried out at the Center. In addition, the absence of any comparable facility in tha state has led tu a greatly expanded instrument calibration
. program .'or the Center, including calibration of essentially all radiation detection
' instruments used by state and federal agencies in the State of Oregon.- This includes instruments used on the OSU campus, plus instruments from the Oregon Health Division's Radiation Control Section, the Oregon Department of Transpor'ta-tion, the Oregon Public Utihties Commission, the U.S. Environmental Protection Agency, and the U.S. Department of Agriculture. Additionalinformation iegarding instrument repair and calibration efforts, is given in Tables VI.C.4 and VI.C.5,
- . . -, .. _ . _,_ - , , - . _ _ . . . . . _ _ , . _ ~w
11126 G. Liht0!rJt)
- 1. Q.0ElinliQD The Radiation Center has lit,raries containing significant collections of texts, research reports, and videotapes relating to nuclear science, nuclear engineering, and radiation protection.
The Radiation Center is also a regular recipient of a great variety of publications from ccmmercial publishers in the nuclear field, from many of the professional nuclear societies, from the U.S. Department of Energy, the U.S. Nuclear Regulatory Commission and other federal agencies. Therof ft,. Conf er libratics maintain a current collection of leading research and regula;ory documentation in the nuclear area. In addition, the Center has a collection over 50 sets of nuclear powei reactor safety analysis ar.d environmental reports specifically piapared by utilities for their facilities. The Center maintains an up-to-date set of reports from such organizations b3 the International Commission on Radiological Protection, the National Courr,1 on Radiation Protection and Measurements, and the international Commission on Radiological Units. Sets of the current U.S. Coao of Federal Regulations for the U.S. Nuclear Regulatory Commission, the U.S. Department of Transportation and other appropriate federal agencies, plus regulations of various state regulatory cgencies are also available at the Center. The Radiation Center videotape library has over one hundred tapes on nuclear engineering, radiation protection and radiological emergency response. In addition, the Radiation Center usos videotapes for most of the technical orientations which are required for personnel working with radiation and radioactive rnatorials. These tapes are produced, recorded and edited by Radiation Center staff, using the Center's videotape equipment and the facilities of the OSU Communication Media Center. l
111- 2 7
- 2. L!tilization Radiation Center libraries are used mainly to provido reference material on an i; as needed basis; however, they receive extensive use during the academic year, in addition, the orientation videotapes are used intensively during the beginning of
- each term, and periodically thereafter.
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- PART IV REACTOR
- A. Qnera.tiDg Statistics For the current reporting period, some of the operating statistics for the OSTR showed a slight drop. This is largely due to the extensive maintenance and refuroishment of the reactor systems and facilities accomplished during this reporting period. Details of several of these may be found in section IV.D.1. Operating data by individual category cre given in Table IV.A.1 and annual energy production is plotted in Figure IV.A.1. Table IV.A.2 is included mainly for reference and summarizes the operating statistics for the original 20% enriched fuel.
The thermal energy generated in-the reactor during this reporting period was 38.7. megawatt days (MWD). The cumulative thermal energy generated by the FLIP core now totals 524.9 MWD from August 1,1976 through June 30,1991. Reactor use time averaged approximately 93% of the normal nine-hour, five-day per week schedule. Tables IV.A 3 through IV.A.6 detail the operating statistics applicable to this recordng
. period, s
in order to maintain ample leeway on the shutdown margiri limit, one funi element was u removed during the current nporting period. This allo ved for the expected slow
. increase in core reactivity due to the effect of the orbiurr poison burnup being greater ,
than the fuel burnup. As a result, the reactor core excess reactivity remained about the same over this reporting period.
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Table IV.A. . 4 is
' OSTR Operat:ng Statistics (Using the titP Fuel Core) '
Operationa! Data August 1,1976 July 1,1977 Jufy 1; 1978 '- ? July 1.1979 July 1,1980 ~. July 1,1981 July 1,1982 July 1,1983 for: 1 Through Through . Through .. Through .: Through ' Through - . Through . Through
< FLIP Core June 30,1977?". June '30; 1978 ' June 30,1979 - June 30,1980 . June 30,1981! June 30,1982 June to,1983 -' Jure 30,1984 Operating Hours 875 819 4r,g - '875 1255 1192: 1095 - 1205
' (critical) -
Megawatt 451 '496 255 571 1005 999 931 943 Houm Megawatt .19.0 20.6 ~ t 0.6 23.8 , 41.9 41.6 -- 38.8 39.3 Datts ass
- Grams u Used 24.0 25.9 13.4 29.8 52.5 52.4 48.6 4 ^-
s Hours at Full Power 401 481 218 552 998 973 850 - 929 (1 MW) Numbers of ' Fuel g ! Elements 85 0 2 O O 1 0 0 Added or Removed (-) Number of irradiation 44 375 329 372 348 408 396 469 Requests {1) The reactor was shutdown on July 26,1976 ter ene month in order to completely refuel the reactor with a new FLP fuel core. l l i _. ___ .._ _ _ _ _ _ _ _ _ _ . _ _ _ - _ __ _ m.. - ,.
-l
- fable IV.A.1 (contired)L I OSTR Operating Statirtics (Using the FLIP Fuel Core)
Operationa! _ , , i Data ' 'Ju!y 1,;1984 1 July 1.1985 . July 1,1986 ' ' July 1,1987 July 1 :1988 Jufy 1,1983 ' July 1,1990 . Jury 1,1991 i for" Through : Through . . ..Throuch' . Through Thrdunh ; Through ' Through. -... Through t
. -June 30,1888 ' June 30,1991 '
FUP Core ' -June 30,1985 June 30/1986 June 30,1987 June 30,1989.- . Jure 30, 1990 June 30,1992-- Operating Hours 1205 1208 .1172 1352 1170 1136 1094 ! (critical) Megawatt 946 1042 993 1001 1025 1013 . 928 Hours , j Megawstt 39.4 43.4 41.4 41.7 42.7 42.2 38.6
' Days 285 Grams U 49.5 54.4 51.9 52.3 53.6 53.0 48.5 Usad i
Hours at Full Power 904 1024 980 987 1021 10C9 909 {1 MW) Numbers of Fuel Elements 0 0 0"' -2d" 0 1, + 1 * - 1 "' Added or ; Hemoved (-) i Number of Irradiation 407 403 387 373 290 301 286 Requests . ; l (1) No fuel elements were added, but one fueled foHovver control rod was replaced. (2) Two fuel elements were removed due to ctadding deformation.
'(3) One fuel elemant removed due to cladding defo*medon and one rmw f uel eiement added. _ ,
(4) One fuei element removed for cc,re excess adjustment. b
3 Tabte IV.A.2 A OSTR Operating Statistics with the Originas (20% Enriched! Standard TRfGA Fuel Core TOTAU l Operational . Apr 1, 72 Apr 1,73 . Apr 1, 74 Apr 1, 75 Apr 1, 76
- Apr 1, 71 Ditta - Mar 8,' 67. - - Ju! 1, 68 .Ju;1,69. , JApr1,70_
Through Through ' March 67 1
. Through ~ Through Through Through Through 1 f4r 20% Through - Through . ~ Thmugh z Ju!26,76 Through - '
Mar 31,70 Mar 31,71 Mar 31,72 Mar 31,73 Mar 31, 74. . Mar 31, 75 Mar 31,76 Enriched . - Jun 30, 68 'Jan 30,69 ' I4) Ju?y 76 (1) (2) 83) s- . Core I Cperating 954 705 563 794 353 0903 904 610 567 855 598 j Hows f icritleai) 213.0 2553.0 223.8 195.1 497.8 335.9 321.5 408.0 Megawatt 117.2 102.5 138.1 Hours 14.1 13.4 17.0 3.0 106.4 4.9 4.3 5.8 9.3 8.1 20.7 Mcgawatt Days 17.6 16.8 21.4 10.7 133.0 23s u 6.1 5.4 7.2 11.7
- 0.2 26.0 Grams Used Hours at - - - - -
856 Full Power 429 369 58 - -- (250 kW) Hours at 200 291 460 205 1700 20 23 100 401 Fu!I Power - - (1 MW) Mumher of H el 2 2 2 0 94 1 1 Bements 70 2 13 1 g Added to Ordtial) Core l Number of 4'o2 396 357 217 4100 429 433 391 528 347 550 Irradiation Requests 109 183 43 39 1560 202 236 299 102 Sd 249 Number of , Puises l r (1) Reactor went critical on March 8,1967 (70 element core; 250 ;J.eL Note: TNs pr-nod length is 1.33 years as initial critica ity occurred in March of 1957, {2) Reactor shut down August 22,1969 for one mor.th for upgrading to 1 MW (did not upgrade r cw ing syster.11. Note: This period lerygth is only 0.75 years as iPere was a c in the report;ng period from July-June to April-March. (3) Reactor shut down June 1,1971 for ote month for cooling syst?rn upgrading. (4) Reactor shut down Ju!y 26,1976 for one mon:h for refueling reactor with a new full FUP fxl cofe. Note: This period ferr;tn is 0.33 years.
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IV-5 Table IV. A.3 Present OSTR Operating Statistics r Operational Data Curnulativo Values for Annual Values Ior FLIP Core F LIP Core fAWH of energy produced P28 12,b99 MWD of ener0y produced 38.0 525 Grams "U used 48.5 659.2 Number of fuel elements added to . (*) or removed frorn (+) the core -1 82 + 3 f f CR'" Nui'.ber of pulses 13 1,168 k Hours reactor critical 1,094 i',370 Hours at full powei (1 MW) 909 .2,270 l Number of startup and shuidown checks 251 3,709 . Number of irradiation requests processad* 280 5,507 Number of sarnples it;adiated 2.84 3 74,584 , (1) fuel follower Control Rod. These numtiers represent the coro loadir.tj at the end of this reporing period. _
. J (2) Each irrad:ation request could authorize from 1 to 120 samples. The number of samples per irradiation request averaged 9 during the current reporting period.
K
IV 6 l i Tablo IV.A,4 OSTR Use Time in Terms of Oper0tional renetions j i Oumulatiso Values OSTR Operational Function- Annplal Values for FLIP Core thours) (hours) ; Checkout, coro excess and 454 5,683 shutdown r Reactor in uso"' 2,750 24.903 i Total reactor use timo 3,204 30.606 (1) This function includos proclude time, multiple reactor experimont time, and tho time the roactoiis in use for teaching but not necessarily operating. (Proclude tirno is the timo the reactor is not available for regular uso duo to performanco ; of surveillanco and maintenance items, such as fuel o!oment inspections, transient rod lubrication, control rod calibration, power calibration, as well as samplo loading and unloading timo.) a f i 5 x
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IV 7 Tablo IV. A.5 OSTR Use Time in Terms of Specific Use Categories Cumulativo Values OSTR Uso Category
^""""i v8 '""" ior FLIP Coro (hours) (hours) -
Teaching ' departmental and 569 3,808 others)"' OSU research"' 240 6,483 Off campus research"' 870 4.490 Forensic services 3 158'" Reactor preclude timo 1,110 10,379 Facility timod ' 385 5,099 Visitor demonstration"4 27 249 Total reactor use timo 3,204 30,660 (1) See Tables I;l.A.2 and Ill.E.1 f or teaching statistics. (2) See Tablo Ill.A.3 for research stati, ics. (3) Prior to the 1981-1982 reporting period, forensic services were grouped undnt another uso category and the cumulative hours have been compiled beginning with the 1981-1982 report. (4) The time OSTR spent operating to meet NRC facility licenso requirements. (5) This is the time that the reactor was used specifically for visitor open-house (demonstration) ovents. The remainder of the visitors viewed the reactor durirg timos when the reactor was being operated for regularly scheduled research and teaching.
_ _ _ . _ _ _ _ . _ _ _ ~ _ _ . _ _ _ _ _ _ l i IV 8 l l Tablo IV.A.6 . OSTR Multiple Use Timo"' Cumulativo Values Annual. Values Number 'of Users for FLIP Coro i
- (hout s)
(hours) Two 135 1,500 - Threo 54 422 i Four 36 152 Fivo 21 31 l r Six 6 29 s Seven 6 10 Total multiplo use time l 258* 2,150* l (1)- Multiple 'uso timo is that time when two or more irradiation requests are being concurrently fulfilled by operation of the reactor. (2) This represents 24% of the total hours the reactor was critical during this reporting ; period. (3) This represcats 13% of the total hours the reactor was critical sinco startup with FLIP i fuelin Au0ust of 1976. l e
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_ _. - _..__ _ _ _ .. _ . _ _..m _ - - - _ _ _ _ _ _ _ . _ . . . _ _. .._. .. IV 10 B. hporlmstnts Performed During the curtont reporting period there woro 11 apptoved reactor experiments available l for use in reactor related programs. The following list of reactor experimonts identifies the 11 approved experiments. Missing numbers signify reactor experiments which are , in tho inactivo filo and are not currently being used. ' i A1 Normal TRIGA Opocation (No Samplo Irradiation). B3 Irradiation of # 4 tons in the Wandard OSTR Irradiation Facilities. B-11 Irradiation of Materiab invc .ng Specific Ouantities of Uranium and Thoriurn in the Standard Oo r.. . .adiation Facilities. B 12 Exporatoiy Experi".. ants. B 21 Beam Port No' 3 Neutron Radiography Facility; Amendment No.1 to B-21; Noutron Holography. B 23 Studios Using TRIGA Thermal Column. B 24 General Neutron Radiography. ! B 25 Neutron Flux Monitors. B49 Reactivity Worth of Fuel. B-30 NAA of Jet, Diesel, and Furnace Fuels. B 31 TRIGA Flux Mapping. Of the approved experime'its on the active list, three were us.j during the reporting-period. A tabulation of information relating to reactor experiment uso is given in Tablo IV.B.1, and includes a listing of the experiments which were used, how of ten each was l used, and the general purpose of the use. Presently,25 experiments are in the inactive filo and could be reapproved for use if needed. ; I
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m.. _ . _ _ _ . . . _ _ _ _ _ _ _ _ _ _ _ IV-11 Tablo IV.B.1 Use of OSTR Reactor Experiments'" , i
-g Reactor
. Experiment Research Teaching Forensic Facilit[ TOTAL i
*U
- Number * -
A1 1 32 N/A 91 124 B-2 120 27 1 N/A- 148 B-11 14 0 0 N/A 14 TOTAL 135 59 1 91 286 (1) This tablo displays the number of times reactor experiments woro used for a par'icular purpose. (2) The following tabulation gives the number of each reactor experiment used and its corresponding title: A-1 Normal TRIGA Operation , 03 Irradiation of. Materials in the Standard OSTR Irradiation Facilities - B 11 Irradiation of Materials involving Specific Quantities of Uranium and Thorium i in the Standard OSTR Irradiation Facilities i (3) The timo OSTR spent operating to meet NRC facility licenso requirements, 3
-7 1 . _ _ . . . _ . - _ . . . . . _ . . ~ - _ . _ _ _ _ _ _ _ - . . - _ _ _ _ _ , _ _ . . , _ . - , . . . . _ - _ . . _ . - - - - _ - , _ .
IV 13 Table IV.C.1 Unplanned Reactor Shutdowns (Scrams) Number of Type of Scram Occurrences Cause of Shutdown Manual 1 Stack monitor filter f ailure. Replacing the expired filter tape remedied the problem. Reactor opermion was resumed. Manual 2 Commercial power f ailure. Reactor operation resumed af ter the power was restored. Manual 1 Stack gas alarm. The operations group was conducting the quarterly argon response check of the stack ef fluent monitor and the stack gas alarrn sct point was not set high enough. The alarrn point was reset, the ventilation system was returned to normal, and operations were resumed. Manual 1 Period circuit problem. The reactor power would not remain steady in automatic mode. A bad capacitor was found in the period differentiating circuit. The capacitor was replaced and operation was resumed. Manual 1 Percent power safety channelion chamber not hookcd up. The ion chamber to the percent power safety channel was not re-connected to the circuit af ter the rnorr ing checkout. The oversi0ht was noticed early in the reactor power increase. The cable was re-connected and reactor operation was resumed. A design chan00 to prevent reoccurrence was also mado later. (The Reactor Operations Committee and the NRC were notified in letters dated July 16,1990.) Safety Channel 1 Squarewave overshoot. A little more reactivity than needed caused an overshoot on rquarewave. The licensed power level was not exceeded. Percent Power 1 Noise spike. The Scientific Instrument Technician Channel hooked up a meter to a 25 volt power supply while the reactor was at 1 MW. This caused a noise spike in the percent power channel scram circuit. The actual reactor power did not increase. High Voltage 1 Noisy mode switch. Randam electronic noise in the mode switch caused a high volta 0e scram when it was rotated from AUTOMATIC to STEADY STATE.
l IV 14 D. Challg tLtE.the_01ULEnl ci ityJole nctothereduren_anttoluc1913r ocilments Eeriorme(LEp.In!apito_103EfLEQ&Q The information contained in thia section of tho report providos a summary of the changes performed during the reporting period under the provisions of 10 CFR 50.59. For each item listed, we have included a brief description of the action taken and a summary of the apDlicablo safety evaluation. Althoughit may not be specifically stated in each of the following safety evaluations, all actions taken under 10 CFR 50.59 were implemented only af ter it was established by the OSTR Reactor Operations Committee (ROC) that the proposed activity did not require a change in the facility's Technical Specifications and did not introduce or create an unroviewed safety question as defined in 10 CFR 50.59(a)(2).
- 1. 10 CFR 50.59 Chanaes 'Q_t!12.Heector Facility There were 17 changes to th0 reactor f acility which woro reviewed, approved, and performud under the provisions of 1Q CFR 50.59 during the reporting period,
- a. REPLACEMENT OF THE REACTOR POWER CHART RECORDER (1) Description The previous chari recorder for reactor power was many years old and wasin need of replacement. As a result,the reactor stalf took out the old recorder and inserted a now chart recorder in its place. An evaluation by the Reactor Supervisor and the Scientific Instrument Technician resulted in the selection and purchase of a now recorder which is similar to the old recorder but has multiple ranges of input.
For example, the old chart recorder would only accept input on the range of zero to ten millivolts. However, the new chart recorder can ce operated on a zero to one hundred millivolt range which allows signal outputs from the wide rango log power channel, the fuel temperaturo channel, and the wide rango linear power instruments to be used without the need for voltago dividers. l l
IV-11 Tablo IV.B.1 Use of OSTR Reactor Experiments
- Reactor Experiment Researth i Teachin0 Forensic TOTAL 1 '*U Number th A-1 1 32 N/A 91 124 03 120 27 1 N/A 148 B-11 14 0 0 N/A 14 TOTAL 135 59 1 91 286 (1) This table displayn the number of tirnos reactor experiments wero .ised for a particular purpose.
(2) The following tabulation gives the number of each reactor experiment used and its corresponding title: A-1 Normal TRIGA Operation B-3 Irradiation of Materials in the Standard OSTR trradiation Facilities B 11 Irradiation of Materials involving Specific Quantities of Uraniurn and Thoriurn in the Standard OSTR Irradiation Facilities (3) The timo OSTR spent operating to meet NRC lacihty hconse requirements. l ___.________._______.___________________.___.______________.______....__.____._______.i
i IVe12 l l C. Unplanned Shutdgwns - Thero were nino unplanned reactor shutdowns (scrcms) dcring the current reporting - period,' Tablo IV.C.1 contains a summary of the unplanned shutdowns includirsg a brief i description of the causo of aach. f i 9 1 t 1 l
+
. l-k 9
I
.i
).
....-.:....-- .m___,.___._.___ _ - - _ _ _ _ _ _ _ _ . . _ . . _ . , _ _ . . _ _ . _ . - _ - . . . _ . . -
IV-13 l Tablo IV.C.1 i Unplanned Reactor Shutdowns (Scrams) i i Number of Type of Scram Occurrences Cause of Shutdown Manual 1 Stack monitor filter f ailuto. Replacing the expiret Ator tape remedied the problem. Reactor operation was , resumed. J Manual 2 Commercial power failure. Reactor operation resumed af ter the power was rostored. Manual 1 Stack gas alarm. The operations Oroup was conducting the quarterly ar00n responso check of the stack of fluent 1 monitor and tho teck gas alarm set point was not set hi0h enough. The alarm point was roset, the ventilation system was returned to normal, and operations were resumod, Manual 1 Period circuit problem, The reactor power would not rornain steady in automatic modo, A bad capacitor was found in the period dilforentiatin0 circuit. The capacitor was replaced and operation was resumed.
= _ .
Manual 1 Porcent power safety channelion chamber not hooked up. The ion chamber to the porcent power safety channel was not to connected to the circuit af ter the i morning checkout. The oversight was noticed early in the reactor power increase, The cable was to connected - and reactor operation was resumed. A design chango to . provent rooccurrence was also mado later, (The Reactor Operations Committee and the NRC woro notified in lotters dated July 16,1990J Safety Channel 1 Squarowave overshoot, A little more reactivity than needed caused an overshoot on squarowave Tha licensed power lovel was not excooded. Porcent Power 1 Noiso spiko. The Scientific Instrument Technician Channel hooked up a meter to a 25 volt power supply while the r reactor was at 1 MW.~ This caused a noise spiko in the percent power channel scram circuit. The actual reactor power did not increase. High Voltago 1 Noisy modo switch. Random electronic noise in the modo switch caused a high voltage scram when it was rotated from AUTOMATIC to STEADY STATE.
, _ . . _ _ _ _ _ _ _ _ _ _ _ _ . ~ . - _ _ _ _ - _ _ . - _ _ _ _
l IV 14 ' D. ChanneaJu_the_QSIB_Encill1rdolcaclothocedur a santtolcactoLInni.ments Ec rio r m o d.htL51!Ar1L19_1Q.Cffl.5Q19 I The information contained in this section of the report providos a summary of the - changes performed during the reporting period under the provisions of 10 CFR 50,59. For each item listed, we have included a brief description of iho action taken and a summary of the applicable safety evaluation. Althou0h it may not bo spqcifically stated ' in each of the following safety evaluations, ell actions taken under 10 CFR 50.59 were Implemented only after it was established by the OSTR Reactor Operations Committoo (ROC) that the proposed activity did not require a change in the facility's Technical Specifications and did not introduce or create an unroviewod safety question as defined .. In 10 CFR 50.59(a)(2).
- 1. .10 CFR 50,59 Channes to the Reactor Facility There woro 17 changes to the reactor f acility which were reviewed, approved, and performed under the provisions of 19 CFR 50.59 during the reporting porlod.
i
- a. REPLACEMENT OF THE REACTOR POWER CHART RECORDER (1) Description '
The prcvious chart recorder for reactor power was many years old and was in nood of replacement. As a result, the reactor stafI took out the ' old recorder and insorted a now chart recorder in its place. An evaluation by the Reactor Supervisor and the Scientific Instrument Technician resulted in the selection and purchase of a now recorder which is similar to the old recorder but has multiple rangos of input. For example, the old chart recordor would only accept input on the rango of zero to ten millivolts. However, the now chart recorder can be operated on a zero to one hundred millivolt range which allows. signal outputs from the wide range log power channel, the fuel i temperature channel, and the wide range linear power instruva 3 be used without the nood for voltage dividers, l o I l l r
,_ +,,, . . - , . . - . . m.,,,,,,,,,,n-. ,,,-.,-.~.r- , ,- + y . - ,. . . . - ,. . - - . - . , . - - - . , . . . . .
IV-15 l l Tho zero to one hundred millivolt range on the new recorder required a modification to the originallinear channel circuit which changed two , resistors and one potentiomotor in order to provido the propor output f from the n-v circuit during pulso operation. No other circuits were af facted by this change. f (2) Safety Evaluation l Caro was taken to ensure that the now recorder met or cxcooded all of , the specifications of the recorder it replaced. The installation of the now recorder was supervised by the Scientific Instrument Technician, f Upon completion of the installation, a number of chocks woro performed by the Scientific Instrument Technician and the Reactor Supervisor to ensure that the recorder, the wido range log channel, the ! fuel temperature channol, the wide range linoar power channel and the n v circuit were functioning correctly before toutino operation of the. , reactor was resumed. Replacement of the recorder will result in increased safety because the now device is much loss likely to f ail than . the old one. Additionally, elimination of the voltage dividers will ! increase the offective input impedance of the recorder channels from ten kohms to fivo mogohms as well as eliminating a primo location for picking up noise in the circuits. Furthormore, the rnagnitydo of any noise picked up will be greatly reduced with the now recorder enabling i it to track the reactor power more responsively and steadily than the 't old recorder. This will also contribute to increased safety.
' b. REMOVAL OF ONE FUEL ELEMENT FROM THE G RING (1) Description As a result of a routine measuromont of the shutdown margin (SDM),
as defined by the Technical Specifications (TS), the value was found , to be approximately 60.85. One fuel oloment was removed from the ' G7 core position in order to increase the SDM and croate a greator differenco between the SDM and the TS limit of $0.57. From previous r .~. . . . . . . _ . , . -_. _. _ _ . _ . . _..-..-.m.- _ - . . . . _ - - , _ ,,,..,,..__w..,~._ , . . .
1 IV 10 exponence and measurements it was expected that the removal of a G ring clomont would increase the SOM to about $1.10. Because the fuel element removal required recalibration of the control tods, the chango was modo just before the scheduled rod calibrations in the beginning of August. The romuvod element was placed in a convo-nient location in the Y fuel storage rock. This fuel element movement also nocessitated a minor chango in OSTROP 10.7.B. including the associated
- NOTE," and a chango in OSTROP 11.D.2 rogarding fuel handling. A summary of thoso changos follows. Normally, a fuel olomont in the B-ring (gonerally B1)is moved to GG when using the sample-holding durnmy fuel olomont or the CLICIT. As a result of removing G7,it is now botter to move the B1 elomont to G7. Thorofore,10.7,0 was changed to: "Using standard procedutos, move the fuel olomont from the B1 position to G7," and the NOTE was changed to reflect the intended use of the G7 position.
Corresponding changes were also modo in OSTROP 11.D 2 regarding uso of the G7 position. (2) Safety Evaluation Removing a fuel element increased the already sufficient shutdown margin of the reactor, and thus slightly increased reactor sofoty. The movement was performed using standerd, approved fuel handling procedures. The olomont was stored in a fuel storage rock which is largely empty, but which was analyzed to be sufficiently sub-critical even when completely full. Removing one element from the coro does not result in a change to tho OSTR physical security category because the mass of non self protecting assU ls stillless than 1 kg. Changing OSTROP 10 and 11 as detailed above ensures that all of the FLIP fuel elements will remain in a contiguous grouping and will, therefore, give a better core configuration than just putting B1 in G6 and leaving G7 vacant, i
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IV 17 l l
- c. REPLACEMENT OF THE SIGNAL CABLE PATCH PANEL FOR THE SAFETY AND PERCENT POWER CHANNELS (1) Description I l
As a f osult of the reportable event which occurred on July 11,1990, the reactor staff replaced the signal cable patch panel for the safety and porcent power channels. The original panol was replaced with a relay and a rotary switched system which oliminatos the need to disconnect and reconnect signal cables to the patch panol, and allows switching of the picoammotor to one of four positions. The positions are: Position O. Normal; i Position 1. Wido Rango Fission Chamber . Position 2. Safety Channel Chamber Position J. Porcent Power Channel Chamber When the picoammotor is switched to positions 2 or 3 the current , coming from the corresponding ion chamber is measurable on the picoammeter. During this time the rest of the circuit is disconnected from the chamber, and a rod withdrawal prohibit interlock is activated. Therefore,it is not possible to operate the reactor while the switch is in positions 2 or 3. l The nood for position 1 was not related to the reportablo event, but ; was incorporated at this time for convenience. Its addition restored the capability to use the picoammotor to measure the current from the fission chomber while the fission chamber is be!r.g used for normal l- reactor operation. This was possible in the past, and is useful in determining the linearity of responto of the linear channel and the chart recorder. Appropriate procedures were modified to describe the proper operation ; of the new system.
- 4 L.-.-_-.--.--- --~ - - _ - - - . - . + --
I IV 10 (2) Safety Evaluation i Hoplacing the signal cable patch panel with the now system definitely onhanced safety by ieducing the dependence on procedural controls to ensure propor connections of signal cables from the safety and porcent power channels. Additionally, the now system makes it physically impossiblo to operato tho toactor unless the safety and porcent power channels are properly connected. The relay and switch system was carefully designed to enable proper switching of the low current circuits, and to be fait safe. If the mercury wetted relays should fail, then thny will f ail in a manner which ensures that the circuits will bo , proporly connected. Such a failure will be noticed during the next startup check when an attempt is made to rnoasuro detoctor curront. , Allowing the fission chamber current to be accuratoly monitored on tho picoammotor during reactor operation has proved to be very usefulin the past and contributos to the increased assurance of correct operation of that channel. The connection to which the picoammotor is attached is an output specifically designed by the manufacturer for
- a remote roadout such as a recorder or motor. No failuro mechanism -
can be dotorminod which would result in any foodback to the fission chambor's circuits as a result of attaching the picoammotor,
- d. MOVEMENT OF THE LOCATION OF THE OSTR STACK SMOKE DETECTOR ,
(1) Descriptinn , An on-going investigation of the OSTR stack smoke dotector revealed . that the detector itself was functional, yet its positioning was such that its smoke detecting of ficiency would be significantly improved by relocating the detector. A representative of the manufacturer felt that } improved operation would be possible due to the pressure differentials and turbulence present at the detector's current location. Therefore, following the advice of the representativo, the reactor staff moved the detector to a location which was upstream of the reactor bay exhaust fan instead of downstream. _ e- __,..;__,_ ., _ _. --_,_ _ _, _ ,__, _ _ _ ._ ____._u_ ,,
IV 19 (2) Safety Evaluation ! This facility chango enhanced safety, because the detector's smoko l detecting ability has been improved. Af ter being relocated, the detector was again tested to ensure that it functionod properly. The change of location introducod no safety implications with respect to the reactor bay ventilation system, which continues to function normally. Relocation of the detector only required that a small holo be modo in the ducting at the now location. The old hole was appropri-ately plugged.
- e. CLEANING THE ROTATING RACK IRR.ADIATION FACILITY (1) Description As a result of nearly 25 years of operation, the rotating rock had become increasingly difficult to turn. On soveral occasions the torque required to turn the rack had reached a point where the clutch assembly slipped and the rack's rotation either slowed significantly or stopped. Attempts had been made to rectify the situation by lubricat-
, ing and cleaning the drive mechanism. However, in each caso the efforts seemed to provide only a temporary solution to the problem. The reactor operations staff felt that the rack's resistance to rotation - was due to a buildup of sticky irradiated oil and not due to any , mechanical problem. The rationato for this argument was the caso - e with which the rack's rotation could be temporarily improved by further lubrication. In order to provide a long term solution to the rotational resistance in the rack assembly, the reactor operations staff used a cleaning _ [ technique recommended by General Atomics, the rack's manuf actuier.- < Mere specifically, the staff filled the rotaling rack with Simplo Green,
- an over the-counter non-organic and non-corrosive liquid degreaser, and then rotated the rack for five days. This provided adequate time and agitation to dissolve and remove the irradiated oil from the rack's
. _ _ _ _ _ . . . . _ _ . _ , - . , . . . , , , , . . , _ , , , . . ...,.~.,,_.,.._.,,,m.,, .._.,_,...,-,,.m,, ,,,..___.m - . . ...mm.._..
IV-20 chain, sprocket and boorings. The Simple Groon was then pumped from the rack, and the rack was flushed three timos with water to clean out the remaining Simple Green and contaminants The system and proceduro used for pumping the Simplo Groon and
- water in and out of the rotating rack was approved after much discussion by the Reactor Operations Committoo, All valvos, hosos and drums woro positioned, leak tostod, and shielded, as appropriato and practical, to minimizo personnel exposure, Great caro was taken in drying ar'd decontaminating the rack and samplo loading tube. Overall, the cleaning was, very successful with the rack now turning frooly.
(2) Safety Evaluation The rotating rack assemblyis an air filled system which is isolated from the reactor primary coolant by its aluminum housing Thoroforo, no interaction betwoon the Simple Groon and the reactor water was possiblo. Simpio Green is a commercial, household product which is an aqueous-based cleaning and degreasing compound, and it was concluded that no problems would be created even if it did conhet the primary wator. The Material Safety Data Sheet (MSDS) indicated that the only hato,dous material component was 2% by volume butyl collosolvo. Since the volume used was small (10 gallons), it was dotormined that it yvould not create a mixed waste disposal problom, and it was further determined that the absorbed liquid material would be ' accepted by Allied Ecology Services Inc. for disposal at their Richland, Washington low-level radioactive wasto disposal sito. ' Discussions with the manufacturer indicated that Simplo Green is used extensively in the nuclear industry as a docontaminating agent. Tests woro performed to provide assurance that Simpio Green would not attack metals or plastics, and neutron activation analysis indicated that the only significant activation products were isotopes of sodium and t '- a w ,
.-m- ---ne- w ,e,- - rN~ vwem v,--o-wN, v w- -w w g o Ns-- .- ---- - ~ , - .n <c-w ~ , m - w w , wom--r- ,eoev,e--~e-v- v
i i IV 21 : I potassium. The reason for leaving the Simple Green in the rack for fivo ! days was based on tests potformed at the OSTR which indicated that l it required soveral hours for Simple Green to adequately sotton and dissolve the irradiated oil. The pumping, air filtration and radiation monitoring systoms woro very l caref ully designod to minimizo any potential for personnel exposuro or l radioactivo material release during the cleaning process. As much as reasonably possible, drums and hosos which contained radioactive material were shioided, and all potentially contaminated air was filtored many timos as well as monitored at least twico prior to dischargo. Radiation dose ratos woro directly rnonitored at all times during tho - operation by OSTR statt and appropriato protectivo clothing and dosimetry woro worn, ! t The systern ornponents wnich were on the reactor top woro posi-I tioned se that the hea;/ shiolding was directly over tho solid concreto reactor tank pedestaland not on the cantilovered portion of the reactor top.
- f. REPLACEMENT OF THE EMERGENCY POWER SYSTEM INVERTER I
7AT'ERIES AND DATTERY ENCLOSURE
'1)
. Descr!ption The originr) tevolt battery system f or the omorgency power inverter did not secr.i to have sufficient reservo capacity to provide the required degroo of rapid response to electrical power variations. Furthermore, the batterios were of a'non standard typo which woro costly and ;
required special ordering each time they noodod replacing. Therefore, jl to increase reliability and reduce the cost of annual upkoop, the reactor ; l' operations staff replaced the omorgency power system's batteries. ; The original o'nclosuro with twenty 6 volt batteries connected in series
- was replaced with a now, specially dorigned enclosure containing ton 12 volt deep cycle batteries connected in series. +
i 1 -. li . - - . -
IV 22 (2) Safety Evaluation The chango mado the ornorgency power system more reliablo by reducing the number of interconnecting cables and toiminals, and by 4 1-@cing the original bottorios with bottorios having a inuch greator nu o shour capacity. Although the omorgency L'attorios do not VMt contribute to reactor safety, it is clear that this chango p@bs reator assuranco of desired emergency powes system operation when nooded, and it will thorofore increate the ability to ' rnonitor various paramotors imtpodiately af ter a commercial p0 Wor failure. In addition, the now batteries are availablo loc. illy, olirninating tho throo wack load time that was previously required to oplaco a defective battery.
- g. REACTOR CONSOLE LEFT HAND DRAWER MODIFICATIONS (1) Description The reactor stafI modified the left hand drawor of the reactor control consolo by moving the two test buttons for the high voltage scrams '
from the interior of the drawer to the front panol. At the same timo, ; the log power / fuel temperatu o motor in the drawor was replaced to- ! oliminato non linearity probic.ns associatod with thoso channels which ; had boon traced to the motor, (2) Safety Evaluation Installing the two high voltage scram test buttons on tho front panol of the icf t hand drawer climinated the daliy opening and closing of the drawer, and thus increased safety by reducing the r,ossibility of ; premature failure of the cablos which ontored througti the roar of the drawer due to repeated flexing. Additionally, the chango eliminated - the nood for the operator to reach into on.onorgirod drawor and, thoroforo, eliminated any possibility of cloctrical shock,
, = .- . .-. -- - - - - - -- - -. -. - -
i IV 23 4 The now meter movement was checked for linearity and smooth ! operation prior to installation. Thort.!oro, replacing the log power / fuel ! temperature rnoter movement with a now identical motor increased } safety by climinating the nood for non linoarity corrections. i
- h. MODIFICATION TO YHE REACTOR CONSOLE SEfWO SYSTEM (1) . Description j
When the now rest 2to: consolo chart recotder was it'stallod, a number l of tests woro performed to ensure that the recorder was funct!oning correctly. During those tests there appeared to be a small thif t in tho , t indicated reactor power level when the rnodo switch was moved from j the squato' wave to the eutomatic position, it rippears that this ! situation was olways present, but that it was recently more noticeable due to a more sensitivo and responsive recordor. An investigation of the servo system circuitry by the Scientific instrument Tocholcian reveriled that the po, lod rimplifier was sending a positivo 0.75 voit slanal to the servo limitor when the reactor period - was infinito. The servo system interproted this voltago as a positivo f pinlod and, as a result, regulated the actual reactor power to a loval about fivo poncent below the demand 50tting when the modo switch f was in the automatic positteni When the modo switch was in the square wave position thoro was no input from the period amplitior and, l therefore,in this configuration the actual power was regulated to bo the same as the percent power demand sotting. It should be recog-f nind that in each caso the indicated power was correct, but that in l r the automatic modo the power'was s5ghtly lower than the porcont power domand setting. In response to the above situation, the Scientific Instrument Technician constructed and installad an amplifier circuit with unit gain and an adjustablo offset of the input signal. This amplifier receives the period
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IV;24 ' 1
, i i
amplifior output from the ! sit hand drawar and then providos a I corrected input to the servo limitor. The ornplifier was constructed on ' a printed circuit board and installed in an existing open slot in the servo ' card box. l t (2) Safoty Evaluation i The change was discussed with electronics personnel at Gonoral Atomics. They ecncurred with our approach and could soo no reason not to proceed. Tho chango to the circuit has onhanced safety by i
- olirninating the shift in Icactor power which occurred when the modo switch was rnoved betwoon the square wovo and the automatic c position. - The high input resistanco of this circuit climinatos the possibility of a f ailure in this circuit which would in ony way inhibit the f operation of the reactor porlod scram. Should a failure occur that would cause the output of this circuit to increase, then tho servo i system would respond by driving the regulating rod in and lowering power, if the circuit failed .with the output low, the servo system !
would respond by withdrawing the regulating rod and raising power, in this caso, the eparator would manually scram the reactor, or without ! operator action, the power increase would be terminated by chher a-high power scram or a reactor period scram depending on the initial i h power level. This situation would be no different than if, for examplo, the console power supply providing ~a positivo voltage to the sorvu - syntom should Iail. Thoroforo,it is clear that Ihis failuro modo does not ' present an unroviewod safety question, t installing the amplifior in the servo card box prov,idos a protected 4
- environrrient for this circuit- and helps- onsure a~ long trouble froo; existence -
b
-, ,-o,,,-.... ,,c- . , _ - , . . , , _ . - . - - - ,,,,.._.--,,,_,__..m- . , - . - , . . _ . . . _ . - - -- ~-__.-.___
IV 26 1 i I. TEMPORARY ADDITION OF A WATER TRAP TO THE ROTATING RACK VENT LINE l 4 1 (1) Description in ordor to spood up the drying of the rotating rack subsequent to the { cleaning and flushing, the reactor staliinserted a temporary water trap , betwoon the loading tube and the first particulato and charcoal filter. At the time,it appot: rod as though drying was being hindered by the presence of the filters due to the moisture dripping back down tho l Inading tubo. By putting a simplo water trop before the filters it was ' reasonod that this moisturo could bo removed more officiently. The i rotating tack vant system was kept running continuously until the rack dried out. 9 A (2) Safety Evaluation i There wero no safety implications associated with this small change in i the rotating tack vent system. The trap was simply placed in the vont line with quick disconnect fittings to f acilitato insertion and romoval as necessary. All of the filtera romained in lino, and any radioactivo
. material ccliected in the trap was routinely monitorod, with thu material being disposed of as radioactive wasto, if necessary. Tho same security locking device was used for the loading tubo as was used during the cleaning process.-
i
), RESIN FLUSH / FILL AND WATER MAKE UP SYSTEM (1) Description lI The reactor operations and hoalth physics staff modified the primary
'vatar derninoralizedpurification loop by adding a system which is used to flush spent resins and add fresh resins to tho ion exchange colurnn, and to provide make-up water to the reactor primary cooling system or bulk shield tank. One of the reasons this system was installed was to i virtually eliminato the already small quantity of radioactivity which was previously drained W a hold-up tank during the resin liush and fill l.
IVJ 26 process, in addition, the system providos tho option to uso distilled water for the reactor and bulk shield tank make-up in order to prolong resin life and further reduce water dischargos to the hold up tank. Two now tanks (a make up water tarik and a resin dowatoring tub) are located along the east wall of the heat exchanger room behind the heat exchanger, while the pump and the plumbing for the now system woro placed at conveniorit locations in that same area. For resin flush, water is pumped from the make-up tank through the domineraliror to a sack in a plastic crate. This crato is raised sulficient-
!y high in the resin dowatering tub to enable the water to drain from the resin without any further handling. The water in the dowatering tub can then be easily pumped back into the make-up tank, For resin fill, water is pumped from the make-up tank through the new resin funnelinto the domineralizer and back to the make-urs tank. Mako up water for reactor systems is added by pumping water from the mako-up tank through the domineratirer to the reactor tank or bulk. shield '
tank, as necessary. (2) Safety Evaluation i. Thesa f acility changes have no of fect on reactor safety in any way, in essence, there is little difference in the resin change process and the water mako up proceduros except that there is a plumbod, closed l system with the option to uso distilled water instead of a once-through city water flush and fill. There may be a slight improvement in reactor
-safety by adding distilled make up water, but the offect is very srnall because the volume of water added is small compared to the reactor tank volume.
The major benefit of this chango is enhancement of the Contor's I ALARA commitment in that there will be a reduction in the radioactivity which will be drained to the hold-up tank. This willin turn L p , f9g. ,. y ++*^7 yaer si w v'--wWwe ur = '""**
_ . . _ . _ _ _ _ _ _ _ _ _ _ _ . _ , _ . _ _ _ _ . _ -~ ~_ _ . - _ . _ _ . . _ . _ .
)
i . e IV-27 , reduce the already ymy srnall amount of radioactivity dischargod to tho sanitary sewer to levels which will probably bo below the limits of i detection. This is consistent with the University's policy and the principles of ALARA. (3) Conforming Procedural Chango8 - OSTROP 7 was revised to add a now section on changing the domineralizor resin using the now system. Appropriate health physics precautions were also added, in addition, section 7.8.A.4 on water ; make up was changed so that it conforms to the now hardware. > i
- k. CHANGE TO THE AIR INTAKE DAMPERS IN THE REACTOR B.' ' VENTILA- i TION SYSTEM (1) Description The pair of air intako dampers for the reactor bay ventilation system were operated by two pneumatic rnotors. One motor was located on j
euch side of the unit which housed the two air intake dampors, and the motors were crupled together through the dampers so that both motors attempted to open and close both of the intake dampers. This P did not scom to be the best design. If the speed of operation of each motor was not exactly equal (i.e.,if the motors attempted to open the dampers at difforent rates of speed), the motors worked against each other, This uneven force increased the stress on the mechanical components of the dampers a?d to ucod the overali ef ficiency of the n dampor closing process. '
' As a result of the above situation, the reactor staff made a small ,
modification which allows two alternato methods of operating the pair i l~ of intake dampers. Approval for both methods was obtained which allows operational flexibility without the nood for further analysis and ' approval. The first a:ternative arrangement results in the dampers
)
l ' being coupled and operated by one pneumatic motor while the other L
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IV-28 motor is disconnectod. The second arrangement involves having each pneumatic motor operato only the dampor on its sido of the damper unit. In this second arrangement, the dampers are docoupled and the motors each indopondently work one of the dampors. (2) Safety Evaluation it should first be noted that the damper system is of a f ail-sato design, i The pneumatic motors koop the dampors opon by *he action of . 5 compressed air. Any conceivable failure would result in air leakago which in turn would cause the motors to close the dampers in I response to the action of a largo spring. In addition, the dampors are designed so that if tnoy are disconnected from the motor-for any reason they will close under the action of gravity. Both of the alternative modos of operation involvo separating tho-action of the two pneumatic rnotors. This is considered a design improvement sinco it oliminatos the possibility that the two motors will r work against each othat, which in turn improves the reliability of the I mechanical aspects of the intoko _ dampers and results i. a more consistoat and smooth closing action. + Doth of the dampers can easily be operated by one pnoumatic motor, due to the fact that the dampors operato very freely and there is very little resistance to overcome. ' Having the ability to use only one motor to operate the dampers will increase operational flexibility, especially should one motor requito maintenance. Tosts have shown that one motor can easily closo all of the dampers well within the specified 5-- second response time. l . The second alternativo has each pneumatic motor operating one of the dampers. Due to the fail safo nature of the damper design,it can bo l seen that this is clearly an improvement over the old system. With this L arrangement, the dampor motors do not work against each other, and
\
I
- L . _ . _ _ _ u _ _ _ _ _ . _ _ _ _.2 _ _ _ _ _ _ _ .
_- - = IV 29 there is an allowance for variations in the individual closing rato of each of the dampers. However, each motor is still required to close tha damper it controls within the 5 seconds stated in the Safety Analysts Report.
- l. REPLACEMENT OF THE REACTOR TOP / CONTROL ROOM PHONE (1) Description l l
The phone between the reactor top and the control room was not -l
- functioning as rollably as desired. It was dotormined that there was an )
intermittent problem with the phone wire. Consequently, the reactor l staff completely replaced the wirin0 and power supply. On the old s(stem the wires woro routed to room D106 where the phono's power supply was located. The now systom usos the + 25 volt power supply in the reactor consolo and now wires were run directly from the control room to the reactor- top, in addition a now buner system war- , designed and installed. (2) Safety Evaluation The only aspect of this minor facility chan00 which nooded ovaluating was the plan to use the +25 volt power supply from the reactor consolo. The consolo 25 volt DC power supply is rated at 1.5 amps. Before adding the phone, the current loadings were about 500 milliamps for the + 25 volt supply and 300 milliamps for the 25 volt supply. The now circuit adds about 300 milliamps of load to tho + 25 volt power supply when in use. Clearly this extra load is very small and still weil within the range of the reactor consolo power supply. No existin0 resctor' wiring was interfered with when the now system was installed. l . e- ww* y,- - v w ni g-vem -v w y =www,- ,m+,-ww1-m,,..ves - % w ~,- w -*e w ee e w v e r-wwg c w- y--ig , e- y -w-wet *g-m-w-a-+w, -
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IV 30 in. REACTOR TANK WATER LEVEL FLOAT / SWITCH REPLACEMENT (1) Description A new reactor tank water level float and switch assembly was designed, fabricated and installed in place of the old float and switches. The new float and switch assembly has two floats with very sensitive high and low water level microswitches for each float. The circuit is arranged such that actuation of only one microswitch is needed to cause control room annunciatier and a green light alarm.
'.2) Safety Evoluation The riew ficat system is engineered better than the previous system, 6 It has a sturdy, welded brar ket which is attached to the reactor tank in an out-of-the-way location. The new system has duplicate floats and more ser'sitive micro-switchcn which will increase safety by providing redundancy and increased sensitivity. In addition, the new ryttem has an indicator gauge marked on the front which makes it easier to observe changas in the reactor tank's water level due to evaporation.
i The new flor t system was thoroughly tested af ter installation to ensure that it was functioning correctly. This test included actually raising and lowering the water level to initiate thu espective alarms,
- n. REACTOR CONSOLE WlRING CLEANJP (1) Description Over the years, the numerous modifications and additions to the reactor console resulted in a maze of wiring which was untidy and inefficient There were several wires which were no longer in use, but their presence made it difficult to trace wires. These wires also may have been potential sources of electrical noise. The Scientific instrumcat Technician cleanad up the console wiring generally, and wired several systems more tidily arid efficiently by routing them to
IV 31 their destination, rather than '.o several locations across the console. I In addition, the specific chinges dotdad below wort m e. These changes have made it be'ag mu-h easier to trace wim .md have reduced potential sourcea of electrical noise. r Specific changes v.*ero: (a) The console power, domineralizer pump power, and fluke temperature indicator power were hardwired to a dodicated terminal board, Previouuly they were plugged into J power strip, (b) The wiring and parts for the claxon horn which were no longer used woro removed.
-(c) ~ The wiring to the switches / annunciators on the reactor console (
were completeiy replaced. (d) The cabling and wirias associated with the old fission chamber and its drive were tidied up. (2) Safety Evaluation There were no changes associated with the reactor consolo wiring : cleanupi Therefore, there -were rio unreviewed safety questions involved. - Howaver, the nature of this work was such that the staf f , felt that it should be reviewed by thePOC prior to implementation. The wiring cleanup resulted in a tidy console with old unused wires removed, and:with existing wires properly connected and bundled.
-- This will make it much easier to trace connections when pr'oblems are -
discoverod, and it will also minimize elec'.rical noise, As each part cf the wiring cleanup was accomplished, the systems - associated with that part were tested to ensure that they were fully functional.
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l IV 32! l l l
- o. ADDITION OF NEW VALVES AND REPLACEMENT OF DEMINERALIZER -
SYSTEM PIPING (1) Description As one of the follow-up actions associated with an occurrenco involving leakage of water from the domineralizor system, two now-valves weio placed in the system so that it could bo isolated nearer the reactor **,nk. The new two-way valves are made of stainless stool and replaced the original plastic three way valves DV1 and DV18. In - conjunction with the valvo replacements, the old Schedulo 40 plastic ' pipin{, between the reactor tank and the domineralizer skid was replacnd with now Scheduto 80 plastic piping. New pico supports were installed in various locations in the trench. (2) Safety Evaluation The valve additions and the new piping will reduce the already small probability of a domineralizer system leak, and will thereby enhance , safety. The original piping was of a lighter gauge plastic and it had been in uso, and exposed to fluorescent lights, for many years, in-addition, it had relatively few supporting hangers on some of the horizontal runs in the tronch. Therefore, replacinn the piping with newer, stronger pipe with additional suppor - 9 reduced the probability of failure, it mado senso to procet 1 .m tre pipo replace-mont at the same time the now valvos were bon.;, m. stalled. Replacing DV1 and DV18 with now stainioss steel valvos will enable thoni to be opened and closed each day with less wear and greater-reliability. This, in turn, will ensure that the domineralizer system is
- isolated closer to the reactor tank than was previously possible, further
_i reducing the probability of water leakage. There is no need for three-way valves any more due to earlier piping changes. All the usual water
- flow lineups are possible with the now valves. To get better pipe runs, the new valves were located on the south side of the reactor shield on the second level rather than on the second level railing where DV1 and OV18 were originally positioned.
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IV 33
- p. HIGH VOLTAGE SCRAM ANNUNCIATOR LOCK IN (1)- Description The three reactor power detectors (two ion chambers and a fission chamber) each require a high voltage power supply. If any of these high voltages drop significantly, then a so-called "high voltage" scram will result. (It is actually a voltage from the high voltage supply which is too low.) As the system was originally configured, only one of the
. thiec high voltage scrams (HV2) would lock in an annunciator.
Therefore,if a scram occurred via HV1 or HV3 the operator tvould not know which of these channels had caused the scram. The Scientific Instrument Technician designed and incorporated a change which now enables each of the high voltage scrams to lock in and annunciate. HV1 in the left-hand drawer was mod:fied to be consistent with HV2, and HV3 uses a new relay as a lock in feature. (2) Safety Evaluation The changes enable any high voltage scram to be identified by a light which remains on even after the transient conditions. This in turn allows more rapid identification of potential causes of the trip. The . circuit changes are all designed to be fail safe and are independent of the functional requirements of the fission chamber and ion chambers. in particular, the detectors' high voltage circuits ore unaffected by the change. This means that a detector's high voltage could return and
. the detector resume norma) operation regardless of whether or not its *
~ high voltage scram annunciator is reset.
l l L L
l IV 34
- q. REPLACEMENT OF THE PERCENT DEMAND CONTROL KNOB (1) Description The original Wdemand control knob had a range from zero to 100%
and could not be tur,,ed above 100%. When the reactor operates at 1 MW in automatic modo, thero is a need to be able to adjuct the knob up or down a small amount on either side of the 100% power setting. For this reason, the console was set up so that 100% of the power for any given power range (selected via the nower rango switch) was equivalent to about the 95% setting on tb A demand control knob. This maant the operator could not set the Wdemand knob exactly at the desired power level, but instead had to set the knob about 5% low. To remedy this situation and to enable the desired power level to be dialed in, the Scientific instrument Technician installed a dif forent style knob. The r.ow knob necessitated a small change in the circuitry to , enable the 10 turn potentiometer to cover the voltage range needed. in addition, to provide better voltago stability, the 1.3 k0 resistor was replaced by an active voltage regulator. The voltage rango covered by the potentiometer was shifted to enable the new knob to vary from 10% to 110% of the power indicated on the range switch. (2) Safety Evaluation The changes which were mado will result in increased sefety. Prior to the changes,it appeared that any changing load demands on the + 25 V power supply resulted in the need for slight changes in the W demand potentiometer setting. Replacing the resistor with the voltage regulator has eliminated any variation in the voltage seen by the potentiometer and has resulted in more stable operation. Changing the % demand control knob so that the Wpower indicated correlates much closer with the actual reactor power enhances safety by avoiding the need for the operator to make a montal adjustment. I 1
'( __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ . _ - - . - - - - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
IV 35 Having a %-demand control knob covering from 10% to 110% of the > power indicated on the range switch is suitable for all operatio_nal needs. This range fits well with the chart recorder, as the paper covers a range up to 110% of the range switch setting. !
~
In addition, while the normal maximum operating power is 1 MW, the reactor is licensed to 1.1 MW so that the maximum setting of the % demand control knob on the maxinium power range will not cause the licensed power level to be exceeded.
; 2. 10 CFR 50.59 Chanoes to Reactor Procedures There were five changes to reactor procedures which were reviewed, approved, and performed under the provisions of 10 CFR 50.59 during the reporting period.
- a. REVISIONS TO THE REACTOR OPERATIONS COMMITTEE CHARTER
. (1) Description On an annual basis, a standing Reactor Operations Committee (ROC) subcommittee reviews the Committee's charter. The 1990 review i
indica *ed that several changes should be made in order to keep the charter current. Several other changes were made in order to clarify y activities specified in the charter. None of the changes involved major changes in ROC operating policies. . l- !: - The changes to the ROC charter included several very minor editorial '
- clarifications which were of no possible significance from a safety standpoint. Other changes which were of a minor nature, but perhaps -
not totally editorial, are listed below. 3 Section Chanae
- 11. 2 (1) The section o, ROC membership was changed to -
delete the statement that the chairman must hold at least a Reactor Operator license valid for the OSTR. The V
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- IV-3 6
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Section Chanae statement was replaced by the requirement that at least one of the ROC members must possess a Senior Reactor - Operator's license valid for the OSTR. The former state- - ment is not required by the OSTR license or TechnicaI , Specifications and is replaced by a statement which brings more technical competence to the Committee. (2) Statements f and g under membership were changed. to include the words "at least one" person whose field of expertise is ..., instead of just "a person". (3) -In the last paragraph of section 11.2, the abbreviation ROC was substituted for the word Committee'in several places. Ill.1 (1) Under- the Audit section, item a was modified by adding the words "and the fuelinventory and transfers" to. the list of items specified for auditing in item a.
-(2) Under the Audit section, a new item o was added to clarify that facility drawings are an item which will be audited as part of the quarterly ROC audit process.
Ill .1 - Under the Audit ~section, there exists an additional list of items to be audited 'on a quarterly basis which includes radiation surveys (item d). The radiation survey statement . was expanded by adding the parenthetical statement
" including routine surveys. such as daily, weekly, and monthly; special surveys; RAM receipt surveys; and environmental monitt,.ing surveys".
J
IV-37 Section Chanaq Under the Audit section, there exists an additional list of items to be audited on an annual basis which includes the
~
Radiation Center Health Physics Procedures (itern f). The statement listing the Radiation Center Health Physics Procedures was expanded by adding the following clarify-ing sentences: "The ROC reviews the Radiation Center Health Physics Procedures (RCHPPs) annually on a rotating basis (i.e., a certain fraction of the RCHPPs are reviewed each quarter). However, during the interim period, the Senior Health Physicist has the authority to review and revise RCHPPs as necessary without ROC approval. Ill.2.c (1) The first sentence of item c in the Review and Approv-al section was changed to remove the statement "within 24 hours" since all 9 vents which are required to be report-ed to the N..C will be reviewed and, as appropriate, approved by the ROC. The reporting time required by the NRC will have no bearing on whether or not such events are reviewed by the ROC, (2) The last senter'ce of item c in the Review arid Approval section was deleted because the requirement for ROC review and approval of written reports to be submitted to the NRC before the reactor may be brought back to an operational state was overly restrictive, is not required by the OSTR license or Technical Specifications, nor by ANSI Research Reactor Standard 15.1. This standard deals with the development of technical specifications for research reactors and is endorsed by and used by the NRC.
rm IV 38 Section Chanan (3) A final sentence was added to item o in the Review and Approval section which roads as follows: "This review and approval will occur before formal submission of reports to the NRC." lil.2.d&o itema d and e in the Review and Approval section had a final sentence added to each of them stating "This review and approval will occur before formal submission of reports to the involved regulatory agency or agencies, Ill.2.f item f in the Review and Approval section had tb9 state-ment "as the need arises" added at the end of the existing statement, (2) Safety Evaluation Based on the nature and scope of the changes to the ROC Charter,it is evident that most of the changes were editorial, In cases where the changes added or deleted statements, these additions-or deletions aroso from the need to ensure that the charter is consistent with and responsive to the requirements of the OSTR license and Technical Specifications, and clearly reflects the operating policies and proco-dures of the ROC, Therefore, all changes can be categorized as being-either editorial, clarifying or_ updates to the charter, Minor editorial changes, by definition, have no safety implications, while additions or - deletions resulting in updates and clarifications are clearly beneficial to safety since they minimize or eliminate the possibility for misunder-standing. Updates to the charter to ensure cempliance and/or consistency with the OSTR license and Technical Specifications also enhance safety by ensuring that the required memberships, audits and reports are strictly i, accordance with NRC requirements,
, IV-39 I b. REVISIONS TO OSTROP 6.0 (1) Description The OSTR staff decided to perform a complete review of OSTROP G and to revise it whero necessary to bring it up to date. In addition, the staff recognized that there were changes which could be made to improve the officiency of various processes. All of the changes, other than typographical or grammatical changes, are listed below. Section Chance 6.2.A.3 The parentheticai ref orences to which personnel were or were not licensed reactor operators were deleted, as they were not relevant here. 6.4 The recently approved changes to the Reactor Opera-tions Committee Charter were incorporated into this OSTROP. These changes were discussed in detailin a 10 CFR 50.59 safety evaluatio.' dated October 17, 1990. 6.5 A new paragraph was added to the beginning of this section stating that normal lines of succession have been established for certain specified positions. 6.5.B.7 Designation of the Reactor Adrninistrator as the Principal Security Officer in the absence of the Radiation Center Director is now included as one of the items in the lines of succession for key reactor positions. Therefore, this matter was delt.ted from the new OSTROP 6. Other Recctor Administrator responsibilities were renumbered.
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Secti20 Chence 6.5.D.1 This section was revised to allow the person filling the Reactor Operator position to hold an NRC reactor - operator or senior reactor operator license. 6.5.G.p Reference to the Student Health Center was deleted
, order to be consistent with the latest revision of R Emergency Plan.
6.5.H.8 +
,;, was made here te recognize that r cobalt-60 irradiators 6.6.A 4 A clarification was made stating that all reactivity changes will be made by, or in the presence and under the direction of, the licensed operator of record at the time the reactivity changes are made.
6.6.A.5 Personnel other than the reactor operator can com-plete the startup checklist. Therefore, this section was changed to reflect that fact. 6.6.B.2.c The range within which the Reactor Supervisor must remain while carrying a radio was reduced from 15 to - 10 miles. 6.6.B.4 For clarity, this section was split into two sections, and subsequent sections renumbered. In addition,
' the Reactor Administrator was added to the list of
- personnel who may suspend operations if necessary.
The Reactor Administrator was also added as a person who needed to give permission for restart.
l- IV 41 Section ~ Chance 6.6.C - A new section with this number was added and subsequent sections renumbcred and revised for conforming consistency. The new section addresses
=
the-fitness for duty of licensed operators and the goals of a drug-free environment. 6.6.D.4- A parenthetical note was added to clarify the intent of the requitement that the reactor operator of record not be the instructor of an ongoing class. 6.7.B.7 A new section was added to specify the physical -
. security requirements when staff observe or suspect unauthorized entryinto a security area. This section is consistent with the OSTR Physical Security Plan.
i
- 6.8 This section was completely revised except for the .
part relating to the reactor status board. The section was split into four new sections (6.8 - 6.11). One of l
- the major intents of these revisions was to remove' the current need to have several: pieces of paper circulating which refer to the samo _ procedural or-facility change. .-In the revised procedure, normally o one document will be used for the requisite review, appreval, and informational purposes.
I
- 1. . . . . .
; in section 6.8, the list of procedures which require a b '10 CFR_50.59 safety evaluation before they .are L changed was expanded to include OSTROPs 12 and 26.
l.
's IV 42 Section Change The now procedure requires all 50.59s to be circulat- 4 od to all of the ROC (rather than to just a quorum) for i their approval, and to reactor operators for informa-tion. - The only exception to this _is when an ROC member is unable to sign the 50.59 form due to absence or illness then he or she may be omitted from the circulation. Provisions are also given for an ROC member who feels ho/she cannot give approval without further discussion.
6.9 This section addresses the new Roactor Operations Committeo Approval Shoot (ROCAS). To a certain extent, this sheet replaces the old OlBs and FCDs. The shoot is used for anything except 50.59 ovalua . _ ,
- tions which requires ROC approval betwoon moot- '
irgs. As with 50.59s, all ROC members sign off on-the ROCAS to signify review and approval, and - reactor _ operators sign to signify review. - ROC signa-tures also indicate agrooment.with the conclusion that a 50.59 safety evaluation is not nooded for the item or action under-consideration. Provisions ar'o- i given if a member feels he/she cannot give approval-without further discussion. 6.10 This section adds a new Information Bulletin used for communicating informational items only. It has no approval function. Flowchart The flows.nart and examples of the standard forms and Forms have boon revised to reflect the changes described I above. l i 1 i
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1 IV-43 (2) Safety Evaluation This safety evaluation addresses only the substantive changes. In
- additionithe changes due to the revision of the ROC charter are not covered here because they have already been addressed in the 10 CFR 50.59 evaluetw Sted October 17,1990.
Section Chance 6.5 - Adding a formalized line of succession for all of the key positions with respect to reactor operations enhances reactor safety. It clarifies who has certain , responsibilities in the absence of key people. Lines of succession for emergency situations are already specified in the emergency plan and implementing , procedures.
- 6.5.D.1 The position of Reactor Operatcr can clearly be fulfilled by a licensed senior reactor operator as -
competently as a licensed reactor operator. There-
- fore, this change does not lead to cny reduction in reactor safety.
6.6.A.5 Stating that the Reactor Operator must complete the -
-startup checklist is unnecessarily restrictive. Any licensed reactor operator or senior reactor operator, or a reactor operator. trainee or nuclear engineering student in the presence of, and under the direction of, a licensed operator _-is allowed by the NRC's regulations to perform such a function.
6.6.B.2.c Reducing the range of travel for a Reactor Supervisor ensures that he/she can return more expeditiously to the Radiation Center if necessary. Therefore,if this
' change has any effect at all it is beneficial m.----,,- -,,--e- -e en- -,,~--w---.--,-,m, - -~ < - .m m.,-. ,.,,ee-<. .- r-n- , - , ,,, ,,, -- ,, .,m-- , , - , - - r,-
. . . _. ~ . ._ ._ _ .._._ ___. _._._._ .__.___.._._._ IV 44 Section Chanog 6.6.B.4 Adding the Reactor Administrator to those lists inc'reases the number of people who may suspend reactor operations and authorize subsequent restart, thereby giving further opportunity for safety review. 6.6.C This new section addresses objectivos and require-ments of the USNRC, the state of Oregon, and Oregon State University with respect to maintaining an environment free from the effects of drugs and alcohol in addition, the fitness for duty requirornents f or licensed reactor operators are clearly stated. Each of these changes can only load to greater reactor safety, by alerting staff and operators to the high standards expected of them. 6.6.D.4 The initial intent of this requirement was to ensure that the person operating the reactor was not dis-tracted by students in a class. Thus, it was meant for larger classos and not for situations where there were just one or two people with whom the operator was interacting. This change clarifies this original intent. 6.7. B.7 - - This section provides a more accessible reiteration of statements already included in the OSTR Physical-Security Plan and therefore, does not affect reactor - safety.- 6.8-6.10 These changes will be addressed together as they are interrelated; Reducing the number of pieces of paper relating to a particular change minimizes the chances of confusion, and reduces duplication. Even though
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l IV-4 5 - I Section .Charma there is now only one document related to each change, there are, in fact, more people reviewing each document. -Under the now process, normally every member of the ROC and every reactor operator reviews, and as appropriate, approves the changes, in the past, most of the responsibility for assessing and approving a 50.59 safety evaluation was carried out by a quorum of the ROC, The new process gives the ROC greater initialiswolvement in changes associ-ated with the reactor and, again, contributos to increased safety by reducing the chances that some important issue will be overlooked,
- c. - UPDATE OF THE RADIATION CENTER AND OSTR EMERGENCY RESPONSE PLAN APPENDIX B (1) Description Appendix B of the Radiation Conter and OSTR Emergoney Responso Plan contains representative listinps of inventorios of- omorgency equipment available at various onsite and offsite locations. A new Appendix B was_ issued in order to keep thoso equipment inventories up-to-date.
(2) Safety Evaluation ! Updating Appendix B has no effect on reactor safety and does not reduce the effectiveness of the OSTR Emergency Responso Plan. In H some small measure it increases the reliability of the plan by keeping it current, and thus enhances safety. < A review by the reactor operations and health physics groups deter-mined that the indicated distribution of emorgency equipment was L more than adequate for any emergency addressed in the Emergency
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_ - . _._ - ~- - _ . - - . . _ - - - . . - . - . _ -- ._ IV 46 Responso Plan. -In the unlikely event thst extra equipment is needed, more is available in the Radiation Center. This extra equipment is used for teaching purposes in the Nuclear Engineering Department's radiation protection classes,
- d. CHANGE OF ACCEPTABLE pH RANGE FOR REACTOR PRIMARY WATER AND BULK SHIELD TANK WATER
-(1) Description The acceptable pH range for the reNtor primary water was shown in OSTROPs 7 and 13 as 5.0 7.5. The acceptable range for the bulk shield tank water was inconsistent, being 6.0 6.5 in OSTROP 10 and 5.0-8,5 in OSTROP 13.-
Changes in pH instrumentation and in the method of measuring pH resulted in some of the pH readings for the reactor water being close to, and slightly in excess of the upper limit of 7.5. Investigations over a few months led to the conclusion that there was really no change in
- the reactor wator pH but that the method of measurement was what caused the change in readings. In the past, the procedu o required waiting for a stable reading before recording the pH. However, under the new procedure the reading is taken very quickly. Taking the reading immediately provides a more representativo value by avoiding the change in pH due to CO2 absorption from the air.
Discussions with General Atomics and an OSU chemistry professor led us to the conclusion that the range of acceptable pH values could-easily be expanded with no increase in the potential for corrosion. The r'
.or staff, therefore, revised the procedure to allow the acceptable-pH range for both the reactor water and the bulk shield tank water to be 5.0-8.5.
I n
IV 47
-(2) Safety Evaluation Investigations of the pH issue have revealed the following information.
The Nuclear Safety Information Center in Oak Ridge made the statement in 1969 that it was impossible to maintain the pH of
. swimming pool type reactors between 6.5 7.0 (as many f acilities were trying to do) due to the carbon dioxide from the air dissolving into the water. They also stated that pH measurements and pH control were difficult with water conductivity be!ow 5 pmho/cm (ours is about 0.5 pmho/cm). General Atomics agreed with this and further pointed out that pH readings obtained at low conductivity are very much a function of such things as the technique used and the electrode history of the pH instrumentation.
-It should also be noted that there was not any real change in the pH of the water. . The recorded results changed simply because the readings were taken immediately af ter taking the sample rather than
' waiting for tl.e value to stabilize, pH measurements similar to those obtained on the old pH instrument can be read on the now pH instrument if the water is allowed to stand as before.
The key to rninimizing reactor component corrosion is maintaining a o low conductivity, and not trying to control pH. It did not seem to be-- l prudent to add chemicals to the reactor water or the bulk shield tank water in an atternpt to control or adjust pH. In particular, it was felt that the addition of potassium chromate to the bulk shield tank (as was written in OSTROP 10.4) should not be allowed due to the hazardous
- . nature of that material.
A member of the ROC who is a professor of chemistry was involved in these discussions on pH and recommended that the ' acceptable range for both the reactor tank water and the bulk shield tank water be
~
5.0 8.5 - He concluded that there will be no change in corrosion rates for wetted components within this range. 1
IV 48 I
- e. EMERGENCY RESPONSE PLAN REVISIONS (1) Description Severai changes necessitated minor revisions t6 the OSU Radiation Center end TRIGA Reactor Emergency Response Plan. These changes are grouped below under the appropriate heading, and are referenced to the page on which the change or changes occur.
Increase in the Licensed Power Level of the OSTR
. The maximum licensed steady state power level of the OSTR was raised frorn 1000 kW to 1100 kW. This necessitated one change.
1-1 Change 1000 kW to 1100 kW. Change in Resoonsibilities of the Emeroency Director and Emerggacy Coordinator it'was decided that the Public Information Officer (PIO) should report to the Emergency Director rather than the Emergency Coordinator. This necessitated several changes in the emergency plan and many changas in the emergency implementing procedures. However, only . the changes in the plan need to be addressed here. 37 "vi) Notify the Public Information Officer and keep him/her informed regarding the emergency situation" was added to the list of Emergency Director duties. 37- "and the Public Information Of ficer" was deleted from item ii) of the Emergency Coordinator duties. 3 10 in the list of PIO duties, "ii) Coordinate with the Emergen-
- cy Coordinator (and Recovery Operations Coordinator)...".
was changed to "ii) Coordinate with the Emerge:y Director...". 3 11 "and Public information Officer" was deleted from item iv) in the list of Recovery Operations Coordinator duties.
IV-49 3 14 The chart was revised to show the line to the PlO going from the Emergency Director rather than the Emergency . Coordinator. The Radiation Center Director box was removed. Removal of the Gamewell Fire Annunciator System
- The Gamowell fire annunciator system is no longer used by the City of '
Corvallis Fire Department. This means that fire alarms from the Radiation Center now will no longer sound in the City 911 Dispaieh Office. _However, they will sound inside the OSU Police and Security Dispatch office. The OSU dispatcher will then notify the Fire Depart-ment. - 7-6 The last sentence in 7.2.1.d was changed to read "For example, OSU Police and Security will receive physical security and fire alarms directly." 85 The first two sentences of 8.2.5 Fire Dectectors, paragraph b), were changed to read "If one of the fire sensors detects a fire, an alarm will be automatically activated, not only in the building, but also at OSU Police and Security Dispatch.
.The OSU dispatcher will then call the Corvallis City Dis-patch who will then alert the nearest available fire engine crew."
(2) - - Safety E' valuation
- The safety considerations related to the increase in licensed reactor power level. have been previously evaluated and the change was approved by the USNRC. Therefore, this change merely brought the plan up-to-date, and is not discussed further in this document.
Discussions between the Radiation Center Director and the Reactor Administrator led to 'the decision to have the PlO report to the Emergency Director rather than the Emergency Coordinator. it was
. .a - - . - .. . .-- . - . . -
IV 50 recognized that the Emergency Coordinator would be very busy coordinating actions betwoon many groups, while the Emergency Director was relatively uninvolved in the erriorgency. It is a logical assignment for the Emergency Director because the press releases have to be approved by this individual, and also because the Emergency Director coordinatos with the University administration. The change of iosponsibility should troo up the Emergency Coordinator without unduly burdening the Emergency Director, and thereby will result in an increase in safety. The fact that the firo alarm signal does not direct.ly annunciato at the City's 911 Dispatch Contor does not reduco reactor safety. OSU Polico and Security willimmediately call the Fire Department who will dispatch the nearest fire crow. This will normally be a team from the local sub station which is located a few hundred yards from the Radiation Contor. The total response time will not be appreciably changed. It should be noted that all of the other alarms which are annunciated outsido of the Radiation Contor also go directly to the OSU Police and Security Dispatch, and therefore, this chango does not present a new situation with respect to emergency response. (3) Conforming Procedural Changes Conforming procedural changes to the Emergency Rosponso imple-menting Procedures (ERIPs) were also mado.
- 3. 10 CFR 50.59 Channes to Ren.glor Experiments There woro no changes to reactor experiments during this reporting period.
IV-51 E. Sitrveillance and MaintqDanRC >
- .1, Non Routingl%ntonaRCD i
July 18,1990 installed a new reactor consolo log and knoar power re':ordor.
- July 25,1990 Replaced the nuclerst dntcetor patch-panol in the back of the consolo with a detector current selector switch.
July 30,1990 Replaced the #2 reactor bulk tator temperature meter. August 6,1990 Removed a fuel element from the reactor core for increased shut-down margin. August 20,1990 . Replaced the east and west bearings on tho south sido cooling tower fan. Sept. 4,1990 Cleaned all the battery terminals on the inverter battery bank. . Sept.18,1990 Relocated the reactor bay stack smoke detector .further upstream in the exhaust duct. Oct.12,1990 to Oct. 26,1990 Cleaned the rotating rack facility by soaking with Simple Green and flushing repeatedly with water. Nov.27,1990 Replaced all the batteries in the inverter battery bank. Doc.7,1990 Replaced the combination log power and fuel olomont temperature meter on the consolo. Dec.7,1990 Moved the high voltago test buttons for both the fission chambor and the safety ion chamber to the face of the consolo left-hand drawer. Dec.10,1990 . Replaced the dif ferentiating capacitor on the reactor period amplifier. Dec.11,1990 Replaced the N.E. reactor tank underwater light. Dec.12,1990 installed a period offset amplifier in the reactor control servo system. Doc.-18,1990 Replaced two voltage divider resistors in the linear recorder circuit. Janc23,1991 Replaced the chopper in the reactor control servo system with an idor;tical component.
IV-52 Jan.28,1991 Began installatio i of the new resin flush / fill and water make-up system. Feb.12,1991 Replaced the diaphragm in the pneumatic motor that operates the north damper in the reactor building in!et ventilation duct. Feb.15,1991 Replaced valve DV-10. Feb.25,1991 Installed a three-inch high colfor dam in the heat exchenger room around the outside door. Feb.26,1991 Removed a connector piece between the two sets of inlet ventilation dampers. Feb. 28,1991 Replaced the K-19 relay in the linear power circuit located in the consolo left hand drawer. May 1,1991 Cleaned all the fission charnber pre amplifier connectors. May 28,1991_ .!nstalled a new dual float and switch mechanism f or reactor tank high and low water level alaims. June 17,1991 Installed ded:cated power terminal blocks in the back of the consolo and removed some unnecessary wiring, June 17,1991 to June 19,1991 Replaced all PVC piping in the domineralizer system with new Schedule 80 pipes. Jane 20,1991 Installed the automatic lock-in and manual reset for the high voltage scram annunciators on both the % power ion chamber and the fission chamber. June 21,1991 Plumbed in the distilled water line f or the new demiaeralizer make-up and flush system. June 26,1990 . installed a new % demand potentiometer on the console.
- 2. Routine Surveillance and Maintenance The OSTR has an extensive routine surveillance and maintenance (S&M) program.
Examples of typical S&M checklists are presented in Figures IV.E.1 through IV.E.4. items marked with an asterisk (*) are required by the OSTR Technical Specifica-tions.
. . _... +,. - - . . . . - . - - - . - - , ~ . -.,.--. . -- . . . . . ~---.... ~ . - . ..-. . . - - . - . . . . .
IV 53
?
F. Reppf.tp.Mp OccurrenG.M , There was one reportable occurrence during the reportin0 period. The occurrence was j , addressed in detail in a ~roport rneiled to the NRC dated July 16,1990. The occurrenco , involved a failure to ensure that the % power safety channel was reconnected befora the reactor was started up, i I f
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*'1 FUNCTIONAL CHECK OF REACTOR WATER ' M AXIMUM US, __ rcNs i LEVEL ALARMS MOVEM!tJT - DN. . .. snctre 23fNCHES AfM _._
2 MEASUREMENT OF THE REACTOR FfuMARY' MIN: S WATER pH MAX; 8$ i 3 MEASUREMENT OF Tite BULK SH' ELD TANK MtN % WATER pH MAX: 85 4 EMERGENCY POWER SYSTEM LO uiD- +1" ON BATTERY CHECKS
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- Ucense Raqtorement.
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L l PART V PROTECTION A. InRDIlurdim! This soction cf the report deals with the radiation protection program at the OSU l Radiation Center. The purpose of this program is to ensute the safo uso of radiatlon and radioactive material in the Center's teaching, research, and service activities, and in a similar manner to ensure the fulfillment of all regulatory requirements of the stato of ! Oregon, the U.S. Nuclear Regulatory Commission, and other regulatory agencies. The ! comprehensivo nature of the program is shownin Tablo V.A.1, whichlists the program's major radiation protection requirements and the performanco frequency for each item. t , The radiation protection program is implemented by a stalf consisting of a Senior Health Physicist, a Herith Physicist, a Radiation Protection Technologist, and several part time ; Health Physics Monitors (sco Part li.F). Assistanco is also provided by the reactor operations group, the neutron activation analysis group, the Scientific Instrument Technician, and the Radiation Center Director,
. The data contained in the following sections have been prepared to comply with the i current requirements of Nuclear Regulatory Commission (NRC) Facility Licenso No.
R 106 (Docket No. 50-243) and the Technical Specifications contained in that licenso. : The material has also been prepared in complianco with Oregon Department of Energy
' Rule No. 345 30-010, which requires an annual report of environmental of facts due to research reactor operations ~ A summary of required data fo the OSTR is provided in Part 1.E for quick reference.
Within the scope of Oregon Stato University's radiation protectiote program, it is-standard operating policy to maintain all releases of radioactivity to the unrestricted j onvironment and cll exposures to radiation and radioactive materials at lovels which are consistently *as low as reasonably achievablo" (ALARA). , a -- I -- .--m--,--.-=~-.n-n..w.~,m..mn,. s m aw w-vvm-w ev,e-w m,--wee m
__ - . _ _ _ _ _ _ _- . - - m_ _ _ m ._ l V2 l Table V. A.1 Radiation Protection Program Requirements and f requencies k FREQUENCY RADiMION PROTECT;ON REQUIREMUJT J DailyAveckly/ Monthly Perform routine area radimion/ contamination monitoring. 1 Weekly Perform gamma spectroscopy of the (OSTR) continuous air monitor particulatr' ;ister, Monthly Perform routine response checks of radiation rnotutoring instruments, Monitor radiation levels (pR!hr) at the environmental monitonng staticos. Collect and analyse TRIGA pnmary, secondary, and make up water. Exchange personnel dosimeter
- and inside area monitoring dosimt;ters, and renew exposure reports.
Inspect laboratones, Check emergency safety equipment. Perform neutron generator and totium assembly contamination survey. Calculate previous month's gaseous effluent discharge. As Required Process and record Sohd waste and liquid effluent discharges. Prepare and record radioactive material shipments. Survey and record incoming radioactive materials receipts. Perform and record special radiation surveys. Perform thyroid and urinalysis bioassays, Conduct orientations and training. Issue radiation work pernuts and provide health physics coverage for maintenance operations. Quarterly Prepare, exchange and process environmental TLD packs. Collect and process environmental soil, water and vegetation samples. Conduct orientations for classes using radioactive materials. Collect and analyre sample from reactor stack etfluent line, Exchange personnel dos; meters and inside area monitoring dosimeters, and teview exposure reports. Semi. Annual Leak test and inventory sealed sources, Conduct floor survey of corridors and reactor bay. Cahbrate ponable radiation monitoring instruments and personnel pocket ion chamber s. Inventory and inspect Radiation Center equipment located in the Corvalks fire Department Har/ Mat van and at Good Samaritan Hospit?' Annual Cahbrate reactor stack effluent monitor, continuous air monitors, remote area radiation monitors, water monitor, and air samplers. Measure f ace air velocity in laboratory hoods and exchange dust-stop filters and l HEPA filters as necessary, , Inventory and inspect Radiation Center emergency equipment. l Conduct f acihty radiation survey of the "Co irradiators and X ray machine. l Conduct personnel dosimeter training, l 1 1
V3 B. Envirortrnental Reignes The annual reporting requirements in the OSTR Technical Specifications stato that the licensee (OSU) shall includo 'a summary of the nature and amount of radioactivo q offluents roloased or dischar00d to the environs beyond tho offective control of the licensco, as m?asured ot, or prior to, the point of such release or dischargo." The liquid and gaseous offluents released, and the solid waste generated and transferrod are discussed briefly oclow. Data ro0ording those offluents are also summarized in detail in the designated tables.
- 1. Liouid Effluents Releaic.d Whenever possible, liquid of fluent is analyzod for radioactivity content at the time it is roloased to the collection point (a holdup tank). However, liquids are always aitalyzed for radioactivity bef oro the holdup tank is discharged into the unrestricted area (the sanitary sewer system). For this reporting period, the Radiation Contor and reactor made three liquid of fluent releases to the sanitary sewer. All Radiation Conter and ros'c tor facility liquid of fluerit data portaining to these three reioases are '
contained in Tablo V.B.1.
- 2. birhorne Ef fluents Released Airborno'offluents are discussed in terms of the gaseous component and the .
particulato component,
- a. Gaseous Effluents Gasoous of fluents from the reactor f acility aro monitored by the reactor stack ofiluent monitor. Monitoring is continuous (i.e., prior to, during, and af ter reactor operations). It is normal for the reactor f acility stack of fluent monitor to bodi n operation as one of the first systems in the morning and to cease operation as one of the last systems at the end of the day. All gaseous of fluent data for this reporting period are summarized in Tablo V.B.2.
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L Table V.B.1 < Monthly Summary of Lioted Effbent Releases to the Sarutary Sewer" (OSTR Contributinn Shown in () and Bold Print) I ' Specific Activity Average Percent of Total Volume For Each Deectable Totai Quantity Concentration
~ Date of . Total Quantity Radionuclide in tte of Each Detectable of Released l taNe Discharge - of Radcactivity Waste Where the Radionuchde . Radcactnre
' a h W es # (Month & Released Release Re! eased in the Material at Year)
' (Cunes)- Concentration Was Waste the Point of '
> 1 x 10 pCilcc ' Material Dduent" (Curies) Release (vCdeci (pCi/cc) IG80 3
October 90 H - 2.12 x 10+ I (fuo OSTR 2.45 x 10' "Co - 8.33 x 10 3.89 x 10 4 0.2%* 1667 l Contribution) Se 1.32 x 10-' 2.35 x 10 7 0.009 % * , 'H 5.47 x 10* 3.73 x 10~* December 90 . "Co 2.90 x 10 ' 1.98 x 10' i (No OSTR 4.65 x 10* Zn - 4.88 x 10 6.81 x 10+ 3.6%* 1803
~
Contribution) Se 6.24 x 10r' 4.26 x 10 4 0.1%*
"*Ce 2.58 x 10~' 1.76x10*
February 91 ( H) (9.75 x 10') (7.90 x 10') (51.9%*) i (OSTR ONLY) (8.18 X 10*) ('*Na) (3.70 x 10*) (3 00 x 10*) (1.01 x 109 (2 W ("Tcl (1.6%*) (2.70 x 10*) (2.19 x 10*) Annual Total 'H - Se Radiat Center o. Applicable ?- % Pfus OSTR Zn
;; (1) Tie OSU operational pobey is to subtract only detector background from our water anatytds data and not bar.kground radcactnnty e the Corvanrs city water. There were no Igred
- effluent releases dunng months not listed. i I: i (2) The total volume of licuid effluer.t plus dduent does not take into consideraton the addrt< mat mixing with the over 7,500.000 gattorn per year of houids and sewage normany '
disctwged by the Rad:ation Center complex into the same sarwtary sewer system. (3) Based on values hsted in 10 CFR 20, Appendix B. Table 2, Co umn 2. (4) Based on values listed in 10 CFR 20, Appendix B Table 1, Column 2, which are applicable to sewer disposal.
. ~ . - _ _ _ _ , _ _ _ _ _ _ _ . . - _ . _ . _ . _ . _ . _ _ _ _ _ _ _ . _ _
. i v5 i Table V.D.2 Monthly Summary of Gaseous Effluent Reicar.es"' , Estimated Average Percent of the ; Total Atmospheric - Applicable ! Total Date of Estimated Diluted MPC for Diluted Estimated Discharge _ Ou'.ntity of Concentration of Conecottation ' Radioactivity (Month & Argon 41 Argon-41 at of Argon 41 at year) Released - Releasedi28 Po nt of Release Point of Release -) (Cunes)
~ (Curles) (Reactor Stack) (Deactor Stack) 1 (pCi/ml) (%)
July 90 0.30 0.30 2.3 x 10 8 0.6% August 90 0.38 0.38 2.9 x 10* 0.7% September 90 0.43 0.43 3.3 x 10* 0.8 % October 90 0.41 0.41 3.1 x 10.s 0.8 % ; November 90 0.44 0.44 3.4 x ~10 8 0.9 % I December 90 0.53 0.53 4.1 x 10* 1.0% January 91 0.40 0.40- 3.0 x 10 8 0.8% February 91 0.34 0.34 3.0 x 10'8 0.7 % March 91 0.81 0.81' 6.2 x 10 8 1.0% April 91 0.42 0.42 3.4 x 10* 0.8 % May 91 0.46 0.46 3.6 x 10* - 0.9 % { June 91 0.61 0.61 5.0 x 10 e 1.2 % . ANNUAL VALUE 5.5 5.5 3.6 x 10 8 '0.9 % l l (1) Airborne effluents from the OSTR contained no detectable particulate radioactivity resulting from reactor I operations, and there were no releases of an,y radioisotopes in airborne effluents in concentrations _ greater than 20% of the applicable MPC value. (20% is a value taken from the OSTR Technical Specificationa.) (2) Routine gamma spectroscopy analysis of the gaseous radioactivity in the OSTR stack dischsige
- Indicated the only detectable radionuclide was argon-41, 4
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- b. Particulato Elfluents Particulato offluents ,eom the reactor facility are also monitored by the reactor facility stack of fluent monitor, f Evaluation of the detectable particulate radioactivity in tho stack offluent ;
confirmed its origin as naturally occurring radon daughter products, within a rango of approximately 1 x 10* Ci/cc to 3 x 10'"pCi/cc. This particulato radioactivity is prodeminantly 8 "Pb and2 "Bl, which is not associated with reactor operations. There was no relonso of particulato offluonts '.vith a half lifo greator than 8 days and thotofore the reporting of tho averago concentration of radioactivo -
- particulates with half lives greator than eight days is not applicable.
- 3. Solid Wasto Roloased ,
Data for the radioactive material in the solid wasto generated and transferred during this reporting period are summarized in Tablo V.B.3 for both the reactor f acility and the Ridiation Contor. Solid radioactive wtsto is routinely transferred [ to the.OSU Radiation Safety Offico.. Until this wasto is disposed of by the Radiation Safety Offico,it is hold along with other campus radioactive wasto on the University's stato of Oregon radioactive materials licenso. Solid radioactivo waste is disposed of by the University Radiation Safety Of fico by '
- transfer to the University's radioactive wasto disposal vendor, Allied Ecology.
Services, Inc., for burial at their installation located near Richland, Washington. 7
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V-7 i Table V.0.3 Annual Summary of Solid Waste Generated and Transferred
. Volume of Total Quantity Dates of Origin of OctoctaWe Solid Waste of Radioactivity - Shipment to
- Solid Waste Packaged RadbnwWes .
in Solid Waste Allied Ecology I in the Waste Services, Inc.t u _ (Cubic Feet) (Curies) : 2dSodium d8 Scandium 6' Chromium 68 Cobalt 6' Iron TRIGA 80 ' Cobalt ec. O,1990 Reactor' 24 esZinc 7.3 x 10 4 Facility 76 Selenium " " * ' ' 00 124 Antimony 13' lodine -! 137 Cesium l id Lanthanum Europium
'* Carbon d
Radiation Scandium Cente 14 I' " Dec. 6,1990 5.5 x 10 s Laboratories # E" E E 75 Selenium :
- trslodine -
TOTAL 38 See Above 7.9 x 10 4 - (1') All Radiation Center and OSTR solid radioactive waste is routinely transferred to the OSU Radiation 4 Safety Office, where it is held on the University's State of Oregon radioactive materlats license, along with other campus waste,~ prior to shipment to Allied Ecology Services, Inc. by the Radiation Safety *
- Of fice.
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. _ . . m.. _ ._ _ _ _. _ _ - -_ _ ._ _ _._ __ - _ _ _ V8 C. P.gigonnelDaign The OSTR annual reporting requirements specify that the licensoo shall present a summary of the radiation exposuro received by facility personnel and visitors. For the purposos of this report, the summary includes all Radiation Contor personnel who may havt, rocoived oxposure to radiation. Thoso personnel have boon categorized into six Oroups: - facility operating personnel, key facility research personnel, physical plant i maintenanco personnel, students in laboratory classes, polico and security personnel, and visitors. ! I Facility operating persorsnelinclude the to ctor operations and health physics statt. The
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dosimeters used to monitor those individunts include monthly X ray, bota, and gamma IX#(G)) film badges, quarterly track otch/ albedo noutron dosimeters, either monthly or - ; quarterly TLD (finger) extremity dosimeters, and pocket ion chambers, i Key facility research personnel consist of Radiation Contor staff, faculty, and graduate students who perform research using the reactor, reactor activated materials, or using other research facilities prosent at the Contor. The individual dosimetry requitoments for thoso personnel will vary with the type of research being conducted, but will generally lacludo a monthly or quarterly XB(G) film badge and TLD (finger) oxtremity dosimotors. l
.lf the possibility of.noutron.oxposure exists, researchers are also monitored with a - -
track eten/ albedo noutron dosimeter, t Phyalcal Plant maintenanco personnel are normally issued a gamma sensii've pocket ion chamber as their basic monitoring devico. A few Physical Plant personnel who mutinely perform maintenance on mechanical or refrigeration equipment are issued a quarterly XB(G) film badge and other dosimeters as appropriate for the work being performed. Students attending laboratory classes are issued quarterly XB(G) film b6dges, TLD-(finger) extremity dosimotors, and track etch /albodo or other neutron dosimeters, as - appropriato. Students or small groups of students who attend a ono timo laboratory ; demonstration and' do not handle radioactive matenals are usually issued a gamma-sensitive pocket ion chamber. I i I
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V-9 OSU police and security personnel are issued a quarterly XB(G) film badge to be used during their patrols of the Radiation Center and reactor facility. Visitors, depending on the locations visited, may be issued a gamma sensitivo pocket ion chamber. OSU Radiation Center policy does not normally allow people in the visitor l category to became actively involved in the use or handling of radioactivo materials. An annual summary of the radiation doses received by each of the above six groups is shown in Table V.C.1. There were no personnel rtMiction exposures in excess of the limits in 10 CFR 20 or state of Oregon regulations during the reporting period. 1 1
s V 10 Table V.C.1 Anr.aal Summary of Personnel Radiation Doses Received Average Annual Giestest Individual Total Person mrem Dose"3 Dose"3 For the Group"3 Personnel Group _ Whole .
. Whole _
Whole Body Extremities Body Extremities Body Extremities (mrem)- (mrem) (mrsm) .(mrem) (mrem). (mrom) Facility Operating Personnel 9 40 105 540 100 780 K9y Facility. Research Personnel 1 -5 15 60 -- 15 00 Physical Plant Maintenance <1 N/A- 10 N/A 150 N/A Personnel Laboratory Class Students 0 N/A 0 N/A 0 N/A - Campus Police and Security Personnel 0 N/A 0 N/A 0 N/A Visitors <1 N/A 10 N/A- 117 N/A (1) *0* indicates that each of the beta gamma dosimoters during the reporting period was less than the vendor's gamma dose reporting threshold of 10 mrem or that each of the neutron dosimeters was less than the vendor's threshold of 30 mrem, as applicable "N/A* Indicates that there was no extremity monitoring conducted or required for the group.
1 V 11 l D. EacEty Survity_D.ola The OSTR Tot.hnical Specifications requiro an annual summary of the radiation lovels and l levels of centarnination observed during routino surveys performed at the f acility. However, the Conter's comprehensivo area radiation monitoring pro 0 ram encompasses j the Radiation Conter as well as the OSTR, and therefore monitoring results for both facilities are reported.
- 1. Area Radiation DatJmRWD Area monitoring dosimotors capablo of integrating the radiation doso are located at strategic positions throughout the reactor f acility and Radiation Contor. All of those dosimeters contain at least a standard personnel typo beta Damma filtn pack.
In addition, for key locations in the reactor f acility and f or certain Radiation Conter lateratories a CR 39 plastic track-otch noutron detector has also boon included in the monitoring package. Figuro V.D.1 shows the locations of tho dosimeters in-the reactor building and Radiation Conter.
-i
.The total doso equivalent recorded on the various reactor facility dosimeters is listed in Tablo V.D.1 and the total doso equivalent recorded on the Radiation Contor aree dosimeters is listed in Tablo V.D.2. Generally, the charactors following the MRC (Monitor Radiation Center) desi0 nator show the room number or location.
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V 12 Fi0 ure V.D,1 TRIGA Facility and Radiation Center Area Dosianeter Locations wrivu MRCitM Reactorfacility3rdfich Rear",or Facility 2nd Floor V V MRC110P j MRCINL {> MRCINW 9 l [: I,, ~ D104 Reactor
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J Table V.D.1 Total Doso Equivalent Recorded on Area Dosimotors Located Within the TRIGA Reactor Facility ; Total Recorded (RIGA Reactor Doso Equivalent ("* Monitor l Facility Location
' (500 Figuro V.D.1) xB(G) Neutton (mrom) (mrom)
MRCTNE D104: North Badge East Wall 15 0 MRCTSE D 104-: South Badge East Wall 15 0 MRCTSW D104: South Badge West Wall 195 0 i MRCTNW D104: North Badge West Wall 45 0 i MACTWN - 0104: West Badge North Wall 0 0 MRCTEN D104: East Badge North Wall 40 0 MRCTES D104: East Badge South Wall 420 0 MRCTWS D104: West Badge South Wall 410 0 MRCTTOP D104: Reactor Top Badgo 400 0 MRCTHXS D104A: - South Badge HX Room 405 0- t MRCTHXW D104 A; West Badge HX Room 30 0 MRCD 302 D302: Reactor Control Room 235 0 MRCD 302A D302A: Reactor Supervisor's Of fice 855 N/A (1) The total recorded doso equivalent values do not include natural background contribution and, except as noted, reflect tho summation of the results of 12 monthly bota gamma dosimotors or four quarterly fast neutron dosimoters for each location. A total doso equivalent of "0"
-indicates that each of the dosimeters during the reporting period was loss than the vendor's gamma doso reporting threshold of 10 mrer.1 or that each of the fast neutron dosimotors was loss than the vendor's threshold of 50 to 100 mrom, as applicablo. "N/A" indicates that there was no neutron monitor at that location. e - (2) These doso equivalon values do not represent radiation exposure through an exterior wall ~
directly into an unrestricted area. (3) The total recorded dose equivalent reflects the summation of four quarterly bota-gamma dosimoters. . l
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F V 14 Table V.D.2 Total Doso Equivalent Recorded on Area Dosimotors Located Within the Radiation Contor ! Total Recorded l Radiation Contor Doso Equivalent"' Monitor Facility Locatiore xp(G) Noutron I.D. (S00 Figuro V.D.1) (mrom) (mrom) : MRCA100 A100: Receptionist's Of fico 0* N/A-MRCBRF A102H: Frt Personnel Dosimetry Stor. Rock 0* .N/A MRCA120 A120: Stock Room 0* N/A~ MRCA120A A120A: NAA Temporary Stora00 15 ' 42 N/A MRCA126 A126: Campus RSO's isotopo Receiving Lab 330* N/A MRCCO 60 A128: "Co Irradiator Room 1410* N/A - MRCA130 A130: Shioided Exposurn Room Om N/A MRC300XRAY A132: X Ray Consolo Room 15* N/A MRCA134-2 A134: NAA Research Of fico 155* N/A MRCA138 A138: Health Physics Laboratory O* N/A MRCA146 A146: G3mma Analyzer Room (Storage Cave) 0* N/A MRCB100 B100: Gamma Analyzer Room (Stora0n Cave) 85m N/A MRCB114 B114: a Lab (22 era Stora00 Facility) 2260 0 MRCB1161 B116: Storage Rm (NAA Pormanont Storage) 25* N/A MRCB116 2 B116: Storago Rm (NAA Permanent Stora00) 2500* N/A MRCB116-3 B116: Storage Rm (NAA Permanont Storago) 25* N/A MRCB1191 B119: Source Storago Room OW N/A MRCB119 2 B119: = Source Stora00 Room 845* N/A MRCB119A B119A: Scaled Source Storage Room 3425 2250 MRCB120 B120: Instrument Calibration Facility 70* N/A MRCB122 2 0122: Radioisotope Storage Hood 1240* N/A MRCB122 3 B122: Radioisotopo Research Laboratory 0* N/A MRCB1241 B124: Radioisotopo Research Lab (Hood) 0* N/A , MRCB124-2 B124: Radioisotope Roscarch Laboratory 0* N/A MRCB124 6 B124: Radioisotopo Rosearch Laboratory 0* N/A MRCB128. B128: Instrument Repair Shop 0* N/A 60* MRCB132 B132: Radioisotope Research Laboratory N/A MRCC100 C100: Radiation Conter Director'* Offico 15* N/A MRCC106-H C106H: East Loading Dock 0* N/A MRCC118 C118: Radiochemistry Laboratory 0* N/A MRCC120 C120: Student Counting Laboratory 0* N/A MRCC123N C123: Gamma Analyror Room (Stora00 Cavo) 1750* N/A l MRCC123S C123: Gamma Analyzer Room 0* N/A l L See footnotes next page. l-
. _ . , _ . _.. _ _ _ _ _ _ _. _ __ _ . _ _ _ _ _ _ .__;___.._..,_._.__._..L
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V 15 Tablo V.D.2 (continued) Total Dose Equivalent Rc;r;rded on Area Dorimotors Located Within the Radiation Center l
~ l Total Recorded !
Radiation Conter Doso Equivalent"' t
. Monitor Fac:lity Location x#(G) Neutron I . D. (See Figure V.D.1) (mrom) (mrom)
+
MRCC124 C124: Student Office / Lounge Om N/A MRC126 C126: Student Counting Laboratory 25* - N/A MRCC1301 C130: Radioisotopo Laboratory (Hood) 0 0 MRCC130-2 C130: Radioisotope Laboratory 85 0 MRCC130-3 C130: lladioisotopo Laboratory 0 0 i MRCC134 C134: Gamina Antsyrer Room (Storage Cavo) 0 N/A ; MRCD101 D102: Pneumatic Transfer Terminal Lab 50 0 MRCD102-H D102H: 1st Floor Corridor at D102 0 0 MRCD106-H D106H: 1st Floor "arridor at D106 35* N/A MRCD200 0200: Senior Hostth Physicist's Offico 85* N/A MRCD202 D202: Reactor Administrator's Offico 115* N/A-MRCBRR D200H: Roar Personnel Dosimetry Storago Hack 0* N/A l MRCD204 H D204H: 2nd Floor Corridor at D204 0 0 MRCD300 D300: 3rd Floor Conference Room 20 0 (1) The total mcorded dose equivalent vatuos 'do not includo natural background contribution and, except es notad, reflect the summation of the results of 12 monthly beta-gamma dosimotors : or four quarterly fast neutron dosimoters for each location. A total dose equivalent of "O" - + indicates that each of the dosimeters during the reporting period was loss than the vendor's gamma dose reporting threshold of 10 mrom or that each of the fast neutron dosimoters was less than the vendor's threshold of 50 to 100 mrem, as applicable, "N/A" indicates that thoro was no neutron monitor at that location. (2) __ The total recorded dose equivalent reflects the summation of four quarterly beta gamma dosimeters. (3) The total recorded dose equivalent reflects the summation of three quarterly hota-Damma ~ . dosimeters that commenced on October 1,1990.
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- r V 10
- 2. -Eputino Radiatlan and Contarnination Survevji The Contor's program for routino radiation and contamination surveys consists of daily, wookly and monthly measuromonts throughout the TRIGA reactor facility and Radiation Contor. The frequency of those survoys is based on the nature of the radiation work being carried out at a particular location or on other factors which indicate that survoillance over a specific area at a defined frequency is desirable.
The primary purpose of the routino radiation and contamination survey progrr.m is to assure to0ularly scheduled surveillance over solocted work areas in the reactor facility and in the Radiation Contor,in order to provide current and characteristic data on the status of radiological conditions. A second objective of the program is to nssuto frequent on tho spot personal observations (along with rocorded data), which will provido advance wa'ain0 of nooded corrections and thoroby help to ensure the saio uso and handling of radiation sources and radioactivo materials.
' A third objectivo, which is really derived from successful oxocution of the first two objectives,is to gather and document information which will help to ensure that all phases of the operational and radiation protection pro 0 rams are mooting thu
. goal of koopino radiation dosos to personnel and releases of radioactivity to the environment "as low as reasonably achievable" (ALARA).
The annual summary of radiation and contamination hvols moasured during routino facility surveys for the applicablo reporting period is given in Table V.D.3. n.m ,vn--,~w,,,-a--e v.~=,-wn .-,--w--- - e-n-r+ erre-~~~
V 17
]
i i i Table V.D.3 Annual Summary of Radiation Levels and Contemination Levels Observed ! Within the Reactor Facility and Radiation Center During Routine Radiation Surveys l Whole Body Contamination Radiation Levoln Lvvelsm < Accessible location I * *'M (dpm/100 cm ) (Sco figure V D,1) , Average Maximum Average Maximum TRIGA Realtqr_facijity: Reactor Top (DiO4) -i
<1 140 < 500* 1470*
Reactor 2rd Deck Area (D104) 5 40 <500 <500 Reactor Day SW (D104) <1 44 < 500 < 500 Reactor Bay NW (D104) <1 50 <500 <500 Reactor Day NE (D104) <1 25 <500* 810* Reactor Day SE (D104) <1 100 <500* 1090* > Class Dperiments (D104,D302) e1 100 <500 < 500 Demineraliter Tank - Outside Shielding (D104 A) <1 14 <500 <500 Particulate Filter -
.Outside Shielding (D104 A) <1 1 <500 <500 Badiglion Centti:
NAA Counting Rooms (A 140,D100,C134) <1 8 <500 < 500 Health Physics Laboratory (A138) <1 <1 <500 <500 80 Co irradiator Room (A128) <1 8 <500 <500 ' Radiation Research Labs (0114,0122,0124,B132,C130) <1 9 <500 <500 Radioactive Source Storage (B119A) <1 10 <500 <500 Student Chemistry Laboratory , (C118) <1 <1 <500 <500 Student Counting Laboratories
- (C120,C126) <1 <1 <500 <500 '
Operations Counting Room (C123) <1 <1 <500 <500 i Pneumatic Transfer Laboratory. (D102) <1 <1 < 500 < 500 (1) < 500 dpm/100 cm - Less than the lower limit of detection for the portable survey instrument used. (2) The contamination shown for this location assumes 100% smearing of ficiency and was immediately rernoved. As a result, the average contamination level at this location during the reporting period was, for all practical - purposes, <500 dpm per 100 cm'.
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V+18 E. Enyhenmental SUIY1Yl'_Gia The annual reporting requirements of the OSTR Technical Specifications includo "an annual summary of environmental surveys porformed outsido tho facility.*
- 1. Gamma Radiation Moni.torjna ,
I
- a. On-site Monitoring Monitors used in the on sito gamma environmontal radiation rnonitoring
- program at the Radiation Conter consist of the reactor facility stack offluent ;
monitor described in section V.B.2 and nino environmental monitoring stations. These stations consist of a polyothytono bottle placed insido a PVC
- tube attached to the reactor building perimotor fence at a height of four foot I i
(soo Figuro V.E.1). j Each fonce environmental station is equipped with an OSU supplied and { 7 processed TLD area monitor inormally three Harshaw LiF TLD-700 chips por : 7 Li monitor in a plastic "LEGO" mount). Those monitors are exchanged and l processed quarterly. The total number of TLD samples for the reporting , period was 108 (9 stations x 3 chips por station por quarter x 4 quarters por year). A summary of this TLD data is shown I". Table V.E.1. Each fenco environmental station also utilized a CaSO TLD monitoring - packet supplied and processed by Radiation Detection Company (R.D. Co.),
- Sunnyvale, California. Each R.D. Co. packet contained two CaSO4 TLDs and ;
- was exchanged quarterly for a total of 72 samplos during-the reporting period (9 stations x 2 TLDs por station per quarter x 4 quarters per year).
- A summary of Radiation Detection Company's TLD data is also shown in Table V.E.1. .
MonthlyLmeasurements of the direct gamma exposure rate, in micro-roentgens _por hour (pR/hr), were also made at each fence monitoring station. These measurements were made with an Eberline Instrument Company micro R por hout survey meter containing a 1" x 1" Nai detector. $$ eM't**81'? "-p4 ('P*'-s'5++9't9- g .er- pvqMp ruw.fwbq-mg-. pqp--- % .w g g ye.-p9,%.- erp w gr,. 2 wy. m-e-s p p,g yg g9 9 . -wg-g g9ey--.g y %,,g,+g-,w:wqg-yrg e ys*g. -syghewww g g
l Figuro V.E.1 y. j g l Area Radiation Monitor Locations for tho TRIGA Reactor, and on iho TRIGA Reactor Area Fence N -= +- PERIMETER FENCE
\ --
MRC FE3 MRC FE2 - 0FFICE BUILDING 3MRC FE4 MRC FE19 (C , l l ( MRC TNE e MRC TSE e r R A DI ATION , MRCTEN g TRIGA 1 REACTOR CENTER l BAY l 4 BUILDING t MRCTWN $ MRCTSW < l G- _S l ( MRC TNW HX $ MRC THXS i
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V 20 ' A total of 108 pR/hr measutomonts woro taken (9 stations por month x 12 months por year). The total calculated doso equivalent was determined by i i averaging the 12 separate pR/hr measurements, multiplying this averago by 8760 hours per year, and then by converting microroontgens to millirem. A f summary of this data is shown in Table V.E.1. i From Tablo V.E.1 we havo concluded that the doses recorded by the dosimotors ora the TRIGA facility fenco can be attributed to natural background radiation, which is about 110 mrom por year for Oregon (Refs. - 1,2).
. b. Off site Monitoring-The off site gamma environmental radiation monitoring program consists of twenty nionitoring stations surrounding the Radiation Conter isoo Figiero V.E 2) and one station loc "d 5 miles to the south at the Corvallis Airport .
Each off sito radiation monitoring station is equipped with an OSU supplied and processed TLD monitor. Each monitor consists of three (MRCTE-11 has six) Harshaw 'LiF TLD-700 chips in a plastic "LEGO" mount. The mount is placed in a 'polyethylone bottle inside a PVC tube which is attached to the station's post about four foot above the ground (MRCTE 21 and MRCTE 22
- are mounted on the roof of the EPA 1,ab and National Forage Seed Lab,
- l. respectively). Those monitors are exchanged and processed quarterly, and the total number of TLD samples during the curtont ono year reporting period was 264 (20 stations x 3 chips por station por quarter x 4 quarters por year 4 plus 1 station x 6 chips per station per quarter x 4 quarters por year). A 4 summary of the OSU off-site TLD data is provided in Table V.E.2. Thirtoon ,
of the off site radiation monitoring stations also have a thin weather-tight l- aluminum box mounted to the post at approximately four foot above the
. ground (these stations do not have an "L" at the end of the station
.. identification number) The aluminum box contains a packet with two L. CaSOg;TLDs supplied and processed quarterly by the Radiatloa Detection Company. The total number of R. D, Co. TLD samples for the raporting nn--> ,-wn,-,--n..n.~ - , , , - - - . . ,,u , , . . ,n,, _ w ,r .,,,,,,a , ,,g- ,-r--
V 21 Table V.E.1 Total Dose Equivalent at the 1RIGA Reactor I acility Fence
. Total Calculated e7ta, Total ficCorded TotDI Recorded Doto Equivalent Envi o Dose Equivalent Dose Equivalent Based on the donitorir.;
Based on R.D. Co. Based on OSU Annual Average Station 1 L D s"' TLDs C H 3' pR/hr (mrem) (mr m) Expotuto Rato") Fip e 1) Imrern) MRCFE 1 98 73 1 5 87 1 19 MRCFE-2 101 75 1 3 93 1 16 fARCFE-3 103 79 t 5 91 1 18 MRCFE-4 105 79 1 2 106 1 24 MRCFE 5 90 68 s 5 80 1 19 MRCFE-6 97 74 1 6 90131 MRCFE 7 96 73 s 8 86 2 16 MRCf E 8 100 74 4 86 3 18 MRCFE 9 95 70 t 9 73 3 12 (1) Radiation Detection Company (R.D. Co.) TLD totals include their annual natural background contribution of 75 mrem for the reporting period. Average Corvallis area natural background using Radiation Detection Company TLDs totals 85 mrom for the same period. (2) OSU fence * 's include a measured natural background contribution of 631 4 mrem. (3) i values represent the standard deviation of the total value at the 95% confidence level.
0 ) V 32 Figuro V.E.2 Monitoring Stations for the OSU TRIGA Reactor !
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l V.23 1 Table V.C.2 Total Dose Equivalent at the ofI Site Gamma Haciation Monitoring Stations te Total Calculated Total Recorded Total Recorded Doso Equ' talent Ra$ahn Dose Equivalent Dose Equiva!cnt Dated on the 2 1
"""'N3 Station Based on R.D. Co. Based on OSU . Annual Average !
TLDs? 1 LDs'*' Mr 'l (ce Nure' (mrem) (mrem) Exposure Hatt* 1
-V.E.2)
,,, ,g ) 4 MRCTE 2L --
7316 53 $ 12 ' MRCTE 3 103 70 t 6 91120 ; MRCTE 4 94 6916 78 3 16 i MRC1E-6L - - 79-t 17 84 2 11 i MRCTE 6 100 7427 94 A 20 MRCTE 7L - 67110 91216 > MRCTE-8 ' 106 7825 96 :t 23 MRCTE 9 101 69 i 8 87124 MRCTE 10 89 72 1 14 74120 ' fARCTE 11 88 5844 68 t - 13 ' MRCTE 12 102 76 i 7 D* i 28 ' MRCTE-13L - 90t 7 84121 MRCTE 14L - 70 4 15 69 1 12 - MRCTE 15 96 78 1 6 75-i 1B , MRCTE 16L - 76s 12 831 10 MRCTE 17 '89 76 210 69114 , MRCTE-18L -- 77127 87112 MRCTE-19 106 89 i '14 93 1 12
- MRCTE 20L -
94212 83122 MRCTE 21 73 6224 44 x 7 MRCTE-22 81 6816 68110 (1) Monitoring stations coded with r.n 'L' contained one standard OSL, hD pack only. Stations not coded with an
,'L' contained,in addition to the OSU TLD pack, one R.D Co. TLD monitoring pack. ,
(2)~ Radiation Detection Company TLD totals hclude their annual natural background contnbution of 76 mrom for
- the reporting period. Average Corwilis esca natural background usirig Radiation Detection Company TLDS totals i 85 mrom for the same period.-
(3)- OSU off-site totals include a measured natural background contribution of 63 , 4 anrem. l
'(4) ~ t value6 sepresent the standard deviation of the total value at the 95% confidence level.
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. u_ ,._.._...-.__..__.~..;__ ,-..,m . . , _ - _ . . - - , _ . .,..,,-.,. .-r---,., _--, - ,... _ . .-
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V 84 period was 104 (13 stations x 2 TLDs per station per quarter x 4 quarters por year). A summary of Radiation Detection Company's TLD data for the l off site monito ing stations is also given in Tavio V.E.2. In a manner similar to that described for the on site fence stations, monthly
]
measurements of the direct gamma exposure rate in microrcentguns por hour ( R/hr) are made at each of the twenty one off site radiation monitoring stations. At, noted before, those measurements are made with an Eberline l Instrument Company micro R per hour survey meter containing a 1" x 1" Nat
)
detector. A total of 252 pR/hr measu'ements were mado during the reporting period (21 es tions per month x 12 months per year). The total dose equivalent for each station was determined by averaging the 12 - separate R/hr measurements, multiplying this average by 8760 hours per year, and then by converting microroentgens to millirem. A summary of this ; data is given in Tablo V.E.2. Aftor a review of the data in Table V.E.2, we have concluded that, like the doslmeters on the TRIGA facility fence, all of the doses recorded by the , off-site dosimeters can be attributed ta natural background radiation, which is about 110 rntern per year for Oregon (Refs.1,2).
-3
- 2. SpikYial&.And Venet_atimLSmy.gyj i
The soil, water and vegetation monitoring program consists of the collection and i analysis of a limited number of samples in each category on a quarterly hasis. The program monitors highly unlikely radioactive material releases from either the TRIGA reactor f acility or the OSU Radiation Center, and also helps indicate the general trend of the radioactivity concentration in each cf the various substances sampled. See Figure V.E.2 for the locations of the samplirig stations for grass (G), soil (S), water (W) and rainwater (RW) samples. Most locations are within a 1000 foot radius of the reactor f acility and the Radiation Center. In general, samples are collected over a local area having a radius of about ten fact at the positions indicated in Figure V .E. 2.
.- =
t W p-4-,- w,-- ig**q y yfw pu'ri>y eg-4-ii- - Wswp1- y--yw- y 19-=yNyv .*ygeiy.W- y ore c -9 p y - g p Yrip-'-r'M'599'y--'w--y vTe-Tr-d*-7dr p 9 ,y9- ma3g-----7,4- yw yh>,-wy-py- p yway 4 -yyw-
V 25 Tr4ere are a total of 22 quarterly sarnpling locations: four soillocations, four water locations (when water is available), and fourteen vegetation locations. The total number of samples possible during the reporting period is 88 (16 soil samples,16 water samples, and 56 vegetation samples). The annual average concentration of total not beta radioactivity iminus tritium) for samples collected at each environmental snil, water, and vogetation sampling location (sampling station)is listed in Table V.E.3. Calculation of the total net beta p disintegration rate ;ncorporates subtraction of cnly the counting system back-ground from tho gross beta counting rate, followed by application of an appropri-ato counting system efficiency. The annual average concentrations were calculated using sample results which exceeded the lower limit of detection (LLD), except that sample results which were
, loss than or equal _ te-the LLD were averaged in at the corresponding LLD
_ concentration. Table V.E.4 gives the average LLD concentration and the range of LLD values ior each sample category for the current reportint ratiod.
- As used in this report, the LLD has been defined as the amount or concentration
- of radioactive material (in terms of Ci por unit volume i t. M mass) in a represen-tative sample, which has a 95% pmbab::ity of being .tected..
Identification.of specific radionuclides is not toutmely carried out es part of this monitoring program, but would be conducted if unusud radioactivity les els above , natural background were detected. However, from Table V.E.3 it can be seen that the levels of radioactivity detected were consistent with naturally occurring radioactivity and comparable to values reported in previous years. E' _ _ _ _ i
. e *- - - . .m - , .-. - . - -- re ,* .. -- .-
V-26 ( Table V.E.3 Annuri Average Concentration of the Total Net Beta Radioactivity (Minus3H) for Environmental Soil, Water, and Vegetation Samples Anr.aal Average Concentration ocam@6 Sample P 9 s (Ses R;ure . lype of the Tota) Net Beta (Minus3H) "* Radioactivity"' V.E.2) 1 -W Water (2n3>2.48 x 10 8 13.33 x 10# vCi/cc 4-W Water (2n482.55 x 104 t 1.83 x 10-8 Ci/cc 11 W Water (2>2.55 x 10'8 1 1.!) x 10 8 Ci/cc 19-RW Rainweter 2'2.55 x 10 8 2 1.59 x 10'8 pCi/cc , 6 3S Soil 9.53 x 10 t 1.51 x 10 6 Cilgram of dry soil 5-S Soil 7.91 x 10~5 2 1.47 x 10~6 pCi/ gram of dry soil 20-S Soil 9.87 s 10~6 1 1.50 x 10 6 pCilgram of dry ; oil 21-S Soil 3.76 x 106 1 1.42 x 10-6 pCi/ gram of dry soil 2G Grass 4.04 x 10 4 3.96 x 10 6 Ci/ gram of dry ash 6G Grass 3.76 x 104 13.85 x 10'6 pCi/ gram of dry ash 7-G Grass 3.86 x 10-*
- 4.?? x 10 6 Ci/ gram of dry ash 8-G Grass 3.05 x 104 1 3.38 x 10'6 pCi/ gram of dry ash 9G Grass 3.34 x 10*
- 3.03 x 10 6 vCi/ gram of dry ash '
1 LG Grass 4.11 x 104 t 3.74 x 10 6 pCi/ gram of dry ash 12 0 Grass 4.33 x 10'" 13.55 x 10'6 pCi/ oram of dry ash 13-G Grass 3.43 x 104 13.56 x 10~6 Cilgram of dry ash 14-G Grass 2.67 x 104 13.64 x 10'6 Ci/ gram of dry ash 15-G Grass 2.80 x 104 2 3.07 x 10'6 pCi/ gram of dry ash 16-G Grass 2.98 x 104 t 2.83 x 10-6 vCi/ gram of dry ash 17 G Grass 4.31 x 10 4 1 3.87 x 10'" Ci/ gram of dry ash 18-G Grass 4.26 x 104 2 3.56 x 10'6 Cilgram of dry ash 22-G Grass 3.16 x 104 13.30 x 10'6 pCi/ gram of dry ash (1) i values represent the standard deviation of the average value at the 95% confidence level. (2) Leas thar, lower limit of detection value shown. (3) Based on two quarterly samples. Location was dry during two sampling periods. (4) Based on three quarterly samples. Location was &y during one sampling period. l l
l V-27 l l Table V.E.4 - Average LLD Concentration and Range of LLD Values for Soil, Wt ter and Vegetation Sao ples Sample Average Range of Reportino Type LLD Value LLD Values Units Soil 1.94 x 10* 1.28 x 106 to 2.70 x 10 5 Ci/ Oram of dry soil Water 2.55 x 10'8 2.47 x 10 " to 2.68 x 10'" Ci/cc - Vegetation 4.05 x 10* 1.69 x 106to 7.85 x 10 5 pCi/ Oram of dry ash m
- c. ..
V-2 8 - F. Badioactive Material Shloments A summary of the radioactive material shipments orginating frcm the TRIGA reactor facility, NRC license R 106,is shown in Table V.F.1. A similar summary for shipments originating from the Radiation Contor's stato of Oregon radioactive materials licenso ORE-0005 3 is shown in Table V.F.2. e e 4 /
V-29 Table V.F.1 Annual Summary of Radioactivo Material Shipments Ori0inating From the TRIGA Reactor Facility's NRC License R-106 Number of Shipments Total Shipped To Activity Type A Quantity L.inuted (Cur es) Quantity White Yellow Yellow Total i 11 Ill OSU Physics Dept. Corvallis, OR 3.3 x 10 4 -- -- 1 -- 1 OSU Oceanography Corvallis, OR 2.3 x 10' 4 -- 4 -- 8 OSU Fisheries & Wildlife 7.5 x 10 4 -- - 2 -- 2 Corvallis, OR Univ. of Washington Seattle, WA 5.2 x 10 5 5 -- -- -- 5 , Univ. of Alaska Fairbanks, AK 2.8 x 10' -- -- 1 -- 1 Lawrence Berkeley Laboratory 7.0 x 10~6 -- -- 1 -- 1 Berkeley, CA Bureau of Mines 6.2 x 10 4
~
Salt Lake City, UT -- -- 2 -- 2 Brigham Young Univ. Provo, UT 2.0 x 10 5 1 - -- -- 1 Un;v. of Wyoming Laramie, WY 1.6 x 10 4 5 -- -- -- 5 Rensselaer Poly. Institute 1.8 x 10' 5 -- 3 -- 8 Troy, NY TOTALS 8.9 x 10- 20 0 14 0 34 _ _ _ _ _ . _ _ _ _ _ _ . . _ _ _ _ ______m_____.__._________.____-________.______m_ _ _ _ _ _ _ _ _ _ _ _ ___.-_- ....-w
V-30 Table V.F.2 Annual Summary of Radioactivo Material Shipments OriginatinD From the Radiation Center's State of Ore 0on License ORE 0005 3 Number of Shipments Total Shipped To Activity Type A Quantity Limited Quantity . Whito Yellow Yellow Total I il ill OSU Pharmacy Corvallis, OR 3.7 x 10'5 10 -- -- -- 10 1 i Lawrence Berkeley Laboratory 7.4 x 10 1 -- -- -- 1 Berkeley, CA UC Berkeley - Berkeley, CA 1.5 x 10'5 1 -- -- - 1 Cal. Tech. Pasadena, CA 1 x 10'7 1 -- -- -- 1 Univ. of Missouri Columbia, MO 8.3 x 10~8 1 -- -- -- 1 Univ. of Tennessee Knoxville, TN 8 x 10 e ) ,, ,, ,, 3
~
State Univ. of NY Albany, NY 4.5 x 10 1 -- -- -- 1 TOTALS 8.0 x 10~5 16 0 0 0 16
- . . . - . . . . . . . - . . . - - . - . - . . --~. . = - . . . ~ . - - -. - - - .. V-31
.G, References
- 1. U.S. Environmental Protection Agency, " Estimates of lonizing Radiation Doses in the United States, 1960-2000," ORP/CSD 72-1, Of fice of Radiation Programs, Rockville. Maryland (1972). >
- 2. - U.S. Environmental Protection Agency
- Radiological Quality of the Environment in the United States,1977," EPA 520/1-77-009, Office of Radiation Programs:
. Washington, D.C. 20460 (1977).
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.l 1
PART VI i WORK .' l it ' l2 , _ f-
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' PART VI WORK
. A .' Summary The Radiation Center offers a large variety of resources for teaching, research and service related to radiation and radioactive materials. Some of these are discussed in detail in other parts of this report.- The puipose of this part is to summarire the teaching, research.and service efforts carried out curing the current reporting period.
B.- Teachino The must important responsibility of the Radiation Center and reactor is to support - OSU's academic programs, implementation of this support occurs through direct- , involvement of the Center's staff and facilities in the teaching programs of various departments and through our participation in University research programs. For example, during the_ current reporting periodithe Radiation Center accommodated 62 OSU academic classes involving a number of different academic departments. In
- addition, portions of classes from other Oregon universities were also supported by the Radiation Center. The 03U teaching programs (not including research)-utilized 569 hours .of reactor time. Tables ill.A.1 and ill.E.1 plus section VI.C.S provide more detailed information on the use of the Radiation Center and reactor for instruction and
- training.
- C. Research and Service Almost all Radiation Center research and service work is tracked by means of a project
! : system. When a request for facility use is received, a number is assigned to the project l .
' and a project sheet is generated. This sheet includes such information au the project -
number, data about the person and institution requesting the work, a description of the pr_oject,' Radiation Center resources needed, the Radiation Center project manager,. , estimated costs for the project, and the funding source.
. - . , . . ._ _ __ _ .__ . . . . . - . - _ . _ . . .. ~ _.._ _ - _ . . ._._._ _ ~..~.m - _.
VI 2 , Table VI.C.1 provides a summary of institutions and agencies which used the Radiation-Center during this reporting period. This table also includes additionalinformation about the number of academic personnelin"alved, the number of students involved.and the numberiof ~ uses logged for each organization. Details on graduate student thesis research which used the Radiation Center are given in Table VI.C.2. . The major table in this section is Table VI.C.3. This table provides a listing of the
- research and service projects carried out during this reporting period and listsinformation
.- relating to the personnel and institution involved, the type of project, and the funding
-agency. Projects which used the reactor are indicated by an asterisk. -
In addition to identifying specific projects carried out during the current reporting period, - Part VI also highlights major Radiation Center capabilities in research and service. These . unique Center functions are described in sections VI.C.1 through VI.C.8. f s .g' i ,r i T
.-. , i , . - , , , , . . . , . , s,,..
VI-3 Table VI.C.1 Institutions and Agencies Wtnch Utikied the Radiation Center Number of Numtier of
""'""U institution
""* "' f aculty Students Pmiects nter involveJ involved f.acihties
' Oregon State University"'
Corvalbs. Oregon 71 56 44 927 U.S. Environmental Protection Agency Corvaihs Oregon 2 NA NA 2 Good Samaritan Hospital -- Corvalks, Oregon 1 NA NA 5 M. Bloomfield Corvattis, Oregon 2 NA NA 2 Corvaits fire Oepartment Corvallis, Oregon 1 NA NA 4
'Myers Mechanical and Meta!!urgical, Inc.
Corvallis, Oregon 1 NA NA 1
'NCASI Corvallis, Oregon 1 NA NA 3 U.S. F' :reau of Mines Albany Oregon 2 NA NA 1 McBee and Ass.ociates Lebanon, Oregon 2 NA NA 6 Oregon Department of Energy Salem, Oregon 2 NA NA 13 _ 'Willamette University Salem, Oregon 1 1 0 1 <
Sun Seeds Brooks, Oregon 1 NA NA 4
' University of Oregon Eugene, Oregon 10 9 4 11 U.S. Environmental Protection Agency Newport, Oregon 1 NA NA 2 Pacific University Forest Grove, Oregon 1 1 1 10
- Oregon Health Sciences University Portland, Oregon 6 4 1 37
- Used the OSTR.
(1) Use by Oregon State University does not include any teaching activities or classes accommodated by the Radiation Center.
VI-4 Table V..C.1 (Continuedi
" * 'U' '
Number of Number o' institulion Facuity
***U' Studen's jects nter invoh ed involved Facilities Vollum Institute, OHSU Portland, Oregon 1 NA NA 4 Oregon State Health Division, Radiation Control Portland, Oregon 2 NA NA 4 Oiegon State Pohce Portland, Cregon 1 NA NA 2 W. Chism Vancouver, Washington 1 NA NA 2
' University of Washington Seattle, Washington 3 3 1 5 Bottelle Pacific f4orthwest Laboratories Richland, Washington 1 NA NA 1 M.B. Research Burnaby, DC, Canada 1 NA NA 1
' University of Alaska Fairbanks, Alaska 1 1 0 1
'Humboldt State University Arcata, Cahfornia 1 1 3 1
' Lawrence Berkeley Laboratory Berkeley, California 1 2 0 2
' University of Cahfornia-Santa Barbara Santa Barbara, California 2 4 1 2
'Califomia State University-Northridge Northridge Cahfornia 1 1 0 1
' University of Cahfornia-Los Angeles Los Angeles. California 3 1 3 3 D. Parsons Fallbrook. Cahfornia 1 NA NA 4
' Montana Col!ege of Mineral Science and Technology, Dutte, Montana 3 3 0 3
'U.S. Bureau of Mines Salt Lake City, Utah 1 NA NA 4
*Brigham Young University Provo, Utah 1 1 0 1
- Used the OSTR.
s
_ . . . -_ . - - . ~ . . - - . - - . . . . ~ ~ . . _ - . . . . - - - . . - - . _ . - . ~ . . . . . . - - - . . . VL5 Table VI.C.1 (Continued) l Number of - Number of . N" *
- OI
"**'D' 08 D' institution faculty Students rojects ""IU' Involved : ; involved Facilities
- ' University of Wyoming Laramie, Wyorning 1 1 2 9
' University of Arizona Tuscon, Arizona 1 2 1 1
' University of Colorado Boulder, Colcrado 2 2 2 3
' Colorado School of Mines Golden, Colorado 1 1 1 1 South Dakota School of Mines and Techr. ology. r ~ Nty, S. Dakota 1 2 1 1 University of ik a >
- Albuquerg, ' exico 1 2 0 1
' Texas Tech. University Lubbock, Texas 2 2 1 2
' University of Texas--Arlington Arhng'on. Texas 3 2 0 -
3
' Rice Unhersity Houston. . Texas - 6 4 ,
2 6 R._Donelick . Houston, Texas 1 1 0 1 Trinity University San Antonio, Texas 2 1 1 1-Stratcor Hot Springs; Arkansas - 1 NA NA 3 Louisiana State University Baton Rougei Louisiana i 1 0 1
'Tulane University New Orlean::, Louisiana = 1 1 1 1 University of Notre Dame Notre Dame, Indiana -
1 1 0 2
'EG&G Ortec Oak Ridge, Tannessee 1 NA NA 1
' University of Tennessee
- Knoxville, Tennessee 4 2 1 6
' University of Rochester Hochester, New York 3 3 3 3
' used the OSTil
.-. . . . _ , . _ - - - - -- , - - . _ _ . _ _ _ _ _ _ _ _ _ _ . - _ _ _ - - = _ - -
VI 3 Table VI.C.1 (Continued) Number of Number of Number of Number of Uses of lastitution - F aculty _ Students r jects Center involved _ involved . Facihties
' City College of the City University of New York New York, New York 2 1 :0 2
' State University of New York Albany, New York 3 3 2 3
'Rensselaer Polytechnic Institute Troy, New York 3 1 3 12 University of_ North Carolina .
Greensbo o, North Carolina - 1 1 1 .1
' North Caruhna State University Italeigh, North Carolina 2 2 2 2
'Clemson Unisersity Clemson, South Carohna 1 1 0 2
' University of South Carohna, Aiken Aiken, South Carolina 7 3 2- -2
' University of Florida Gainesville, Florida 2 1 4 2 International Atomic Energy Agency Vienna, Austria 1 1 1 -1 Austrahan Museum Sydney, Austre'ia 1 1 0 1 1'
TOTALS 189- 131 89 -1,146 9
- Used the OSTR.
I R -i Table VI.C.2 L
' Graduate Student Thesis Research Which Utilized the Radiation Center s
.j
. Student's Name ;
3
- Program ; Academic Department :Facu!ty Advisor- Thesis Topic - j
- 1 i
OREGON STATE UNIVERSITY l Abdul-Hamid, S. PhD Nuclear Eng'neering i Klein Lifetime Performance of Thermionic Fuel Elements ! t +
- Ahmad; l. PhD Geosciences Lawrence Petrologic and Tectonic im;>lications of igneous Rocks from Pak.istan
' Ahn, H. MS Nuclear Engineering Reyes A.P600 Long-Term Cooling Test k l Al Baroudi, H. 'PhD Nuclear Engineering 'Klein Heat Rejection System in Space Reactors [
Ala, A. t PhD Nuclear Engineering Reyes An Expenmental Investigation of Two-Phase Natural Circulation in a Passively Safe : Reactor System Al-Kheliewi, A. PhD Nuclear Engineering Klein Transient Thermalhydraubc and Thermionic Performance Analysis l Almonacid, F. MS Food Science Torres Microbiat Stabilization of Minced Fish Seafood l
-i Anand, A. MS Nuclear Engineering Binney Design of Marine Sample Analysis Systems !
- Baik, S.-H. MS Radiation Health Higginbotham "Sr/"Y Ouantification in Environmental Samples Using Beta Particle Spectroscopy' !
with Active Gamma Ray Discriminat+on Bostick, K. MS Nuclear Engineering Klein A Two-Dimensional Temperature Modetting cf Target Materials Bombarded by lon I Beams I Bukar,K. MS Nuclear Engineering. . Robinson Comparison of Various Flux Calculational Methods in Nodal Codes Chen,' C. Agricultural Chemistry Whanger Chemical Analysis of Goat Tissue from Eastern Germany Cho,B. MS Nuclear Engineering Robinson Nodal Methods for Calculating Nuclear Reactor Transients, Control Rod Pattems, ; and Fuel Pin Powers i Desonie, D. PhD Oceanography Duncan "Ar "Ar Dating Donnely, P. PhD. Forest Science Entry Herbicide Degradation
- Dundon, L PhD Physics Gardner High Pressure Perturbed Angular Correlation-ZrO 2 ,
Eichenberg, T. MS Nuclear Engineering Reyes Numerical Analysis of Condensation induced Water-Hammers in Ho zontal Piping . Systems '! r
- Thesis research which utilized the OSTR. !
4 i _# , , _ . ~ . . . . .
6 Table VLC.2 (Continued) Tiesis Topic Program Academic Department Faculty Advisor
- Student's Name Chemistry Daniels Time-Resolved Laser Spectroscopy of Nucieic Acids
$ Vingxian PhD Gardner Pertubated Angutar Correlation Spectroscopy of Condensed Matter (at Devated "Fuchs,K. PhD Phys cs Temp!
Nuclear Engineering Robinson Development cf an Objeci Onented Expert System for PWR Co e Re; cad Greek, K. PhD Nuclear Engineering Robinson Process Monitoring and Control with Expert Systems in Nuciear Engineenng Greene, K. PhD Nuclear Engineering Klein Space Nuclear Reactor Gu8shan-Ara, Z. MS Physics Krane y-y Angular Correlat: ens for "#Er
*Gummin W. PhD Microbiology Rohevec Kdhng of Bacterial Kidney Disease Gutenberger, S. PhD Dodd Radiation Protection Opttm4zation of a Broad License Fac20ty Hicks, T. MS Radiation Health Taylor Controls on Skic Magma Evolution in the Central H;gh Cascades of Oregon
- Hdt, B. PhD Geosciences Jordheim, D. MS Nuclear Engineering Binney Production of 2nPu in Vivo Behavior of Detergent-Solubdized Purified Thrombemodu5n on Intravenous l
Kalns, J. PhD Pharmacy Ayres l injection into Rats Torres Microbia! Stabilization of Shrimp Seafood Kantt, C. MS Food Scaence Ddles Trace Element Contents from Vanous Ore Deposits in Pakistan
*Kausar, A. MS Geosciences Nuclear Engineenrr3 Klein Fabhc Composite Heat Pipe Testing and Construction Kiestier W. MS Nuclear Engineenng Heyes A Study of Buoyant Backilow anstabihties in a 1/5 Scale Reactor Geometnr King, J. PhD Nuclear Engineering Reyes A General Theory for Flooding Imv'ementing the Cuspoid Catastrephe Lafi, A. PhD Grunder Structure and Geochemistry of the Steens Mountain Sasait
*Langer, V. MS Geosciences Nuclear Engineering Klein Systems Analysis for an Advanced lhermionic Reactor Lee, H. MS Microbiology Bottomley Shizcbium Ecology Leung,K. PhD Nuclear Engineering Klein in{ ore Ucutrorpc Analysis of an Advanced Thermionec Reactor Lewis, B. MS
- Thesis research which utilized the OSTR.
j
.t Table VLC.2 (Continued) '?
- Student's Name : : Program ' Academic Department Faculty Advisor ' Thesis Topic I
- Liu, Y.-G. PhD Chemistry Schmitt A Chemical and Petrographic Study of Refractory Irclusion From KABA (CV3) t Chondrite Luicx, B. PhD Food Science & Tech. Penner Passage of Food Components Through the GI Tract of as lat [
- M? clean, l. MS ' Geosciences Schmitt Practical Applecation of INAA to Geologic Materiais. l Mankowski., M. MS Entomology Morre!! Hott Preference of Dampwood Termites on Western Wood Species Marks T. MS Nuclear Engineering Klein Space Reactors . I Martsoif, S. i MS Radiation Health Binney Pituitary Tumor Therapy Using Boron Neutron Capture Therapy ;
*Mathis. A. MS Geosciences Grunder Age, Stratigraphy and Petrogenesis of Rock from Hart Mountain
*McDwee, C. PhD Oceanography Duncan "Ar Ar Dating Miles. T. MS Nuclear Engineering Binney MCNP KCODE Criculations !
Pauley, K.- MS Nuclear Engineering Klein Fluid ana Thermal Calculattons for Bubble Membrane Radiation for Space Nuclear Power Apolications l Pawlowski, R. MS Nuclear Engineering .Klein Temperature and Power Performance for Thermionic Fuel Elements in an Advanced Space Power Plant Piepmeier, E.' PhD Pharmacy Ayres in Vivo Benavior of Detergent-So!ubilized Purified Thrombomodulin on Intravenous Injection into Rats i
- ' Pratt, D. MS Radiation Health Higginbotham Hot Particle Detectors l Saleh, H. PhD Nuclear Engineering Binney Fdtermg of Nat Detector Output ;
*Schiiki A. PhD Chemistry S<,nmitt INAA of Meteorite Materials !
Shanks, C. MS Microbiology Rohovec ElBS Studies t Smith, E. . PhD Pou try Science Savage X-irrad^ator Induced Chromosomal Mutations in Turkeys Snuggerud, R. MS Nuclear Engineering Klein Theory of Fabnc Composite Heat P:pe Oxration
*Streck, M. PhD Geosciences Grunder PetrochemicalInterpretation of the Rattlesnake Ash-Flow Tuff, Southeastern Oregon So,H. PhD Physics Gardner Use of Angu!ar Correlation in Studies of Zirconia and Zirconia Alleys i
- Thesis research which utilized the OSTR.
- I t'a i
s a Table VI.C.2 (Continued) O
. Student's Name ' ~ Program - l . . Academic Departmer ti Faculty Advisor-- Thesis Topic L
- Turner, S. MS- Nuclear Engineering Binney Production of Medecal Radioisotopes
*Weise, K. MS ' Geosciences '
Practical ApplicaSon of INAA to Geolegic Materials Zahm, L. ME Nuclear Engineering Klein Cold Fusion Experiments UNIVERSITY OF OREGOu r
- Hull, C FnD Geological Sciences Petroch mistry of Feeder Dikes for the P6cture Gorge Basalts, Oregon :
*Maurtio, R. MS Anthropology - Ayres Geochemical Sourcing ct Uthic Materials from Pohnpei Island, Micronesia
- Skinner, C. PhD Anthropology Aikens Geologic and Archaeologicat Obsidian From Westem Oregon
- Stimac, J. PhD Geological Sciences Goles/McB<ney Characterization of the Sraergaard intrusion PACIFIC UNIVERSITY
*Wollan, G. MS Physics Brosing Gamma Dose Rate Measurement in a 250 kW Research Reactor UNIVERSITY OF WASHINGTON
- Russell, A. PhD Oceanography Emerson Use of Urar.ium in Foramirtfera as a Tracer of Deep Water Anoxia in the Pleistocene i
UNIVERSITY OF CAllFORNIA--SAN FRANCISCO
~ *Williard, R PhD Hunt in Vrvo Behavior of Detergent Solubilized Purif ed Thrombomodu8in on Intravenous i injection into Rats UNIVERSITY OF CAUFORNIA-SANTA CRUZ *Closmann, C. MS Sisson Trace Element Mocelling of Open and Closed System Magmatites UNIVERSITY OF CAlfFORNf A-SANTA BARBARA *Hoernle, K.
PhD Geology Tilton Petrochemistry of Volcanic Rocks From the Canary Istar js
- Thesis research which utilized the OSTP.
Table VI.C.2 (Continued)
/
Faculty Advisor Thesis Topic Student's Name' Program Academic Department UNIVERSITY OF CALIFORNIA-LOS ANGELES PhD Earth & Space Sciences ' Davidson Geology and Petrology of Quaternary Volcarsc Rocks from the Salon De Vyvrs
- Fee!ey, T.
Region Southwest Bohvia , UNIVERSITY OF COLORADO PhD Geological Sciences Farmer Isotopic Study of Early Protoroic Crustai Growth in Southern Wyoming
- Ball, T.
- Skewes, A. PhD Geological Sciences Stern Andean Volcanism COLORADO SCHOOL OF MINES Geochemical Characterization of Archean Felsic igneous Rocks so the Granite i
- Langstaf f, G. PhD Geology I
- olden M3untains, Wyoming UNIVERSITY OF ARIZONA MS Geosciences Damon Volcano-Stratigraphy and Fetrogenesis of the Mid-Tertory Gahuro Volcanics.
- Durchell, A.
Southern Antoru SOUTH DAKOTA SCHOOL OF MINES AND TECHNOLOGY
- Fntch, E. MS Geology Shearer /Patterson Petrogenetic Relations Between Gold M,nerahration and Igneous intrusions in the Black Hdis, South Dakota TEX AS TECH. UNIVERSITY PhD Geosciences Bames Geochemistry of the Composite Enghsh Peak P:uton, Klamath Mourttains. Cahforrua
'Schmidt, B.
RICE !!N!VERSITY Geology Sisson Element Mobihty Related to Partial Melting and CofStreaming in Granchtes from
- Baker, L. PhD Southwest No way and Southern indra
~.
- Thests research which utthred the OSTR.
,5.-
Tabfe VI.C.2 (Centinued) d ; P a Student's Name' : Program : ' Academic Department - Faculty Advisor ' 1 Thesis Topic - TUI.ANE UNIVERSITY
*Sanchez, E.- PhD Geology Nelson Geology and Petrology of Socorro Island, Revillagigedo ArcNeefago, Mexico ~
i UNIVERSITY OF TENNESSEE
'Jin,Y. PhD ' Geological Sciences Taylor ' Elemental Characterization of Mineral Separates and Bu rk Rocks -
- UNIVERSITY OF ROCHESTER
' Cole, R - PhD Geological Sciences ~ DeceHes . Tectonic 1mphcations of Miocene Volcanic Rocks, Santa Maria Province. Cakforrua
*Rdgway, K. PhD Geosciences DeCe!!es Determine Source Areas of Sediment FiHing Along Dena:i Fault, Yukon Territory, t Canada
'Sharma, M. PhD Geological Sciences Basu Charactenzation of the D;fferent Mantie Reservoirs Responsible for the Dngin of the l Permo Triassic Sibenan Flood Basalts L
F STATE UNIVERSITY OF NEW YORK
'Bruechert, V. MS Geologica! Sciences Delano Geochemical Constraints on the Origin of Paleoroic fronstones
*Schuster T. PhD Geological Sciences Delano Geochemical Constraints on the Origm o,' Paleozoc tronstones UNIVERSITY OF SOUTP CAROLINA
- Beaman, J. MS Geology Shervais Petrology and Geochemistry of the Coast Range Ophioitte en Northern Cahfortsa
*Zogiman, M. MS Geology ,
Shervais Petrology and Geochemistry of the Coast Range Opfwohte in No'them Cahfornia ' -[ UFiVERSITY OF NORTH CAROLINA '
)
- Miller, J. PhD Ge0 logy ' Glazner Cenozoic Magmatism of the SW United States !
I L
- Thesis research which utilized the OSTR. ,
I i f
Table VI.C.2 (Centinued) , t 4 i Student's Name : i Program - i Academic Department , : Faculty" Advisor.-:- - Thesis Topic - NORTH CAROf INA STATE UNIVERSITY- '
'Galar, P. ' PhD Marine, Earth and - .Fodor Petrogenesis of Gabbro and Ultramafic Xenoliths from Mauna Ke2 Volcano, Hawaii.
Atmospheric Science
'Gandhok, G. 'MS Marine, Earth and Fodor Mantie Characteristics Beneath Northem Brazil Atmospheric Science -
UNIVERSITY OF Ft.ORfDA *
'D'Arcy, K. PhD. Geology . Muetter Geochemistry of Precambrian Metamorphic Rocks of the Montana Metasedimentary.
Terrane ,
- - Home,L MS Geology- Mueller - Geochemistry of Precambrian Metamorphic Rocks of the Montana Metasedimentary I
Terrane
- Murphy. J. MS- Geology - Muetter Madison Range Archean Rocks from Southem Montana
*Weyand, E. MS Geology Mueller Madison Range Archean Rocks from Southem Montana '
I b i ! l . -i II 6 i i ai
- Thesis research which utiiired the OSTR. I*
to
..i
+ v e a e- m ~ 8. - - -~ r
- - - e .,n,n.,., ,
6 Table VI.C.3 $ Listing of Major Research and Service Projects Performed or in Progress at the Radiation Center and Their Funding Agencies Project . . Department and
' Numtier User (s) Name T institution Project Title - Descriptsn Funding Agency 118 G. Larson National Park Service, OSU Crater Lake Study of the primary production of phytcotankton in Forestry, OSU M. Herley Cooperative Studies Unit Crater Lake using '*C labelled substances. *165 J. Cooper NEA, Inc. Pollution Studies NAA of sediments and filter papers. NEA, Irc.
192 N. Kerkvfiet Veterinary Medicine, OSU Mice Irradiation immunosuppression of mice by gamma irradiation. Veterinary Medi-R. Tomar eine. OSU
'231 H. Wollencerg Lawrence Berkeley GRP Project Fission track determination or uranium distribution Lawrence Berkeley S. Flexser - Laboratories and at:undance in fractured heated rock. Laboratories
*321 J. Steidtmann Geology, University of Foreland Investigation Fiss>on track determination of the location of 23sU, University of P. Groll Wyoming 23e0 and 23: Th in natural rocks and minera!s. Wyoming G. LeFebre
*322 D. Mitter Geology, Rensselaer Fission Track Research Fission track determinat:on of the location of Geology, M. Roden Polytechrsc Institute uranium and thonum in r atural rocks and minerats. Rensselaer Poly-R. Donetick technic Institute
'335 B. Kowallis . Geology, Brigham Young BYU Fission Track Study Fission track dating of natural rocks and minerals. Geology, Bngham University Young University
*374 K. Tabbutt Earth Science, Dartmauth Fission Track Studies Fission traca irrad ations in the thermal column. Dartmouth Cottege COUege
*377 B. Idleman Earth Sciences, Westem Fission Track Age Dating Fission track irradiations of apatites and zircons in Western Carolina Caro:ina University the thermal column for age cating. Urwversity
'398 R. Schmitt Chemistry, Geology, OSU High Cascade Mafic Plat- INAA of minerals separated from eclogite rock Radiation Center, S. Hughes form samples from Africa. OSU (Unfunded E. Taylor Research)
*415 R. Schmitt Radiation Center, Geology, Pakistan Thrust Belt INAA study of major and trace etements in Himala- Joint Radiation S. Hughes OSU yan rocks from the fold-and-thrust bet in Northem Center, Geology, J. Di!!es Pakistan. OSU and NSF R. Lawrence Grant
~~ -
- Projects which utilind the OSTR.
=. _ ~ . .
l Table VI.C.3 (Continued) , i
-[
i
.Projech ; Department and . .
i
. Number : User (s) Name : Institution' Project Title ' Descriptron . Funding Agency .
i 422 S. Kaattari Microbiciogy, OSU Fish Lymphoctye irradiation irradiation of fish fymphocytes in the #Co irradiator. Microbiology, OSU M. Arkoosh
- *427 J. White .U.S. Bureau of Mines-Afbany Nitride inclusions in Titanium Development of INAA and neutron <adiographic U.S. Bureau of. f Alloys techniques to detect nitride inclusions in titanium Menes-Albany - i alloys.
I i '428 R. Schmitt Chemistry OSU Meteorites iNAA of meteorite samples. NASA ! Y -G. Liu ! i !
'443 J. Gardner Physics,' OSU ' 8'Hf Angular Correlation Perturbed angular correlation measurements of Physics, OSU ,
S.-S, Lin Expenment condensed matter.
*444 R. Duncan Oceanography, OSU **Ar "Ar Dating Production of 3'Ar from 8'K to measure radiometric Oceanography, C. McOwee ages on basaltic rocks from oceart basins. OSU i D. Desanie _
*445 R. Schrmtt Geology / Chemistry, OSU INAA of Meteorite Materiats- Determination of chemicai mposition for purposec NASA A. Schilk (Mokoial of genetic modelling/ trace element behavior,
'452 R. Schmitt , Chemistry. OSU NAA of Sediment Samples Determination of Al content in selected sediment NASA Y.-G. Liu samples from the Pacific Ocean.
.479 D. Livesay CH2M-Hill Liquid Scintillation Countmg LSC counting of samotes for gross a and B. CH 2M-H4t!
(LSC) i 480 A. Johnson Raciation Center, OSU RC Technical Support to Technical support to the state of Oregon to assist in Radiation Center, ! 8.Dodd Oregon DOE and Depart. emergeczy preparedness for the PGE. TROJAN OSU ; J. Higginbotham ment of Human Resources factlity. - 481 L. Winans Oregon Health Sciences Cahbration of Radiation Survey instrument cabbration for the Oregon Health Oregon Hea'th University , St . ?y Instruments Sciences University. Sciences University 482 1 Fox Vottum Institute. Oregon Calibration of Radiation Survey instrument ubbration foc the Vollum insti- Vollum lastitute Health Sciences University Survey Instruments tute for Advanced Biomedical Research. 488 G. Little Radiation Safety Office, CSU Cahbration of Portable Cahbration of portable radiation survey instruments Radiation Center, ' Survey instruments for radiation users on OSU campus. OSU t
- Projects which utilized the OSTR.
u,
i I. Table VI.C.3 (Continued) $ !
- Project. .
' Department and Number . ' User (s) Name Institution . Project Title . Description Funding Agency :
489 N. Goevelinger ' Oregon State Health Division, Cahbration of Radiation Calibration of portable radiation survey instruments Radiation Control Radiation Control Section Control Section Portable for Oregon Radiation Control Section.. Section, OSHD Survey Instruments
506 J. Gardner Physics, OSU Use of Angular Correlation investigation of microscopic structures and defect Physics. OSU H.Su in Studies of Zirconia and dynamics of Zirconia and ets a!!oys by potential K. Fuchs Zirconia Alloys angular correlation technscues.
*515 M. Pen ner Food Science and Passage of Food Compo- INAA of rat feces to assess the rate of passage of Food Science and B. Luick Technology, OSU nents Through the GI Tract Co and Cr labetted food substances through the GI Technology, Radia-of a Rat tract. tion Center, OSU 519 B. Livingstone USEPA--Corvattis Instrument Cahbration Cahbration of EPA portable rad.ation survey meters. USEPA--Corva!!is >
J. Gite P. Monaco
*S21 J. Vance Geological Science, University Fission Track Studies Therm: , cotumn irradiation of rircon and other Uruversity of of Washington samples to induce fission tracks in catcher foils for Washington, Dept, dating. of Geological Science
'533 R Collier Oceanogr phy. OSU Sediments and Crust INAA for trace elements in Crater L^ke sediments Oceanography, R. Conard Materials from Crater Lake and crust materials. OSU 535 B.Nash U.S. Bureau of Mines--Albany instrument Cabbration Calibration of Bureau of Minet portable radiation U.S. Bureau of survey meters. Mines-Albany Research Center
*541 8. Collier Marine Geology, Trace Elements in Sediment INAA for trace elements in southern Oregon Coast Oceanography, i B. Conard Oceanography. OSU Cores from Southem Oregon sediment cores. OSU Coast
'544 B. Tansy NEA, Inc. . Reactor Irradiation of irradiation of sediments and filter papers fonowed NEA, Inc.
Samples for INAA by shipment or on-site analysis, as appropriate. 547 B.Boese EPA. Newport Survey Instrument Cat.bration of GM and other portable survey meters. USEPA Calibration
- Projects which utilized the OSTR.
~ . - -
Table VI.C.3 (Continued) Project ' .
.. Department and L Number > User (s) Name - . Institution Project Title Description . Ft nding Agency-
*S48 R. Schmitt - Chemistry, Radiation Center, Major and Trace Element INAA of very smail lunar glass samples. NASA Y.-G.Liu OSU Study of Lunar Votcanic Glasses 353 P. Bottomlev Microbiology, OSU - Rhizobium Ecology . Sod sterilization via
- Co irradiation. Microbiology, OSU -
K. Leung 554 B, Robison r Oregon Department of Energy' instrument Cahbrati cn for instrument cabbration of survey meters for PUC Oregon Depart-D. Stewart. Smith
, Oregon Department of truck inspectors.. ment of Energy Energy
'555 C. Bennett intel Corporation Quantification of Trace Ouantificatbn of tract. amounts of P in the presence Intel Corporation Amounts of Pncsphorus in of As in pure s.hcon semiconductors.
Silicon Semiconductor Materials
*557 R. Walker Radiation Center, Nationat ' ASTM Task Groop's Biologi- Standardization of peach and tppie leaves for use Radiation Center, D. Becker institute of Standards and cal Material Quakty as standard reference materiais. OSU Techno!ogy Assurance intercompanson
'558 W. Loveland Chemistry, OSU Vial Certification Test screwtop vials for use in the OSU TRIGA Radiation Center, reactor. OSU
*563 D. Mdler Rensselaer Polytechnic Thermal History of Sedimen- Analysis of U content of apatite snd zircon for use USDOE (Reactor M. Roden Institute . tary Basins in fission track age determinations. Use Share)
*S64 C. Hull Geological Sciences, Petrochemistry of Feeder Determination of feeder dikes for the Picture Gorge USDOE { Reactor University of Oregon Dikes for the Picture Gorge basalt by use of trace element characterization. Use Share)
Basalts, Oregon
'571 C. Skinner Anthropology, University of Geochemical Characteriza- Use of abundances of trace elements in obssdian USDOE { Reactor Owc + tion and Correlation of artifacts as fingerprints to determine the source Use Share)
Geologic and Archaeological locations and identify tradirig routes. Obsidian from Western
' Oregon f
- Projects which uti!ized the OSTR. $
k
.a
, - _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ . ~ . . . . . . . . .
s 1 Table VI.C.3 (Continued) f 1 . .
'+
j . Project : Department and 1
]
t Number . : User (s) Name 1 ?nstitution - Project Title Description [ Fund %g AQency < l '573 J. Schieber Geology, University of Geochernistry of Shaies Determination of source terranes, fractionaten of USDOE (Reactor . 1 Texas-Arhngton from the Westem and elements during transport, and vanations m Use Shatef Central Bett Basin; Mor.tana - weathering intensity of the Proterozoic Bett 'I Supergroup, Montana..
- l
- l. *574 J. ScNeber Geology, Un'versity i of - A' Geochemical Survey of Determination of tectonic settire and igneous USDOE iReactor l R. Schmerold Texas-A,rlington Proterozoic Metasediments environment of; volcanic rocks One the source areas Use Share) and Metavolcanics from of the sedimentary rocats to ebridate early crustal l, Central EtNopia history of East African craton.
'575 P. Muetter Geology, Un versity of Florida Madison Range Archean investigation of Archean rocks from the Madison USDOE (Reactor
[ J. Murphy Rocks from Southem Range to determine if they are an ancient analog of . t Use Share) *
- E. Weyand Montana . a modern convergent plate margin.
+
*576 K. Hoemie Geology, University of ; Geochemistry of Basalts on Deve!opment of petrogenetic models for the Gran USDOE (Reactor ' lf G. Tilton Cahfomia. Santa Barbara Gran Canaria, Canary Islands Canaria picrite-thoteiite through mefititite suite, to Use Share) i H. Schmincke determine if batch or fractional melting models are ; more appropriate.
'584 A. Johnson Radiation Center, OSU Radiation Center Tours Tours of the Radiation Center and TEIGA reactor for USDOE (Reactor various non-OSU academic groups on an as- Use Share) [
requested basis. i i
*585 S. Lewis ' Geology, Montana College of Correlation of Precambrian Establishment of geochemical criteha for the USDOE (Reactor M, Bartholomew Mineral Science and Crystalline Massifs in the comparison of Precambrian crystathne massifs that Use Share) '
Technology Appa!achian Mountains, underhe metamorchic and plutonic rocks of the ; Eastem United States AppalacNan origin.
*586 S. Hughes Chemistry, Montana College Petrology and Geochemistry Evaluation of the petrogenesis of magma types USDOE (Reactor l of Mineral Science and of Columbia River Basalt associated with CRS feeder dikes, to study the Use Share)
Technology Feeder Dikes in tectonic relations of early CRB eruptions in eastem -[ Eastem Oregon . Oregon, and to gain '.tnowledge of feeder dike inter- '} action with the country rock through wNch they erupted. ' i i
- Projects whic's utilized the OSTRc ,
t
, Table VI.C.3 (Continued)'
' l4 Project t
- t
..... ;. Department and - '
... n .
. Number ; User (s) Name'
- Institution = . Project Title' . Descrintion " Funding' Agency ;
. *588 J. Steiner Earth and Planetary Sciences, REE Characteristics of the' Mapping of the various magmatic puises of the Pali USDOE (Reactor ;
, City College of City University Paksades Magma Pulses, sades hill using REE content, to identif y the initial Use Share) ] of New York ' New York and New Jersey - chemical signature of the pulses, and to estabhsh
. chemical variations resulting from internal ditferenti-
) ation following emplacement. >
'592 A. Glazner Geology, University of North ' Geochemistry, Isotopic Use of trace element data to constrain models for USDOE (Reactor -
g J. Mille 4 Carolina' Composition, and Age of the Mesozoic tectonic evolution and possible source - Use Share) Mesozoic Plutonic Rocks in rocks for Cenozoic magmatism of the southwestem the Westem and Central United States. Mojave Desert [ 593 N. Kerkvliet Veterinary Medicine, OSU Behavior of Fifier Cells for irradiation of filler cells in
- Co facihty. Vetennary .
T-Enzymes Medicine, OSU 596 G. Davies Oregon Health Sciences i Gamma Ray irradiation of Collagen irradiated to a gamma dose of 2.5 Mr&Js. Oregon Health - .i J. Bentley University : , Dned Protein (Collagen) Sciences Uriversity l;
'599 A. Robinson ' Nuclear Engineering, OSU; i Study of instrumentation Familiarization with reactor operation and concepts.' Intemational !
R. Abdur International Atomic Energy and Control Related to a Atomic Energy ' + Agency Research Reactor Agency f t
'600 8, Patrick Geoscience, New Mexico Fission Track Dating of Irradiati'm of zircons and apatites in thermal co8umn New Mexico Tech. .;
Tech. Geological Samp!es - for age dating of geologic samples. I 602 M. Bloomfie!d Private citizen '-Text review, advicc, consul- Review of the radiological portions of the text for Radiation Center, [
,tation by Dr. Dodd the fif th edstion of " Chemistry and the Living Organ-- OSU ism
- by Bloomfield. ,
'605 A Mathis Geosciences; OSU Age, Stratigraphy, a wf i
- Use of geochemical data, especiaffy trace elements, Radiation Center, i A. Grunder Pe'trogenesis of Volcanic to determine the age, stratigraphy, arid plausible OSU (Unfur.ded i Focks from Hart Mountain, petrogenetic models for Bastn and Range volcan.c Research) [
$outheastem Oregon rocks from Hart Mountain, southeastem Oregon. i
[ R , t
- Projects which utilized the OSTR.
f tO i t 1
#- r , - - ,,- 4 . , ,,.. , y .- -,.p-,,
a S , k Table VI.C.3 (Continued) O Project -
- Department dnd " -l
'I Number. - User (s) Name . : Institution . ?
Project Title . Description x : Fundmg Agency
*606 F Sutherland Australian Museum, Trace Element Characteriza- Determination of the range of trace e!ement con- Radstion Center, ^
i R. Walker Radiation Center, OSU tion of Australian Gem tents of the various groups of zircons from Austraria OSU (Unfunded Quality Zircons to provide important information conceming zircon Research) i crystallization and sources.
~
*609 R. Fodor Marine, Earth and Atmo- .. Petrology of Tertiary Basalt ' Anatysis of trace element contents of xenoliths and USDOE { Reactor A. Sial spheric Sciences, North and Ultramafic Xenoliths and megacrysts to determine mantie heterogeneity Use Share!' ,
G. Gandbok Caroiina State Univ. Megacrysts: Mantle Charac- beneath northern Brazit and of basaits to distinguish teristics Beneath Northern between continental and oceanic magmatL;m. i Braril-
*610 P. DeCelles ' . Geological Sciences, Middle Tertiary Sedimenta- Anaty.is of trace element contents of sandstones USDOE (Reactor. !
K. Ridgway Uriversity of Rochester tion in Strike-Stip Easins and conglomerates that fill smaii basins along the Use Share) Along the Denali rault, Denali f ault in Yukon Terntory to correlate with l Yukon Territory, Canada nearby source areas and establish provenance.
*611 D. Smith Geology Trinitit Petrologic and Geoca.emical Determination of trace element contents to con- USDOE (Reactor.
P. Pearce U.iiversity Characteristics of Creta- strain possible petrogenetic processes such as crys- Use Share) [ ceous Hypabyssalintrusions tal fractionation or magma mixing. in Central Montana and -[ t Precambrian Granitoids from Central Texas ,
*612 F. Beardsley Anthropology, University of Easter tsland Obsidian Stud- Determination of trace element contents of USDOE (Reactor ?
W. Ayres Oregon ies: Research on Source obsidians from Easter island to estab!ish source Use Share) G. Goles Variability and Artifact Dis- areas and trading routes of artifacts. ' tribution ; i
*613 V. Sisson Geology and Geophysics, Trace Dement Mode!Iing of Determination of trace element contents of different USDOE (Reactor '
S. Olsen Rice University; Johns . Open and Closed System types of migmatite to establish charactenstics of Use Share) I C. Closmann Hopkins University; University Migmatites movement for va<ious elements during formation. ! of California-Santa Cruz
'616 J. Gardner Physics, OSU High Pressure Perturbed teradiation of ZrO2 to assess properties under high Physics, OSU ,
L Dundon : Angular Correlation (PAC) pressure using perturbed angular correlation !
, [ techniques. '
1
- Projects which utilized the OSTR. :
i
,, , . . - - . , m _ _________J
__ _ __ _ _ _ = ; ' .t t r l-Table VI.C.3 (Continued) s 4
- Project .
Departs wit and ' . Number . User (s) Name - institution P Titie - Descriptm Furfarva Agency
*618 K_ Mcdonald AN ,rd Chemistry. MB FeasMty Study-4NAA Development of a fast 89d CosttffectNe INAA Ra&ation Center,. ,
i Research Measurement of low procedtne for measureme tt of Cne m wood CSU [ cornaining VJaod satpes.
' Pre ~ <ative
*620 FL Schm:tt Chemistry, OSU; Geo cgy. INAA o( Standard Lurur irrat3 ton of len g' ass) stardard lunar samples for NASA, Ursve'sity j, L Tayk>r Universrty of Tennessee Samples subsem.ent IWUL af Ter.nessee l., 622 W. Chism Private citrien "Co irradiaton of Wood Gamma strad:aten of sood saWes to % used in Ra6aton Center, j W -s v%n bndges. OSU nJn;onded j
Researchl i i - l A. Klein
'625 Nuclear Engmeermg, OSU Cold Fusian Ceu Resdoes Chemcat ident ficaton of meta %c res . ~ found m Rad.aton Center. l cold fuuon ce!!s forlowng expenmental furt OSU (Unfunded
- Research)
*623 G. Harper - Gealogical Scences. State Ocearwc Faufung and Hydro- Dete<menaten of trace eiemant geoctemastry to USCOE (Reactur Urwversity of New York thermat Met. rnarpNst-i of defne the roles of magma etumbee *frearrf, Use Share) the JosepNne Oph.ohte, are extensene faultmg, and perode fav. eeupton in its Pelation to Frac *cnation the formaton of JosepNne opher#te. Kiameth l ;n D.kes and Lavas fAvitaens, Ca4fortua.
~
} . i '629 C. Shearer . Inst. for the Study of Mmeral Petrogenetc Relatons lovestgaton of the ro'e of spatict'y associated igne- USDOE (Reactor Deposits South Daketa [
- l. C. Patterson Betweer; Gold Mene+ahrate ous intrussons w'th sed.rrentary Scste6 epithermai use Share) l j E. Fntch Schoot of Menes and and P;neous intrusions in the goid moerahration en the B;ack Heis South Dakota. t
? Technology Black Hdfs, Sot.,ch Daketa
~
l ! 632 R. Thompson Oregon State Pohce Radoton Survey inst ument sabbraton of portable radiation survey instruments. Oregon State i Cahbrat on for Oregen Sate Pohce, Crime
- Ponce Cnme Laboratory Laboratory b i I l '634 S. Bersey Nuclear Engineering, OSU Production of Madcal Determinatior of producten rates ard unknown ce Nuckar E'rgere I j S.Tumer Radoisotopes poorly 8 mown cross secticns for rahsetopes of eng. OSU f j medcal eter-st. ,
1 l
- Protects wNch udhred the OSTFL 4
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)
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- m. W
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- w. a i C gc iv nl n n su io ne e n e gea 4.
. ud t l e v c S nin t
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p mtae d o a r f s ad eactes i r ec e t a ot y sg vi t n mt c a le r ena e e e s e %m e s t s . o s. d mr t wh t c a- Cve yr 'a D e c. N C n d ee sy ai mv Awt io u cm loc c ir te o nt t d a n a 6- h et e be barta a f e nf oo ear ca ar a sor '? nc - s cog rWt t t t _ r m ge ou t ded v
- ur b f s o
f is t o pa ae nce e eb i ogi o o pM nd eo aral n nda k aa nd d ma a oen Nf s Rl n a inor t en d he to oeP er ct n f o o f foto t ad f t go t r wte in oe t o
- a. t i
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+d 6 aWt f ci n o6 r -
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. r b n ur r.
pntt r 3 le l e p sTn Sn t g e o ka E n Ch e pt nt d ia s l a bca nrr t g e deni a s it m' e oat n f ozoo en r n eI t s f oo r C. I
. T a in c r hssH$a t o r h.
t e t o e o rMnn t s n- O obi inn V. x f la t t T t c E orr a a aC ebuA e
- e. e nem t d oGt i d i
i vl ufun M m r t a vl t n - o"a e lb j s nf sy a o haod sote eSe a o md ooeluR a r aodt e B e n hu r s t r h s v f T P n e t a ess it i et n use c it s iv n e et - mcoge ea'n n b n t n b n Da oS g inpa e ebn ca e as a r eb r Gs t es t spCm oam g ogmi v< om Te r r w ogmi ek r a i cem areo r e s v e na n o a ie o us vt r e dip ah gw glo f t o i vi vt ou e r s _ OP TCf r InRiG o C I n dt ehn o RS EF S i n dt ehn o l ' f - o y t r s so r c d n' U e es an ; S c n nvrc S' O e r n . 4 - U ic Ua r t S O' . w.,e u r S ;F t O , a U U . t i y ' n S Sn e s n s h p e tt O U c Oa e C a S e ,S e I c a r e y y O s t y a- , n n D e g Ht c d e r ci - i o' o s 2 a s e O anr c n r c t e S G mo s o e a e c d a a s ws- ~. h m r a isy h n u G rf al h a i G O R 0U P P S E PC R T S . O e m e m a h a h r t
.N t
o e r u d r e sr r b ys ,
.?s a rdr n ee e n o dr iz
( r ss eu ea ig lt i v s e o se dr n e m st eii a ti s e t d a b n loo ig n a e yeove r a w y e ry -eil
+
u y DK CC BD APM i M A H *W,
.U H G S h
. . . . . . . . c
'R B IA J JG JEJ . J R R JAR N
w _ r s _ ce t eb 5 9 0 2 4 7 8 9 0 t c jm 3 3 4 4 4 4 4 4 5 e . o j 6 6 6 6 E 6 6 6 6 o - PN r I P r i: j:1;!I!' jj+ ' i ; ' }:" liIlj;4[;1,iiI); 4 ;j* ii. ? 5 ' i,
L' Table V! C.3 (Cent nwd) ! Pro.tect f ' Department and Numt.er User (s) Name inststution ProrT Thie !
*651 Descr+cten R. Comer Marine Geology, OSU Funding A;c ry V. Kulm ' B!ack Sands Ocearngraphy. OSU INAA cf beach, rwes arvj contmentai shdf sands B. Conard [ Ocemp aphy.
f frorr Northern Cahfomia aN 0 egon fer co<re' awn OSU l of sou<ces to deposit sees. !
'*652 D. Walsh Urwversity of Alaska. M narai ;
Placer Gold Irradiatiom Industry Research Lab Producion of *Au by irrManon cf pfacer gdd Uruvers:ty cf _ sa rT l es a -d shomen* cf wra%ted samples to A:aska 653 i Un' vers:tv of Ataska. A. Torres I Food Science and F. Almonacid f Technob3cy, OSU M+crebta' Stabarate o' h Effect of temperature abuse on the sN!? Me of FAnced F:sh Seafood I processed shnrop sea' cod. Radia*en Cr-ater. OSU (U-f Wef 654 A. Torres Rosr : cm Food Science and C. Kantt Techno;ocy, OSU M:crobta! Stab >faatw3n of Shnmp S+afood ' Eff ect of terrperature apose on ttw sNtf 1,fe of Fr pf Sc *<w;e and
*655 processed shrop seafood.
W. Ayres Techrwegv. OSU Anthrcoology. Un.wersity of Elemental Compos:t,on or R. Mauncio Oregon Chemmai charactenza!>on of pr6stanc btridmg Stone Bueng Matana! from An hroprbgy. Nan Madol Nhnpei is'and. matenal from Nan M3 doi archaeo;ng<af site Pc% Unversey of Merenessa Is;and to deterrnrre the provenonce of tM stona. O egen 656 f D. Harlan Radiation Safety. OSU R. Farmer Racaten Proteton of OSU Ouantitative gamma anaiysrs of o<w f?ter pap *< Research Pe<sennel and Ra+a w Cer cr. Research Labo<atenes sw$e for co-femacon c? "en concertt<atrn- OSU
*657 R. Wa"a er Rada!>cn Center, H Corbelf a A:kal.ne Volcanic and intro-Geosciences. OSU sive Igneous Rocks from Dev&oment of retrogenanc modeis based or' trace element concentratons en samp;es of a^kene volca- Rawaten Cen*er.
Terra del Ft*go. Argen9na OSU (Unf;nded rk and intruvve ignaeus rods from t** Sea ~a de ResearcN Orcsrwyeu. Sera de los Chacays, a'vf Ser a de , Somuncura. Tera de Fuage. Argryt,na. I
*658 S. R; dosevich ;
Anthropology, U<wvers-ty of D,etary Constra:r*s Based O<egon Deterrruna +on of Sr. Ba, Zn contect cf benes from on Trace Elemer t Centent, USDCE fReacto< an Exam !e from Harappa tv Ha appa s4te te estafAsh cocelatons w t$ eet. UseShre)
'659 l C. Richardson Strattor P!atoen Group M* tats rn Magnat:tes and Er emes Determ naton of as many p!atorn g oup me als en S tra *mr l
samcias of mantce a~f Mm*e as is feastle useg standarc it.AA tectnews.
- Pro;ec+s which ut8aed the OSTR.
r PJ (J
s h Tabte Vt C.3 (Con muedi F;nd:nq Agency Department and Descnction Project
- Progct Twe inst:tution USDOE iReactx Number User (s) Name Use of trace elemem contents of roca ucrts Use to deln-Sh. vel Nature of Carchna Tenane A. Dennis Physical Sciences, University Basement. South Appata- eate an accreted istand arc within the southern
'660 of South Carobna-Aten Appalachan piedmont.
D. Secor, Jr. chan Pe:dmont Fcd,aten Cen*er, J. She"vais Gamma ray spectroscopy of foodstuffs canrwd OSU in situ Measurement of Oregon Health D* vision, be* ween 1930 and iSSO. 661 M. Debblee Radeonuclide Content of Ra&ation Control Saction, J. Higginbotham Canned Pacec Northwest Ra&ation Center. CSU Foodstuffs. 1930-1960 -- RaCainn Camer. Petrogenett mode %nc and detenmnaten of parti- OSU (Uch.okd Eiemental Charactentaten Geologear Sciences. of M;nerai Separates and t on coeffic>ar ts fe" bama6c and mafe rocks from Research)
- '662 L Taylor Unrvers ty of Tennessee TaNit.
" Y. Jin Bdk Rocks Ra6acomi Ce -tar. Text reve for tachn*cai accuracy and chora ses- CSU f Consuttrno and Photog <aphy son of typ+ cat GMs and dos 2 mete <s for bek reve Pr,vate cstiran ) f'03 M. Bloo. **1d sr t Raca!*cn Camar. l _ inst *ument Cahbraten, R@- Cabbrtion cf ra6aton survev enstru rents. OSU t Good Samantan Hospital, atson Survey Instruments 664 M. Wrrght RaCaton Center.
} Spec:af imaging 1
r CaFbraten of rasaton survey estrumems. OSU Instrument Ca ib atron. Rade Corvanis Frre Depar*. ment 665 J. Kennedy ation Survey instruments USDOE (Reactor Petrogenate meenog of p<oarade a -cNtehtel Use Sha'el Geology Montana Conege of Charactenzation of g<an Ate-f actes metamc.phsm and retrograde
*666 M. Bartholomaw Lovingston Massif Rock. greenschist-faces metamorphism using t. ace eie-S. Hughes M<nera! Science and Technology ment data..
USDOE (ne acto-Petrogenetc modcEng cf P.ocene to Holocam Use Share) Andean Volcanism magmas tnat gave r se to ca:deras aM porey*y Geological Sciences.
*667 C. Stem A. Skewes Urnversity of Colorado coccer mmrabraico en the Andes of cent *al CNe.
USDOE meacto-Petrogemi c r cdeft ng of Mecene and Pecene Use Sharel Ongen of Miocene and Pho-J. Longshore Geology, Humbo!dt State andesrtes and basa'is to determina their tactX
*668 cene Andestics arvi Essais settog and rnode of orvn.
Un=c-srty Near Canby. Modo; Ceu -ty, J. Crum C. Deebler Cahfomia J. Carlson
- Projects wNch utthred tne OSTR.
I Table VLC_3 (Contmued) - L l t t ' L Project .
. Department and i f:
Number User (s) Name institution : Pmect Title Desc*iptson FundN Agency
*669 D. Miller Geology, Rensselaer Thermal History ;f Analys2s of U content of apatite and zircon for use USDOE Beat. tor :
M. Roden Polytechrsc Institute Sed.mentary Basins in fissen track age determ'natons. Use Sharr) C Ravenhurst ! R. Dor ebck !
'670 ~ l A. Basu Gaolog<al Sciences. Petrogerests of the Sebenan Characteruaton of t5e detferent mantie reservoirs USDOE (Reactor M. Sharra . University of Rochester Flood Basalts. USSR responsible fof the ongm of the Permo-Tnasse Use Share)
G. Nisterer*o Sebenan fkvad basatts.
*671 G. Harper - Geolowcal Sciences. State Geocherrustry of D*kes and Charactentation and constract of the sources of USDOE (Reactor Universrty of New York Ses intruded Dunng the Em- d kes that mtruded the Jose:hne ochnoiate approxi- Use Share) placement of the Josechene rnately t0 mahon years fe nowing the empfa,,ement i Oph.obte. Cshforrwa of 1% och ohte. I
*672 J.1%Iano Geologtcal Sciences. State Geochemcat Constraints on Determmaten of the sour e for Palactore sfonstones USDOE { Reactor V. Bruechert Urworsity of New York the Ongin of Paleozo.c to assess whethat they are dragerec or latent < in Use Sharei !
T. Schuster l fronstones origen.
*673 K. Hoemie Geology, Uruversity of Haterogeneity in the latho- Petrogenetc modeFeng using trace element and USDOE meactor G. Taton Cahfomia-Santa Barbara sphere-Asthenosphenc *sotcpic abundances of rocks tnat fym the Use Sharel H. Schmincke Mantle Beneath the Canary I-thosphere-ast5enosphe'e bourwfa y beneath the ,
and Madeva Island G*oups Cana<y and Madevra Istarvos. [
*674 P. Weigand Geolog, cal Sciences. Origin of Miocene Volcarwc Petrogenetic modeiteg of M ocene volcar=cs from USDOE meactor Cahforrma State Urvvarsity- Rocks from the Los Angeles Catahna Is!ancf. Cahfomia to dete m'ne the source Use Share) i Northndge . Area. Cahforrwa of these rocks which have unus;.;aUy low i aburtjances of REE. !
i
*675 R. Wamer Earth Sciences. Clemson Geochemistry of Mesozo.c Petroganctic modeihng of Masozoic age debase USDOE (Reactor I Urwcrsity Drabase in South Ca*o1*na d;kes from the South Caroica Pevdmont. Us* Share) .I I
'676 A. Johnson Radotion Center. OSU Radtation Center Tours Tours of the Radoton Center and TRIGA reactor for USDOEtReactor [
various norWSU academ,c croups en an as- Use Sha el requested basis. i l. l
- Projects which utihred 3 ' OSTR. < -
h I cr ! I* k! ..
I Tabte VI C.3 tContinued) Project Dwartment and Institution Protect Titie y Descnption funceu A pery Number User (s) Name USDOE (Reactor !
'677 E. Sanchez ! Geology. Tulane Urvversity Geology and Petrologw of Petrogenetic modemng of the basait-trachyte-S. Nelson Socorro Island. Revmag geo camei: ente sete of Socorro tstand to detmeate Usa Share)
Arcfvpe'ago, Mewico rnagmatt sources ar'd processes. Geochemistry of the Petrcgeneoc modemrg of the Jurassic age Eng'rsh USOCE (Peactor
*679 C. Barnes Geescences Texas Tech. 7 B. Schmidt Ureve sity pos:te Erv. bsh Peak Pt. ,
Peak pk:tm cf the Klamath Moun*atns CaWrrma. Use Share) Mama *h Maumains, Cantort a
*679 T. Lehman Geosciences. Texas Tech. Ekmer:tal Destneutson en Geochemical charactenraten of seds that scan tre USDOEtReactor Uneversity Buned Scds (Paleosots! extincrm cf the 6nosaurs. Use Share}
Scannmg the Cretaceous /
.Te-tra y Found. , a Texas R. Knaus Nuclear Science Cemar, Wet!ards 5%udy iNAA of sampies for Dy and Sm wh*ch es used as USDOE (Reactor
'680 Lovesiana State Urvversity honton ma kers. Usa Share)
*681 P. Muener Geology. Uruve<sity of Ronda Gaochemstry of Precarmbn- Petrogeretc r ocenng of the meta **d:memary USDCE (Reactor K. D'Arcy an Metamorphac Rocks of rocks found in southwestem Mentana o Use Share}
L. Horne the Montana Metasede understand the na+ure of the crust. mentary Te<rane
'682 C. Skrnrer Anthropology, Urwversity e s Preh storic Obsecian Geoc5emrcat charac+cniaton cf obs> dan sources USDOE meactor Oregon Prodarement en Westam and a tfincts en westem Oregon to estabesh t ade Use Share)
Oregon rou*es and uterat on.
*683 J. Davidson Earth and Space Sciences, Characionration of Igneous Petrochemical modemog of vt9canec rocks assoct- USDOE (Reac or Use 55a e} f D. Barr Urwvers:ty of Cantom a-Los Rocks from the Lenestone ated weh the older subducdon rone of tM Lassar N. Bognossian Angeles Caribees: St. Maa< ten and Anves.
St. Bartholomew, Lesser j Antites
*684 D. Smrth Geo;ogy, Tnnety Urwversity Ongin of the Enchanted Petrogenede medenmg et tne Precambren Encham- USDOE Peactor Rock Bat 5ohth. Uano Upft, ed Pvxk bathoM5 to dete-mine its origins. Use Sharel Cemra: Texas
- Projects which utdized the USTR.
t a r Table VLC_3 (Contrnved) I I I Project Departmer t and ,. , Number . User (s) Name Institution Project Trtle Descnotion Fundirq Agency l
'685- V. Sisson Geo8ogy and Geophysics, Element MobItty Related to GevC+6.o! characterizaten of granuhtes to trace USDOE (Reactor [
i L Baker Ree University Partial Metting and CO2 - tre movement of elements durmg metamorphrsm. Use Share) l M. Santosh Streaming in Granulites from i i Southwest Norway and [ j Southem India t i l j *686 A. Burchell Geosciences. Uraversity of Volcano-Stratgraohy and Gi+J+..-.at charactenraten of rhyokte votarmes to USDOE (Reactor i P.Damon. Anzona Petrogenesis of the Mrd- constram the st<atrgraphy and develop petrogeretc Use Sha e) 4 W. Dickinson Tertiary Galiuro Volcarscs, models. l ! Southem Arizona [ t
- . *687- V. Langer Geosciences, OSU Structure and Geochemistry Dewkywi of petrogenete models usrng trace Racat on Center. l l of the St-ens Mountain element contents of basalts assocnted with the OSU (Unfunded (
Basaft. SE O<egon Steens Mountain secten m SE Oregon. Researchl l j
*688 J. Davidson Earth ard Spece Sciences, Characteritateon of igneous Petrogenetec modelimg of volcarve rocks associated Unrversity of Cati- [
Urvvcrsity of Cafefomia-tos Rocks from the Lancstone with the older subducten tone of the Lesser foerma-Les Angeles Angeles - Caribees: St. Maarten and AntTies. i St. BarthoW. Lesser ! 4' Antit:es I t 689 S. Gutenberger Merobiology, OSU intercellular Studies of Reni- Stentization of cells useg "Co gamma erradraton. Microb ology OSU Bactenum (Sahmoninarum)
- *690 J. Myerr Myers Mecharwcal and Forensic INAA of Lead INAA of Icad shot pellets. Myers Machar= cal f Meta!!urgical, Inc. Peifets and M2tafiurgeaf. I 1 loc. !
+
*691 M. Streck Geosciences, OSU Petrochemcal Interpretation Trace element determ, nation of vancus ash-ficw Radtaten Cen*er.
A. Grunder of the Rattlesnake Ash-Flow unrts within the Rattlesnake tuff to determme OSU (Unfundad Tuff. Southeastem Oregon changes in the composition of the manma chamber. Research] 1 *692 F. Prahl Oceanography, OSU Colombia Estuary protect INAA of Colombia Estuary Samples Oceanog aphy. l M. Sparrow OSU j B. Conard l ! 5 I,
- Projects whech utilized the OSTR.
4 i f 4 N ! (
. . ~ . - . . . . . - . - , . .- . ., .
~
r PJ Table VI.C.3 (Continued) co
- i f
Project - Departrrm and Number User (s) Name - Institution ' Project Titfe Descripton ~ Funding Agency *
,- *693 K. OsteJker, Jr. NCASI Organic Chlorme in Paper INAA of aqueous effluent extracts from Oregon NCASI .
Mell Aqueous Effbents paper mills to assess chionde content. l
*694 T. Ball Geological Sciences. CIRES, Geology and Petrology of Petrogenetic modening of the Precambnan crust USDOE (Reactor i G. Farmer Universrty of Coloraoo the Precambrian Crust ttrough trace eleme st and isotop c characterization Use Share) of metasedarientary and metaigneous rocks from ;
the Cheyenne Belt. Wyomeng [
*695 T. Feeley Earth and Space Sciences, Geology and Petrology of Petrogenetc modefirng of the Quatemary volcanic USDOE (Reactor J. Davidson University of Cahfornia-Los - Oestemary Volcarne Rocks rocks of SW Bohvia. Use Sham) !
, Angeles from the Salon De Vyvrn Region. Southwest Bolivia
*696 R. Fodor Marine, Earth, and Atmo- Petrogenesis of Gabbro aruf Petrogenetre modefieg of the crust undertying (MDOE (Reactor ,
P. Galar spheric Sceences, North Ultrathafic XerViths from Hawan. Use Share) ' Carolena State University Mauna Kea Volcaro, Hawas .i i .; *697 G. Langstaf f Geology and Geological GecGe rdcal Characterha- Detee- ton of trace element contents of USDOE (Reactor [ i G. Holden Engineering, Colorado School tuon of Archean Felse metamorphovd and weathered Archean rocks to Use Share! 4 of Mines Igneous Rocks in the Graratt estabksh regional correlatbns. ! Mountains, Wyom'ng ) I 4 f
*698 J. Schieber Geok>gy, University of Irwestigaten of Trace Use of trace element signatures to determine USDOE (Reaccur Texas-Arkngton [
] Element GesG+2try of regn>nal stratgraphy and ccfretatio t Use Share) s
- Proterozoic Sediments from i
! Idaho and Washington l l '699 M. Dyar Gcologica! Sciences. Effects of Mantle Determenaten of the effects of metasomatism on USDCE (Reactor i 1 M. Harren Unrversity of Oregon Metasomatism on Pendotite vanous types of mantie reno!iths and t5e,r Use Share) ! , Menerals constituent rNnerats. ! . *700 W. Leeman Geology and Geophysics, Epithermal Neutron Actin- Use of trace e8ement abundances that are analyti- USDOE (Reactor ) Rece Ursversity tion of Basalt Samples frem cally ere_d by epethermal actrvaten to charac- Use Sharel ;
- Vclcanic Arcs terize sedrmenta y input into subducte related j
! magma. - l
- Projects which utihred the OSTR. i J
, , ., -.s -- - s v-- , . - -n. - . ., - --
j jj'I il1 i Ie _ y t y s r, - n sr c r r r - n o o m e e s; t c t c t c a e ev no t n e . m e t n A g a a a c ,r O Ug t e sa u g s u e e) e) C C Red o o "F n a v R( e a l - a me f c y5 . re n e h gi E U h g n o d a Eh Eh E w lo h a s nr r a S n t n OS OS OS o;W t a ti c cO t a F u De S s De S s De S s h a- t U aS s n a icua . s e t U aS UU UU UU cgf Soo RO m 'H N n r W RO een -n g
- o -a t
ta e . d no me #n t o t r p c a r a os cs a n ea s s o mt n c aac t n t.ot r a a sf t
'c te e a r r aP r
o f w e
;e p c f
ca c e h s s a
% f ot c o g oh t yn a u t pr t sf a nraC < mdr a-ss sa i
ne ot O 3 lere a < o o c - e n S e s e y y se C d o 0
- ew r 3 o ud
- r. nt :ebu m0 E
E R toeh s et e ht g Ot Cm AA n pt m n L f e6 p o mr n e cngs oc u o ni Cv au net ao o aP oo crf t e r o v - oc c i s it n o cA s a r: orau = a f t o f a nf dOo 2c v t va ar Oc i a es o oc f t n s v e a f le n n ni n r sg 3 a r f u c s p ute o s of i o t c ei n ur Cri c a oo gd e e m b a ;g o t as . At aatt 2 r gh g nt . D a al e r es a e . r. nr n - s t s i d s t e nh R b
+md nu o Co r s y t i e sa l& et a b
a a r t f o o ra r r r 2 cge S st es t sa a r cg mgn g r i n ag t uevAG Snn qe ,ha F t e dn -refo r na n un e dW o ieeiM ur h c r i mqk u e c i Nt R oI sT B de c "F f o" n a eh at r t ue pp ic ed a t la f ony t nt . r e e g ct n loc a cab t n c t r o b r n )s of m 'e m e f t a neSa r F f n t r n e uf n - v omt r o r. r t i t oe t t mob pc o o f oevhe m oo i-ta mgs e md ur o t n t r a. uc i u t t ans ccy o !et A Asu r i nk r p a d md &x O bo+cg s leb s A e so t Ar t h enc e a t s gl v ad n r ao o" ae v ao e nc
)
d NI Umfo Nn I i Tt at r Inne os I r cc r P + F s ne Det i e u e n yt - i w n g t n o tr sc h
,ba r mp t
t o i T I t o i i sC a C o C( mhp f okc . e ae r e u nU o heOa soe h la oC C n 3 e cen r nR o cn t n Fodeh v c r o ei n i C lt i ogo e f o s e n ot f E m t a T enf ic v p s F r nu i t r I a ni e t r n n u e e V t c Gah c ar ot r mei e Sl p ' T b h ie e d R aC bpl cP t t n u. ca v f g a nra x f oma o C t b a ot r nt s a a nr moa Vn a aI zd nr aT on en lo S n n o d T P y oe I ea r e nS oe L o gCh lo e n ceM nn i t a cg UaAco f s g n o t g t c 0 Rm oh oN oea a a r r e oa et r w r an u 0 R a r r t ct conn 4 aa eat s a mt ac i d 6t Tg t t ef eiar h k s r aie le r u o pes S or P oi n TMSfo CS UfeWP t C i r d P r AT OP ht u o ,n t s U U U
~
S r yo e S S S d e h t n f o t pg U w O O O a n , s .n an S ht . . . y s e s e o g r i gh O r g g g tnio t eh o s o n n n eu t s i ccno c nre na r N n i r n mt r e a e e e e e t t i v eR o eO i c eW t n ci e n e n n r s i f f cf e f an n So So Ooy ic g i i g i g pi U C ay n n n e . layt lay f n Pr E E E D y a ci ct i ot o o o r r r gn is gr is gr lore t i leta a a a oh oe loev o v a le r o e e e lorc o n lc lcu i l loiv h i d t t b c ea en er cn a a a u u GC GU GU SU R BL N N N R T S O e m e m a h a h d t N s nan y n n t u d s e o o r e t e n o s b c e
)
s aaa i c a sr lles r s
+ y en s g z a
( vmkg r fe mleB i sr ed n. u ne e na d g ea o r e Cle s e dd g e ne y d u t u s eo oc um noig e hU on SB eZ h Si GM ADH G r RAA DS t < U . DC RE BG h
. . . . . . . c JGA. . . . . . . .
JJM PR AS TBJ M. SJ JHA BR h w r s t t c be 1 2 3 4 5 6 7 3 9 c e 0 0 0 0 0 0 0 0 0 ej ojm 7 7 7 7 7 7 7 7 7 o r u * * ' ' ' ' *
- r PN P llliI fl llIl if1 1
4
. Table VI.C.3 (Continued) $
Project . Department and Number User (s) Name Institution Prow Title - Descnotion Finding Agency l *710 S. Binney Nuclear Erg;reia 9. OSU Measurement of Ta impun- Determ nation of Ta impunty levels (ppm) in V Nuclear Engmeer-i tes in V samples by standard INAA. - ing, OSU a }. 711 D. Mattson Vetennary Medscine, CSU Diagnostic Bso'gy Stenfirate of serum in "Co irradetor. Vete< mary , Medicme. OSU 4 712 J. Entry Forest Science, OSU Herbicide Degradaten by Radictracer research utilizing "C. Forest Science, 3 P. Donneiy Fungi OSU 713 D. Parsons Pnvate citizen Cobalt-60 Irradiaton of Irradiation of various gemstones to prescnbed levels D. Parsons Gemstones in 'SCO irradiator to induce color charges. 4,
'714 L Neaty U.S. Geological Survey, Determination of Partrtion Use of partition coefficients to determ.ne petro- Radstion Cente".
) R. Watker Denver, Colorado. Coefficients Usmg INAA genetic modeis for volca'uc rocks from north central OSU (Unrunded } Geoscences. OSU Anzona. Research)
*715 J. Steiner City College of New York: Continuing Geochemical Investgatog gLucf.en.; cal charges through Rad.ation Center, j R. Wafker Radiaten Center. OSU Charactenzation of the Pa!a. magmatic diffe entiaton and crystal fractionation in OSU (Unfunded sades Sill, New York and war.ous parts of the Palisades Sen. Research)
. New Jerse)
*716 R. Wilen Anthropology, University of Cornpositonal Anatysis of Deterr wnation of differences in source area of pre- USDOE (Reactor Oregon Ceramics from the Huay Sai fustoric ceramics by estabt.sfung trace ekment Use Share)
Khao Basin, Nc6theast signatures thro gh mu8 tie!ement analysis. l Thailand
*717 B. Nelson Geolog. cal Sciences. Earty Crustal History of the INAA of g*arvtes from Eastem France. USDOE (Reactor j tirwversity of Washington Massif Central of Eastem Use Share)
France
'718 C. Shearer Instrtute of Meteontes, History of 4_ong Valley INAA of geoiogic samples to assess the trace USDOE (Reauer J. Papike Universsty of New Mexico Magma System element character of intrusive and extrusive ursts. Use Share) 719 J. Morrell Forest Products. OSU Host Preference of Damp- Stentitation of 2400 cm3of wood samples with Forest Products, M. Mankowski Entomology, OSU wood Termites on Western "Co garrma irradiation. OSU
- Wood Species I
i Prt " cs which utilized the OSTR. i
l :
,hil; .t I!I!l f }f[ .fJI ,iIIh[ ,EriI ii!h i <
e
$w *' '
y U m U , r _ r S S r t o
- O U e - y O y ed -
e S f o h' t
< g y mad N g s C C ar y h
t r A A e u pe g p s r Cu en f oS c y a i'a U en o a e yA 9 n e t r e r uS DE lo r g v i nfnh
)
tt N 6 s u no f n o n oUrca s _ uO ft 4, ic r B se o t o n U t ( a r ee s m c ny. gt aU e e _ uvm n r F t o e h e . n gt r i e r e c i e cS c di Us aSe r a - G C S. U M As e Om M OO R ROR UD e k r e s ht . c o m c in e i u s. a oo - f f m n n q s r t r sro r n e y d f sen i pf n Z o ei a n d _ r c a n Ns s u o t e r u Nc un se r a. s k c t a a _ a p r ng a ft o r m r o erc t a d a a r f o ere o i a s a sufor a r a v r s m 4 m l e r t t e t sel e g b o r d i y u d o f o ee e e n f o r a C nt g t h a b s. n t s . s r n i. o uc d g " s s f t e o - i w s e e t f nt ooic e c it o' n clo h y oo t e laA t r a a n oo t i nN e nut oli s r t d i r pd w n aA os d ss a
- c. tin o 6
ip a s a nteais. t d r r d i, IN an C r i e n t 4o he se + y C ' i o yr u i s t sgt t ' b y o r fac a s s s ib mlet a r l e p enn e. NC ns t s a es s er n v emin
- t.
- F Z
r o a eg - h y ia lekc d tei r u eo m. at _ i
- f or is eo sn la Yio t f
o f w t la f n a cr aC
;t
. hM r e .
ces o t o se +d nya at no no f . r ih i mt ha n o n oR f o imto ni b t i t d p N walaa c enr i s e edu b n ro e t h ee cen t a r . tiT cS s
%n s t t as a
r a m in eam f t cn aR uO y eo - i r owm r e pT d la vp t c! A oa etsH ci 4e Am t eef t eS r oe n es a r i r a A y t ae ak e r ah e
) Pb o PO' Ptr h A Dre ivr N I Mm TPt Nl e I
d e o n - r s t r a o t n . n r f e n d - h sn r C o a r e a d y n n n s sy ec mso i p g d a nls c a n u ( nna r o o nn d a er er aI n i 3 le ok i STO Ma n L C. I T it i ov MtgNe
$ n f e nk r oie it c
u d-r o dege r r ae inm nt si aa oc snk s t oa.t cegs a f o e V n . d N pm s ee nt aR lI f k i e t c e amt ee t aB o r C e r E t mht a nCc d a d f o sYt rs ra ce niu n oP . P s tb f o ds ede o r j a o i s pny r P ycla e adN Mnp as nm P _ T P r e ei nhD e r rer o c e s in r i e ogs d u mS e S ar coo la et P wta a' su ono B&e' f o gt i r t s osm oacs ne t gne r r eo t S h f oip e a or r T h p al r o es t t s Ala a loik t ep l r t eoo nc cL aCa - b Z r nm t oip bd s S B cema arooo Ast e tr pc l mma PiCt r TUL '
' SC yo LRR aae l E
r TCf C r Na I BM PiR emo le ES L U e f o t r S ic y a O U R' ti d S , S , s n , y O s r e s r c a 'n e n t s g U isy Gr t o ni t U' e e n U S h U U . e u SO M m S O i r p S mt U h e e e O , o G , S f h s ot a i t t r s , C nr , y e e an s O uU g y h p G s ce pI e a la n g e n em e c y , r o a &y c n r ey u E r g n e a D e t r t r lo yi t e c ic i s BC ui lt u a ib o n gr s c
> SD
. s ml e c e o a loe s h er lcl r oi v o
. i' e e
,o! r t t e h S. ka g u e c en e ar o
G~ C UL A N M 'O GU G EN R T S O e m' e
.m ht a h a d e t
N n e o c n c d e
) a ue b e se dr a n r
.s n k v r ed
( r 's le v dr iom k a igAd k t n o a nt h e m e r a la hs
.e le o a ar gae ah oo e wm e t
u
.s e h o MLa li Lah e
L L N U D . B HBL i SR CC .
.A h
c J W R. BJ JSJ CJ BR W RI. C N w . r s ce t jeb 0 1 2 3 4 5 6 7 8 9 t c e 2 2 2 2' 2 2 2 2 2 2 j o m 7' 7 7 7 7 7' 7 7 7 7 o r u * ' * ' ' * * ' ' r PN P
' , ,+1!I: ,j: !ii a
I Tab!e VI.C.3 (Contir sed) a Project 1 ' Department and , Number User (s) Name - Institution . Protect Title Deschnion ' Ftnf.no Agency
*730 D. McCreery Anthropology, Wit:amette Trace Bement Analyses of Search for trace element pattems tfvm;gh time m USDOE (Reactor University Ancent Linseeds from lenseeds (ftax) collected from the Test Enre site in 'Jse Share)
Jordon the Jordon Valley. i 732 E. Smith - Poultry Science, OSU X-Irradiation Induced Chro- X-ray irradetson of turkey semen. Pouitry Science, mosomal Mutations in OSU Turkeys
'733 J Brosing Pacific University Gamma Dese Rate Measure- Measurement of gamma dose rates in t e core Pacifc Urwves.ty G. Wollan ment in a 250 kW Research *eg+on of a 250 kW research reactor usirg RDs.
Reactor 734 J. Higgmbotham Nuclear Engineenng. OSU Ouantifcation of " SriY Cc.c%e,1 of a beta particle wis..cter to Nuclear Engmeer-S.-H. Baik Contamination Using Beta measure "Sr!*'Y actnnty in the presence of a mixed ing OSU Pa tcle Spectroscopy beta particle / gamma ray radiation field. 1 735 G. Davies Oreoon Health Sciences Collagen irradiat.on Research and development of co: tag-n for bum OHSU, Ba;f emis-J. Bentley Universsty Biocty;mistry treatment. try 736 L Gordon Oceanographi, OSU Gamma-ray Sterikration of Gamma <ay stentizaten of standa d reference Oceanography. Seawater Nutnent Standards matenals for intertaooratory cormpansons. OSU
*737 W. Leeman Geology and Geopnysics, Trace Dement Characterita. Petrologic study of primetnre oceanic arc basaits Pxe University Rce Uruverssty tion of Pnmitive Oceanic Arc that are thought to have low continental Basatts from the Sandwich sedementary input.
1 istands
'738 V Sisson Geology and Geophysics, Dement Mobitsty Related to GM-,.ca; cha'acterization of granuistes to trace Ree Urwersity L Baker Race Crwversity Partial Metting and COr the movement of elements during metamorphism.
M. Santosh - Streaming in Granur ites from Sot.thwest Norway and Southem lodia
*739 J. MacLean Geosciences. OSU Practcal Application of Completion of a standard sequentra! mstrumer tat Radsaton Center, K. Weise INAA to Geologic Materials neutron activation anatysis protect in freu of a OSU (Urdunded 2
taboratory associated with Chem stry 576. Research) y Projects which utilized the OSTR. 1 i _ .. ._ m . _
i Tabie VI.C.3 (Contmued)
. . , - i, Project ~ Department and -
Wumber User (s) Name institution - Project T;t'e' - Description Fundmg Agency 740 A. McBirney Geologcal Sciences. Investigation of Trace Determ.naton of regional rA local petrologsc Departmere. of G. Goles University of Oregon Element Geochemistry of ' changes in Cascade volcarwc rocks through the use Geological Scienc-C:scade Volcan c Rocks of trace element signatures. es. Uruversity of Oregon 741 W. Loveland Chemistry. OSU Target Fragmentaten in Low Gamma spectroscopy analysis of varon targets Chemistry OSU Energy, Intermediate Energy, *rradiated at accelerator facilities throughout t+e Relativistic End Ultra Relatrv- world. istic Nuclear Cottisions 742 J. Horstman Joumaiesm, OSU Joumahsm 390-Reportmg- Accomparument of the Reactor Ope'ator durmg Radiation Cemer, S. McCannett Class Project startup and shutdown checks of the OSTR OSU i
743 L Taylor Geologcri Science, University Mantle Xenoliths from East. INAA of eastem China mantle menosith samples. Department of I of Tennessee em China Geo!opcal Scm.
Ur.nrersity of Tennessee
*744 L Taytor Geological Science, Univesty Compositional of Hunganan USDOE tBeactor of Termessee Crustal and Mantie Igneous Determeate crustal and mantieof ditferences in the rocks from sites geoc*emrstry in Hur gary. of ' Use Share)
Rocks a 745 T. Clarke Urwversity Hospital. Oregon Gamma Stenfiration I radiation of varous med cmais to OHSU-speed ed Radaten Center. Health Sciences Unive<sity doses in "Co readiator for the purpose of sterdira- OSU
.. ton.
746 57. McBee McBee and Associates. Effects of H gh Doses of irradiation of concrete samp!es in "Co erradetor and McBee and Gamma Radiaton Upon performance of post *radiaton studes of Associates Sulfur Polymer Concrete concrete's strength. l t 747 B. McBee McBee and Associates Estrnate of Gamma shield- Measurement of the reducten in gamma miensity -Bee and ing Propertes of Sulfur as a function of the tfwckress of sulfur pofymer A a zates ! Polymer Corcrete concrete.
*748 D. Rosenberg U.S.D.A., Fishenes and Mrgratton and Predator loss Production of d'Ta in the OSTR in sma!! wire Fishenes and Wdd-Wildlife, OSU of Salamanders segments for imclantaten mto satamandars. Efe. OSU L
f
- Projects which utifired the OSTR. < {
O !
I 1. Table VI.C.3 (Continued) I j ; Project ' Department and l j Number User (s) Name Institution Project Tatie Desenption Fteding Agency l '749- R. Donetick Houston, Texas Fission Track Analysis irradiaten of samples in the therrnal column for R. Donet.ck subsequent fission track analysis. 750 S. Nordmark Food Science and Utilizaten of Acid Wtvey as ' "Co irradiation to sterdize whey and cenulase Food Soence, OSU
- j. Technology OSU a Substrate for the Prodt;> suostrates.
tion of Food Grade l Cenutases 4 '751 B. Albertson Medone/Endoennology, Pituitary Tumor Therapy irradiaten of tissue sar:v,Jes cwd sy % Oregon Heafth l S. Martsoif Oregon Health Science Using Boron Neutron compounds to enhance ce# killsng m B-loaded ce r!s. Soences University University Capture Therapy 3 j 752 D. Bames Beochemrstry, OSU Schistosoma Cell Cultur=e irradiaten of feeder layer with "Co irradiator. Bochemrstry, OSU C. Rawson ! 753 P. Whanger Agneuttural Chemistry, OSU . Chemacal Analysis of Goat trradiation of goat liner tissue for stenfiratwi. Agncultural
- C. Chen Tissue from Eastem Chermstry, OSU J. Deagen Germar'y
! 754 J. Franko Oregon Department of Er ergy Radiation Center Library Short-term loan of ICRU 39, ICRU 45 and ICRP 51 Radiaten Center, ! Loan and Technical Assis- to aid n extemal dose assessme it. Also, research OSU tance on *H Production en acceerator use in 8H productiori. i 755 J. Griffiths Intemational Education, OSU Short Presentation on Presentaten of information to students p&i;cv.12v Radiaten Center. l *Chenobyl and Radiation
- in the Kiev exchange program about poss.bie health OS'J risks associated with Irving rear Kier 1
756 M. Craig Veterinary Med~ cine OSU Bacterial Incubation with incubaton of bact-ria in "C-labened TNT w th Vetennary S. Smith "C-Trinitratofuene (analysrs md separation! of .netabolic products by Medone, OSU D. Wachentem HPLC or TLC and LSC. D. Bilich 757 P. McFadden Beochemistry/ Biophysics OSU Mutagenesis of Zebr. Fish "Co irradiation of frsh eggs. Food Science, OSU f.*. riartman Embryos i Projects which utilized the OSTR. i
Table M43 (Contmued) ' 1. Project . . Department and '
- Number User (s) Narre Institution ' Protect Tde Descnot e Funding Agency n.
[ 76') M. Johnson U.S. Erwironmental Protection Neutron Doses Around a Estimaton, measurement and s%-st-3. of piotec. Rad.aten Center, Agency. Corvaihs - Controlled &rcronment trve : tens to mirwmeze neutron doses from a sovi OSU !. Chamber moisture gauge used in a Cont.oped L r.is...ent j' C hrc h er. 1
- '761 D. Pnncehouse Geoscences. OSU Petrogenesis of the PetrMe--O defation of the Yen-41.A. pluton by G-+scs As. OSU Yemngton Pluton erarrnnaten of the most evdved stock.
i i 5 i-i. i i t i I 4 1-4 4 i
- Projects which utiF ed the OSTR. I b
Ut m
i VI 30
- 1. Neutron Activation Analysis ,
Noutron activation analysis (NAA) stands at the forefront of techniques for tho quantitativo multi clomont analysis of major, minor, trace and rare olomonts. The ! principle involved in NAA consists of first irradiating a sample with neutrons in a ; nuclear reactor such as the OSTR to produco specific radionuclidos. After the ! irradiation, the characteristic gamma rays omitted by the decaying radionuclidos are quantitatively measured by suitable semiconductor radiation detectors, and tho gamma rays detected at a particular energy are usually indicative of a specific ! radionuclido's prosonce. Data reduction of gamma ray spectra by means of a : computer then y! olds the concentrations of various olomonts in samplos being , studied. With soquentialinstrumental NAA it is possible to measuro quantitatively about 35 olomonts in small samplos (5 to 100 mg), and for t'ctivatablo olomonts, the lower limit of detection is on the order of parts por million, or parts por billion doponding on tho element. The Radiation Contor's NAA lahoratory has analyzed for the major, minor, and trace element contant in many thousands of samples covering essentially the completo spectrum of material types and involving virtually overy scientific and technical field. While some rosearchers perform their own samplo counting on their own or on Radiation Contor equipment, the Radiation Contor providos a completo N A A service for researchers and others who may require it. This includes samplo preparation, sequential irradiation and counting, and data reduction and analysis. Data on NAA research and service performed during this reporting period are r included in Table VI.C.3. e L l l
VI37
- 2. Egressic studies Neutron activation analysis can also be advantageously used in critninal investigations. The principio underlying such application usually involves matching troco niement profiles in objects or substances by NAA. This in turn can help l identify materials or products (e.g., identify the manuf acturer of a given object), :
t and in somo casos can match bullets and other materials recovered from a victim i to similar materials obtained from suspects. Mbtorials which h6vo boon analyzed =i by the Radiation Con'or Ior forensic purposes includo bullots, metals, paint, fusos, coats, glass, meat, and salts. j Forensic studios performed in this reporting period are included in the listings in ! Tables VI.C.1 and VI.C.3. 1 I
- 3. Irradiations As described throughout this report, a major capability of the Radiation Contor j involves the irradiation of a largo variety of substances with X+ rays, gamma rays
{ and neutrons. Detailed data on those irradiations and their uso during this reporting period are includod in Part lll as well as in section C of this part. 4, _Radioloalcal Emeroency Resoonso Servicca - The Radiation Contor has an omorgency response team capablo of responding to all types of radiological accidents. This team directly supports the City of Corvallis ! and Benton County emergoney responso o.ganizations and medical facilities. In ! addition, most members of the team have been cortified as Regional Radiologl cal Technical Assistants (RRTAs). As a result, these individuals are authorized to provida assistance at the scono of any radiologicalincident anywhere in the state ; of. Oregon on behalf of the Oregon Radiation Control Section and the Oregon j Department of Energy. ' The Radiation Center maintains dedicated stocks of radiological emergency . response equipment and instrumentation. These items are located at the Radiation i_ Contor, at the Good Samaritan hospital, and in the Linn/Benton Region 5 hazmat vehicle.
VI38 During the current ieporting period, the Radiation Centor emergoncy response team conducted several training sessions and exercises, and responded to ono rninor
;ocident. This involved a child playin0 w;th a plastic container marked " Caution Radioactivo Material." It was determined that the containor was empty and not
, contaminated. A report of this incident was submitted to the Oregon Stato Health Division, in conjunction with the OSU Department of Nuclear Engineering, Raciation Center stafI provido on-Doing support to the stato of Oregon's emor0cncy responso plan for the Trojan Nuclear Power Plant. About seven persons residing in the Radiation Conter hold either primary, second shif t or alternato positions in the Trojan Emergency Plan, and would work in the Emergency Operations Center in Salem, or in the Erner0ency Operations Facil;1y at Trojan in the ovent of an incident. During the past year, Radiation Contor personnel attended training sessions, participated in dri!!s and oxorcisos, and provided advico ,olating to omergency responso to a Trojan incident, but no ono was required to respond to e real Trojan emergency.
- 5. Trainina and IDilW.tti 2.0 in addition to the acadernic laboratory classos and coursos discussed in Parts Ill.A.2, Ill.E and VI.B. and in adaition to the routine training nooded to meet the requirements of the OSTR emergency responso plan, physical security plan and operator roqualification program, the Radiation Center is also used for spo?ial training programs. Radiation Center staf f are well experienced in conductin0 these special programs, and re0ularly offer traiain0 in areas such as research reactor operations, research reactor mana0cment, research reactor radiation protection, radiological emor0cncy responso, reactor behavior (for nuclear power plant operators), neutron activation analysis, nuclear chemistry and nuclear safety analysis.
Special training programs generally fall into one of several categories: visit!'10 faculty and research scientists; international Atomic Energy Agency (IAEA) fellows: special shortqorm coursos: or individual reactor operator or healtn physics
VI 39 training pro 0 rams. During this reporting period there were six visitin0 scientists and special traineos. Three visiting scientists,000 each f rom Japan, Sweden, and India, worked in tho field of nuclear chemistry under the direction of Dr. Loveland. A visiting associato professor from Portland Community Collo00 worked extensively on neutron activation analysis with the Radiation Conter's goochemist this past year. Finally, two high school students were mentoted by nuclear engineering faculty during this reporting period. Two special oro week long training opportunities woro provided at the Radiation Centor during the summer. One was a workshop for high school scienco and social science teachers entitk.d *Radioactivo Wasto: Technical and Socialissues." The other was the ongoin0 Regional Radiological Technical Assistant's summer school, which in 1990 was in its fif th year. G. Smjintion Proten. tion Servicn The primary purpose of the radiation protection pro 0 ram at the Radiation Contor is to support the instruction and research conducted at the Center. However, due to the high quality of the program and the lovel of expertise and equipment available, the Radiation Centor is also able to provide health physics services in support of the OSU Radiation Safety Offico and to assist other stato and federal a0encies. The Radiation Contor does not compoto with privato industry, but supplies health physics services which are not readily availablo elsewhero. In the caso vi support provided to stato a0encies, this definitely helps to optimiro the utilization of state resources. Tho Radiation Contor is capable o6 oroviding health physics services in any of tho arcas which are discussed in Part V. Those include personnel rnonitoring, nadiation surveys, scaled source leak testing, packaging and shipment of radioactivo materials, calibration and repair of radiation monitoring instruments (discussed in detailin Section VI.C.7), radioactive wasto disposal, radioactive material hood flow surveys and radiation safety analysis and audits. During this reporting period, the Radiation Contor began to provide services and technical support as a backup radiation laboratory to the Oregon State Health
VI40 Division (OSHD) laboratory in the ovent of a radiological omorgency within the stato of Oregon. In this rolo, the Radiation Conter will provido gamma ray spectroscopy analysis of water, soil, milk, food products, vogotation, and air samples collected by OSHD radiological responso field teams. As part of thc ongoing preparation for this omorgency support the Radiation Contor participates in inter laboratory drills and cross calibrations each year. In the current reporting period, the Radiation Contor hoolth physics program supported the OSU Radiation Safety Of fica by poriotming gamma cpoetroscopy on a number of charcoal filters and paper smears to identif y possible airborno or suriaco contamination, by assisting the of fice with equipment and instrumentation noods, and by perinrming instrument calibrations for a number of organizations.
- 7. fladiological Instivment RCRaiLADiCD l ibtation While repair of nuclear instrumentation is a practical necessity, routino calibration of thoso instruments is a licensing and rogulatory requiremont which must be mut.
As a result, the Radiation Contor oporatos a radiation instrument repair and calibration f acility which can accommodato a wide variety of equipment. The Contor's scientific instrument repair facility porforms maintenance and repair on all types of radiation detection and other nuclear instrumentation. Since the Radiation Conter's own programs regularly utilize a wide rango of nuclear instruments, components for most common repairs are of ten on hand and repair time is therefore minimized, in addition to the instrument repair capability, the Radiation Contor has a f acility for calibrating essentially all types of radiation monitoring instruments. This includes typical portablo monitoring instrumentation for the dotection and measuromont of alpha, beta, gamma and neutron radiation, as well as instruments designed for low lovol onvironmental monitoring. Highor rango instruments f or uso is radiation accident situations can also be calibrated in most casos. Instrument calibrations are porf ormed using radiation sources cortified by the Nationalinstitute of Standards and Technology (NIST) or traceable to NIST.
VI41 1 Tablo VI.C.4 is a summary of the instruments which were calibrated in support of the Radiation Center's instructional and research programs during this reporting period, wailo Tablo VI.C 5 shows instruments calibrated for other OSU departments and non-OSU agencies.
- 8. CDnE!!1011QD Radiation Contor stafI ate able to provido consultation services in any of the areas discussed in this annual report, but in particular: research reactor operations and use, radiation protection, neutron activation analysis, neutron radiography, radiological omergency responso and radiotracer methods.
Records are not normally kept of such consultations as they of ten take the form of tolophone conversations with researchers encountering problems or planning the design of experiments. Many f aculty members housed in the Radiation Center have on going consulting functions with various agencies,in addition to sitting on numerous committees in advisory capacities. l h M
l VI42 Tablo VI.C.4 Summary of the Types of Radiolo0 i cal Instrumentation Calibrated to Support the OSU TRIGA Reactor and the Radiation Centor Type of instrumont Number of Calibrations Radiation Contor Instruments GM Detectors 85 lon Chambers 32 Alpha Detectors 4 Noutron Detectors 6 Micro R Meters 6 Mini Detectors 35 Civil Defonse Detectors 26 Personnel lon Chambers 104 Support Agency Instruments Corvallis Fire Department 4 Good Samaritan Hospital 5 (Corvallis, OR) TOTAL 30/
Vl43 Tablo VI.C.5 Summary of Radiological in.*.rumentation Calib'ated to Support Otho! "SU Departments and Other Agencies Department / Agency Number of Calibrations OSU Departnio.its Agricultural Chemistry 4 Animal Sciences 3 Biologi::al Chemistry G Botany 4 Crop Science 1 Entomology 1 Fisheries and Wildlife 2 Forest Science 1 Horticulturo 1 Microbiology 1 Oceanography 3 Physics 5 Radiation Safety Offico 7 Voterinary Medicino 2 Zoology 1 Non-OSU Agencies U.S. Department of Agriculture, Agriculture Research Service 3 U.S. Environmental Protection Agency 2 Oregon Department of Transportation, Highway Division 6 Oregon Health Sciences University 5 Oregon Pub'ic Utilities Commission 6 Oregon State Health Division 4 Oregon State Police Crime Lab 1 TOTAL 69
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I Vll-1 l j PART Vil WORDS A. Eub!!g.glions in Print
' Anthony, E.Y. end ten othors (W .,,
- Examples of modern rif t volcanism and Proterozoic anorogenic magmatism: The Potrillo Volcanic Field of southern New Mexico and the Franklin Mountains of West Texas " Field Guide to Geologic Excursions in New Mexico and Adjacent Areas of Texas and Colorado, Now Mexico Bureau of Mines and Mineral Resources Bulletin 137, p.1-3.
"Bartholomew, M.J., S.E. Lewis, S.S. Hughes R.L. Badger and A.K. Sinha (1991),
" Tectonic history of the Blue Ridge basement and its cover, central Virginia "
Goologic Evolution of the Ere*~rn United States, Fieldguido for the NE-SE GSA Mooting, p. 67 90; Virginia ~.Teum of Natural History Fieldguide No. 2. Martinsburg, Virginia, p. 304. Binnoy, S.E. (September 1990), " Nuclear ~ 'tadiation Physics," Courso Lecturo Notes f or NE 231. OSU-NE-9014, Oregon uto University, Cor' 91!.3, Oregon. Binney, S.E. (January 1991), " Nuclear and Radiation Physics," Courst Lecturo Notes for NE 232, OSU-NE-9103, Oregon State University, Corvallis, Oregon. Binney, S.E. (1990), " Multiple Decaying Source Method for the Determination of the Dead Timo of a Delayed Neut.on Counting System," Nuclear /nstruments and Methods in Physics Research, A292:643-647.
'Binney, S.E. (September 1990), " Capabilities for P.oduction of Medical Radioisotopos in the Oregon Stato TRIGA Reactor," Oregon State University, Department of Nuclear Engineering Report OSU-NE-MED 9001, Corvallis, OR,11 pp. ;
Binney, S.E., H.R. Brager, W.W. Schultz, et al. (1990), " CURE: Clean Use of Reactor Energy," USDOE Report WHC-EP-0268,189 pp.
- Binnoy, S.E., S.A. Turner, R.J. Walker, R.E.Schonter and D.J. Jordheim (1990),
" Production of '88W/'88Re in a Research Reactor," Oregon State Unviersity, Department of Nuclear Engineering Report OSU-NE MED-9003, Corvallis, OR,34 pp.
'Binnoy, S.E., R.J. Walker and J.D. Leidtko (1990), " Analysis of '8"W/'88Ro from MiP Test," Oregon State University, Department of Nuclear Engineering Report OSU-NE-MED.9004, Corvallis, OR, 9 pp.
'Binney, S.E., S.A. Turner and D.P. Jordheim (1990), " Calculation of the Neutron Flux in the OSTR CLICIT Facility," Oregon State University, Department of Nuclear l Engineering Report OSU-NE-MED-9005, Corvallis, OR,17 pp. l
- Indicates OSTR use.
Vil-2 l Binnoy, S.E., J.C. Ringle and M.F. Roardon (1990), " Nuclear Wasto Glossary: A l Layperson's Guido to Technical Terms," Oregon State University, Department of Nuclear Engincoring Report OSU NE-9016, Corvallis, OR,11 pp. Binney, S.E. and L.Y. Arnaut (1990), "Radioactivo Wasto Transport Bibliography," Oregon Stato University, Department of Nuclear Engineering Roport OSU NE 9019, Corvallis, OR,39 pp. Binnoy, S.E., B. Dodd and J.C. Ringle (1991), "The Oregon HLW Transport Public Information and involvement Program," Trans. American Nuclear Society,63:357-358. Binnoy, S.E., D.P. Jordheim and R.E. Schenter (1991), "A Computer Codo for Calculating Pu 238 Production, Quality, and Irnpurity," Trans. American Nuclear Soc.'ety, 63:423 424. Binnoy, S.E., L.L. Carter and T.L. Milos (1991), " Quantifying the Reliability of Uncertainty Predictions in Monto Carlo Reactor Physics Calculations," USDOE Report WHC-Sk1OS9 FP,46 pp. Binnoy, S.E. and R.G. Most - (1991), " Summary Responso of Key individuals about the Transport of Radioactivo Westo from Hanford through Oregon: A Pro Survey," Oregon Stato University, Department of Nuclear Engincoring Report OSU NE 9101, Corvallis, OR,38 pp.
*Binney, S.E. and R.J. Walker (1991), "Measuromont of Long lived impurities in Vanadium," Oregon State University, Department of Nuclear Engineering Report OSU NE-A1ED-9101, Corvallis, OR.10 pp.
'Binnty, S.E., R.J. Walker and J.R. Green (1991), " Production of "F in 'i Research Reactor," Oregon State University, Department of Nuclear Enginer ; 1 Report OSU-NE-A1ED 9102 Corvaliis. OR,9 gp.
Binnoy, S.E., M.L. Blazok, J.E. Franco, R.W. Robison and B. Dodd (February 1991),
"Public Concerns about Radioactive Wasto Transport in Orogon," Proceedings of the Symposium on Waste Afanagement, Tucson, Arizona, Volume i, pp. 359 364.
Binnoy, S.E., M.L. Blarek, J.E. Franco, R.W. Robison, W.J. Sanderson, D.A. Stewart-Smith and B. Dodd (April 1991), "The Oregon Experiment: Public information and involvement," Proceedings, International High Lovel Radioactive Wasto Management Conference, Las Vegas, Nevada, pp. 741-747,
'Burchell, A. (1991), "Mid-Tertiary Volcano Stratigraphy and Petrogenesis of the Galivro Mountains, Southern Arizono," University of Arizona Gooscience Colloquium Abstracts with Programs.
' indicates OSTR uso.
Vil 3
'Cerveny ill., P.F., R.J. Dorsey and B.A. Burns, "Apatito and Zircon Fission Track A0es from the Sierra San Pedro Martir Eastern Peninsular Range, Baja California, Mexico," ADstracts with Programs, G.S.A. Cordilleran Section, San Francisco, California. ,
'Cox, L.J., B. Houser. E. Force, A. BurchcII, M. Gettings and F. Fisher (1991), "Goologic Map of the Sierrita Mogollon Corridor (AZ NM) and implications for Mineral Resources
- U.S.G.S. Research on h1ineralHesources 1991 Soventh Annual V.E.
McKelvoy Forum !!.S.G.S. Circular 1902.
'D'Arcy, K., G. Murphy, d. Mueller and D. Mogk (1990), " Age and composition of the Cherry Creek metosupractustal suite of SW Montana: Evidorco for an ancient soutco,* Geol. Soc. Amer. Abs , p. t 74.
'DeBari, S.Y. and N.H. Sleep (1991), "High-Mg, low Al bulk comp'osition uf the Talkeetna island are: Implications for primary magmas and the nature of arc crust," Geol. Soc. Amer. Bu//.. v.103, pp. 37 47.
'Delarso, J.W., Y.-G. Liu and R.A. Schmitt (1991), *Goochemistry of Apollo 17 impact Gl asses: regolith compositions, Lunar & Planet. Sc/. XX//, pp. 309 310.
Dodd, B. (1990), "Safo Transport of Radioactivo Material," editor, international Atomic Energy Agency, Training Courso Series No.1, IAEA-TCS-1, Vienna.
'Dodd, B. (1990), " Teaching and Training Applications of the OSU TRIGA Reactor,"
Proceedings, American Nuclear Society Topical Mootina, The Safety Status and Future of Non Commercial Reactors and irradiation Facilities, Boise, Idaho. Dodd, B. (1990), "The Validity of Population Dose and Cancer Risk Coef ficients in the Determination of Latent Cancer Fatalities," The Health Physics SocietyNows/etter, XVill(4):8-9.
'Donolick, R.A. (1991), " Crystallographic orientation dependence of mean etchable fission track length in apatit0: An empitical model and experimental observations,"
American Afineralogist, v. 76, pp. 83 91.
"Donelick, R.A. and J.R. Dickie (1990), " Low-Temperaturo Thormal History of the Coast Plutonic Complex and intermontano Belt, Northwest British Columbia," Gcologica/
fieldwork 1990, Paper 1991-1, pp.139-144.
'Dorsey, R.J. and B A. Burns, "Toctonic Implications of Lower to Middle Miocene Sedimentary and Volcanic Rocks in Northern Baja California, Mexico," Abstracts with Programs, G.S.A. Cordillerari Section, San Francisco, California.
'Eckert, J.O., L.A. Taylor, C.R. Neal, R.A. Schmitt,'Y.-G. Liu and A.D. Patchen (1991),
"Cumulato lithologies and molt rocks from Apollo 17 breccias: Correlation of whole-rock and mineral chemistry," Lunar & Planetary Science XX//, Lunar and Planetary Institute, Houston, pp. 333 334.
- Indicates OSTR use.
M
Vll 4 I l 'Elliott, W.C., J.L. Aror' son, M.K. Roden and D.S. Miller (1990), "The formation of illito in the Appalachian Basin: A test of the fluid expulsion hypothesis," Geol. Soc. America, Abstracts witis Programs,22, p. A62.
'Golos, G.G. (1990), "A strontium lotopic study of Newberry volcano... " J.
Volcanology and Geothermal Res., 43, pp.159174.
'Grunder, A.L. (19911. "High temperaturo hydrothormal circulation during middle tertisry magmatism in eastern Nevada," Geological Soc 4ty of America. Abstracts with Programs, 22:22.
'Hoatherington, A. and P. Mueller (1990), "Mosozoic igneous suites in the Florida bosomont: Implications for mantio sources and tectonic reconstructions," Geol.
Soc. Amer. Abs., p.162.
'Hoatherington, A.L and P.A. Mueller (1991), "Goochemical evidence f or Triassic rif ting in southwo* om Florida," Tectonophysics 188:291 302.
Higginbotham, J.F. and G.G. Simons (1990), *Bota Particle Spectroscopy with Activo Gamma-Ray Discrimination," Nuclear instruments and Afethods, A293:551-554. Higginbotham, J.F. (November 1990), "Rosponso Characteristics of Modified CDV 700 Radiation Survoy Instruments. Final Report," Oregon State University, Department of Nuclear Engincoring Report OSU NE-9017, Corvallis, OR,18 pp.
'Higginbotham, J.F. (June 1991), " Refurbishment of tbo Oregon Stato University Rotating Rack," Transactions of the American Nuclear Society, 63:25 26.
'Hoornia, K.A. and G. Tilton (1991), "Sr, Nd and Pb isotopo data for Fuertoventura (Canary Islands) basal complex and subaerial volcanics: applications to magma genesis and evolution " Schweiz. Afineral. Petrogr. Afitt.,71:5 21.
'Hoernte, K.A. and H.U. Schmincke, "The St Nd Pb isotopic evolution of Gran Canaria magma sources over thn past 15 Myr: evidence for onriched oceanic lithospheric mantle,* Earth and Planenary Science letters, in press.
'Hoernio, K.A. and H.U. Schmincke, "The major and trace olomont geochemistry of the tholeiito-melilito nephelinite basalts on Gran Canaria, Canary Islands: Crystal fractionation, accumulation and melting depths " .lournal of Petrology, in press.
'Hoernio, K.A., "The major and troco elomont evolution of Gran Canaria magma sources over the past 15 Myr: An intermittent Canary Island plume?", Journal of Petrology, in press.
'Hoornlo, K.A., G. Tilton and H.U. Schmincke (1990), "The 15 m.y. isotopic evolution of Gran Canaria, Canary Islands,* EOS Trans. Am. Geophys. Union 71, No.
43:1696.
' Indicates OSTR use.
Vil 5 Hughes, S.S. (1990), " Mafic magmatism and ascociated tectonism of the central High Cascade Range, Oregon," J. Geophysical Res. 95, No. 012, pp.1962319638. Klein, A.C., B.R. _ Lewis and R.A. Pawlowski (August 12-17, 1990), " Advanced Thermionic Reactor Systems Design Code," Proceediaps,25th Intersociety Energy Conversion Engineering Conference, Reno, Nevada, Vol. 2, pp. 305 309. Klein, A.C., L.L. Zahm, S.E. Binney, J.N. Reyes, J.F. Higginbotham, A.H. Robinson, M. Daniels and R.B. Peterson (October 22-24,1990), " Anomalous Heat Output from ; Pd Cathodes without Detectable Nuclear Products," Proceedings, Anomalous Nuclear Effects in Deuterium / Solid Systems Workshop, Provo, Utah. Klein, A.C. and A.I.A. Almarshad (October 14-19,1990), "A Semi-Empirical Model for Diffusion of Oxygen in Zirconia," Proceedings, Symposium on High Tamperature Chemistry of the Electrochemical Society, Seattle, Washington. Klein, A.C. and T.S. Marks (January 1991), "An Experimental Approach to Compare Wicking Stabilities of Fabr:c Materials for Heat Pipe Applications," Proceedings, > Eighth Symposium on Space Nuclear Power Systems, Albuquerque, New Mexico, pp. 8694 74. Kleini A.C., B.R x Lewis, R.A. Pawlowski and K.J. Greek (January 1991), " Advanced Thermionic Reactor Systems Design Code," Proceedings, Eighth Symposium on Space Nuclear Power Systoms, Albuquerque, New Mexico, pp. 222 227. Klein, A.C. and T.S. Markc '/anuary 1991), " Material Compatibility issues fnr Fabric Composite Radia ors." F wdings, Eighth Symposium on Space Nuclear Power Systems, Albuquerque, rww Mexico, pp. 320-325. Mein, A.C., H. Al-Baroudi and K.A. Pauley (January 1991), " Experimental Simulation of t5e Bubble Membrane Radiator Using a Rotating Flat Flute," Proceedings, Eighth Symposium on Space Nuclear Power Systems, Albuquerque, New Mexico, pp. 723 727. Klein A.C. and T.W. Eichenberg (September 1990L " Tritium Inventory Tracking and -
!Aanagemend-Final Report," Oregon State University, Department of Nuclear l Engineering Report OSU-NE-SOf f, Corvallis, OR. .
l - Klein, A.C,, R.A. Pawlowski and H.H. Lee (June 1991), " Low Power incore Thermionic
. Space Reactor Design Concepts Using Advanced Technology," Proccadings,
- International Conference on Emerging Nuclear Energy Systems, Muoterey, Ca!!fornia, pp.1011.
Klein, A.C. and S.M. Slater (September 1990), " Limits to Power System Growth--Final Report," Oregon State University, Department of Nuclear Engineering Report OSU-NE-9013 Corvallis, OR.
- Indicates OSTR use.
.n .- ., . - -. - - - - . . . . . . - . .- . . ~
yll.6 l Klein, A.C., B. Beaver, H.A. Al Baroudi, K.J. Greek, B.R, Lewis. T.S. Marks, K.A. Pauley and R.A. Pawlowski (October 1990), " Papers Presented at the 8th Symposium on Space Nuclear Power Systems," Oregon State University, Department of Nuclear Engineering Report OSU-NE-90f S, Corvallis, OR. Klein, A.C. and T.W. Eichenberg (May 1991), " Tritium Inventory Modehng of Potential Tokamak Reactor System Operational Scenarios," Fusion Technology,19(3):1680-1685.
' Knaus, R.M., " Instrumental Neutro U" ation Analysis to Measure Short-Term Accretion and crosion in W. ~ t,. Using Rare Earth Element Soil Horizon Markers,* J. Rau,aanal. Nucl. Chem., in press: Proceedings, International Canference on Activation Analysis andits Applications, in press.
" Knaus, R.M. (1991), "The Application of f-Elements in Ecological Research," European
. Joumal of Solid State Inorganic Chern., 28:379: First Intematio.1 Conference on f-Elements, Program end Abstracts, in press.
'Kowallis, B.J., E.H. Christiansen and A. Deino (1991), " Age of the Brushy Basin Member of the Morrison Formation, Colorado Plateau, western USA: Cretaceous Research," in press.
L
' Lewis, S.E., S.S. Hughesi M.J. Bartholomew and R.J. Walker (1991), " Geochemical Comparison of Representative Plutonic Suites from e Praterozoic (Appalachian Blue Ridge) Magmatic Arc," Geologic Society of America, Ab: tracts with Programs, in press.
' Lewis, S.E. S.S. hughes, M.J. Bartholomew anu P.J. Walker (1991), " Lower Crustal Evolson of Middle Proterozoic rocks i1 the Central Virginia B:ue Ridge during Grenville methamorphism," Goological Society of America, Abstracts with Programs, v. 23, no. 'i, p. 59.
'Mogki D. and P. Mueller (1990), " Evidence for Archean accretionary tectonics in the northern Wyoming Province, SW Montana " Geol. Soc. Amer. Abs., p. 262,
'Mueller, K.A , " Cenozoic Exhumation of the Northern Ruby-East Humboldt Metamorphic Complex, Northeast Nevada: Kinematic, Temporal and Geometric Constraints,"
Abstracts with Programs, G.S.A. National Convention, San Diego, Cahfornia.
'Mueller, P/, J. hofle, A. Heatherington, J. Wooden, D. Mogk and P. Thuiston (1990),
" Origin of Archean Low-grade metasedimentary rocks from the Jardine area, northern Wyoming Prpvince," Geol. Soc. Amer. Abs., p.175.
'Mueller, P.A., D.W. Mogk, K. D'Arcy, A. Heatherington, J. Hofle, J. Murphy, P.
Thurston and J. Wooden (1990), " Crustal evolution in .the Montana metasedimentary terrane," Taylor Colloquium (Origin and Evolution of Planetary Crusts) Abs., p. 23.
' iridicates OSTR use.
i Vil 7
- Mueller, P. A. and J.L. Wooden (1990), "Archean crust-mantle evolution of the Wyom:ng craton: Evidence for enriched ancient mantle," Geol. Soc. Austra//a Abs. #27, p.
68.
" Neal, C.R. L.A. Taylor, S.S. Hughes and R.A. Schmitt (1990), "The significance of fractional crystallization in the petrogenesis of Apollo 17 type A and B high Ti basalts," Geochim. Cosmochim. Acta 54, pp.18171833.
'Neal, C.R., L.A. Taylor, Y.-G. Liu and R.A. Schmitt (1991), " Paired lunar meteorites MAC88104 and MAC88105: A new " FAN" of lunar petrology," Geochim.
Cosmachim. Acta, in press.
'Neal, C.R., L.A. Taylor, R.A. Schmitt, Y.-G. Liu and J.O. Eckca (1991), " Cumulate lithologies and melt rocks from Apollo 17 breccias: Correlation of whole rock and mineral chemistry, including deep-seated spinel troctolite, chemistry and petrogenesis," Proc. Lunar Planet. Sci. Conf. 22nd, in press.
' Nelson, B.K. (1990), "Proterozoic anorogenic volcanism in North America: Isotopic and trace element constraints on andesco and rhyolite ger.esis, St. Francois Mts.,
Missouri," IAVCEI International Volcanological Conference Abstracts with Program, p. 77.
- Pearcy, L.G.. S.M. DeBari and N.H. Sleep (1990), " Mass balance calculations for two sections of island arc crust, and implications for the formation of continents." ,
Earth Planet. Sci. Lett., v. 96, pp, 427-442. Reyes, J.N. and T.W. Eichenberg (1990), " Scaling and Design of a Transpar: nt Two-Phase Natural Circulation Loop," Transactions of the American Nuclear Society, 62:683-685. Reyes, J.N. and T.W. Eichenberg (August 1990), " Numerical Analysis of Condensation Induced Water-Hammers in Horizontal Piping Systems," Oregon State University. Department of Nuclear Engineering Report OSU-NE-9102, Corvallis, OR. Reyes. J.N. and 'l.W. Eichenberg (November 1990), " Scaling and Design of a Transparent Two-Phase Natural Circulation Loop," Sixth Proceedings of Nuclear ThermalHydrau//cs, American Nuclear Society 1990 Winter Meeting Washington, D.C., p.113-121. Reyes, J.N. (January 1991), " Scaling Analysis for the AP600 Long Term Cooling Test Facility," Oregon State University, Dep8rtment of Nuclear Engineering Report OSU-NE-9107, Corvallis, OR.
'Roddy, D.J., R.A. Schmitt and S.H. Schuster (1991), " Asteroid and comet impacts on continental and oceanic sites: Computer simulations of cratering and interred Fe/Ir ratios in electa vapor compared with Fellr ratios measured at the K/T boundary from the Shatsky Rise (Pacific Ocean)," Lunar & Planet. Sci. XXII, pp. 1129-1130.
- Indicates OSTR use.
Vll8
'9oden, M.K. and D.S. Miller, "Tectono-thermal history of Hartford, Newark and Taylorsville Basins, Northeastern United States using fission-track analysis," Swiss Bull. Mineral. Pctrol., in press. .
'Roden. M.K., C.E. Ravenhurst and D.S. Miller (1991), "Effect of Etching on Apatite Fission-Track Annealing," Trans. Amer. Geophys. Union, EOS, 72, p. 309.
'Roden, M.K., M.T. Brandon and D.S. Miller (1990), " Apatite fission track thermochronology of the Olympic Subduction Complex, Washington," Gec!. Soc.
America, Abstracts with Programs,22, p. A324.
*Schilk. A.J., l.D. Hutcheon and R.A. Schmitt (1991), "Zelda's cousin revealed," Lunar
& Planet. Sci. XXII, pp. 1183 1184.
'Schmitt, R.A., Y.-G. Liu und R.J. Walker (1991), "Shatsky Rise evidences support hypothesis that hqttl a bolide (asteroid or comet) impact (BI) and Deccan Trap floodings (DT) caused CretaceouslTertiary (K/T) extinctions and not hypothesis of either Bl .qt DT alone, I., Lunar & Planet. Sci XXII, pp. 1187-1188.
'Schmitt, R.A., Y.-G. Liu and R.J. Walker (1991), "Shatsky Rise evidences sug, port hypothesis that koit1 a bolide (asteroid or comet) impact (BI) and Deccan Trap floodings (DT) caused Cretaceous / Tertiary (KIT) extinctions and not hypothesis of either BI ot DT alone,11., Lunar & P/anet. SciXXII, pp. 1189-1190.
- Shannon, W.M. and C.G. Barnes (1991), " Summary of the geochemistry and petrology of Proterozoic granitic rocks, Franklin Mountains, West Texas," Field Guide to Geologic Excursions in New Mexico and Adjacent Areas of Texas and Colorado New Mexico Bureau of Mines and Mineral Resources Bulletin 173, pp. 712.
'Shannon, W.M. and C.G. Barnes (1991), "Petrogenesis of Middle Proterozoic alkaline A-type granites, Franklin Mountains, El Paso, Texas," Geol. Soc. Amer. Abst, with Programs 23, p. 93.
'Sharma, M., A.R. Basu, R.B. Cok md P.G. DeCelles (1991), " Basalt-rhyolite volcanism by MORB-continental crust interaction: Nd, St-isotopic and geochemical evidence from southern San Joaquin basin, Califomia," Contributions to Mineralogy and Petrology, in press. *
' Shearer, C.K. (1990), " Geochemistry of Laramide igneous instrusions, northern Black Hills, with implications for petrogenetic relationships and magma sources,"
Metallageny of Goldin Black Hills, South Dakota, pp. 35-42.
'Snyder, G.A., L.A. Taylor, R.A. Schmitt and Y.-G. Liu (1991), "Petrogenesis of the westem highlands of the Moon: Evidence from a diverse group or whitlockite-rich rocks from the Fra Mauro Formation," Proc. Lunar Planet. Sci. Conf. 22nd, in press.
- Indicates OSTR use.
l
Vil 9
'.Snyder, G.A_.,- L.A. Taylor, Y. G. t.iu and R.A. Schmitt (1991), " Geochemistry of REEPy basalts: A new-basalt suite from Apollo 14," Lunar & Planetary Science XX//, [
-Lunar and Planetary institute, Houston, pp. 1293 1294.
'Streck, M.J. and A.L. Grunder (1991), "The Rattlesnake Ash flow Tuf f, eastern Oregon: i zoning and a large compositional gap," Geological Society of America Abstracts with Program, 22:101,
' Warner, R.D., D.S. Snipes, S.S. Hughes, R.J. Walker, R. A. Schmitt z 41 J.C. Steiner,
" Geochemistry and Petrology of Mesozoic Dikes in South Caroliru ' Eastern North American Mesozoic Magmr'sm, Special Paper 268,in prnss.
' Warner, R.D. and D.S. Snipes, "Diabase Dikes of Chester and Fairfield Counties, South Carolina," in press.
'Wollenber9, H.Al, A.R. Smith and S. Flexser (1991), " Radionuclides in hydrothermal systems as indicators of respository conditions," Scienti//c Basis /or Nuc/ car Waste Management X/V, v. 212, pp. 711-718.
l-l-
- Indicates OSTR use.
l I Vil 10 B. Ititsaa
'Burchell, A. (1991), "Mid-Tertiery Volcano Stratigraphy and Petrogenesis of the Galivro Mountains, Pinal, Graham, Cochise Counties, Southern Arizona," Masters thesis. .
University of Arizona.
'Cerveny,Ill, P.F. (1991), " Fission-Track Thermochronology of the Wind River Range and -
Other Basement Cored Uplif ts in the Rocky Mountain Foreland," Ph.D. dissertation, University of Wyoming.
'Cho, B.-O. (1990), " Nodal Methods for Calculating Nuclear Reactor Transients, Control Rod Patters, and Fuel Pin Powers," Ph.D. dissertation, Nuclear Engineering, Oregon State University.
Eichenburg, T.W. (1990), " Numerical Analysis of Condensation induced Water Hammer in Horizontal Piping Systems," Masters thesis, Nuclear Engineering, Oregon State
- University.
' Harris, K. (1991), " Petrology, geochemistry, and petrogenesis of the Tertiary igneous intrusions in the Annie Creek /Foley Ridge Mine arsa, and their relationship to the gold mineralization," Masters thesis, - South Dakota School of Mines and Technology.
'Jin, Y. (1991), " Petrology, mineralogy, and geochemistry of upper mantle / lower crustal xenoliths and their hot,t basalts from Tahiti, Society Islands, French Polynesia,"
Pn.D. dissertation, University of Tennessee at Knoxville.
' Jordheim, D.P. (1990), " CHAIN.238DJ: A Computer Code for Calculating Pu-238 Production, Quality, and impurity Levels in the Np-237 Trarismutation Chain "
Masters thesis, Nuclear Engineering, Oregon State University.
'Kausar, A.B. (1991)," Petrology of the Kohistan Arc and hosted hydrothermal sulfides,
- Gilgit area, Pakistan," Masters thesis, Oregon State University,256 pp.
King 'J.B. (1991), "A' Study of Buoyant Backflow in Vertical Injection Lines," Ph.D. fdissertation, Nuclear Engineering, Oregon State University. Lafi,E A.Y. (1990), "A General Theory for Flooding implementing the Cuspoids Catastrophe," Ph.D, dissertation, Nuclear Engineering, Oregon State University. Piepmeier, E. (1991), "Pharmacokinetics of Parenteral Thrombomodulin Analogues," Ph.D. dissertation, College of Pharmacy, O'regon State University.
"Schilk, A.J. (1991), _" Chemical and statistical analyses of chondrules from the Mokoia (CV3) meteorite," Ph.D. dissertation, Oregon State University.
-Zahm, L. (1990), " Nuclear lovestigations of the Electrolysis of D 2O Using Palladium Cathodes and Platinum Anodes " Masters thesis,- Nuclear Engineering, Oregon State University.
- Indicates OSTR use_
o Vll 11 C. Bgports Su_bmitted for Publicatiou
'Cerveny, lit, P.F. and J.R. Steidtmann (1991), " Fission Track Thermochronology of the Wind River Range, Wyoming: Evidence for Timing and Magnitude of Laramide Exhumation," Tectonics, submitted.
'DeBari, S.M. (December.1990), "Petrogenesis and physical evolution of the Fiambala ;
gabbronorite, northwestern Argentina: Syntectonic magmatism in the deep crut: ; of a continental margin arc," J. Petrol., submitted. , I
'Grunder, A.L. and S.H. Wickham, "'80 depletion and '80/'80 homogenization of the continental crust during extension-related magmatism," Earth and Planetary Science Letters, submitted.
- Kalaswad, S., M.K. Roden, D.S. Miller and M. Morisawa (1991), " Evolution of the Continental Margin of Western India: New Evidence from Apatite Fission-track Dating," I;eol. Soc. America Abstracts with Programs, submitted. ;
3
'Neal, C.R., L.A. Taylor, Y. G. Liu and R.A. Schmitt (1991), "New lunar meteorite MAC88105: a- ferroan anorthosite breccia with possit>'a mare tendencies,"
Geochim. Cosmochim. Acta, submitted.
'Neal, C.R., L.A. Taylor, R.A. Schmitt, Y.-G. Liu and J.O. Eckert (1991), "A plethora of ,
highland lithologies from the Serenitatis Basin: a window to crustal processes and ' compositions," Proc. Lunar & Planetary Science, 22nd, submitted. t
' Pan, Y., W.S.F. Kidd, P. Copeland, T.M. Harrison and M.K. Roden (1991), " Structural and Thermochronological Analysis of a Major Low-Angle Extension Shear Zone in the Nyainquentanglha Range, Souther Tibet," Geol. Soc. America Abstracts with Programs, submitted.
' Pogue, K.R.,-J, A. DiPietro, S.S. Hughes, R.D. Lawrence, S. Rahim and J.ii. Dilles, " Late Paleozoic rifting in northern Pakistan," Tectonics, submitted. ,
'Wamer, R.D., D.S. Snipes, S.S. Hughes, R.A. Schmitt and J.C. Steiner (1991),-
" Geochemistry and petrology of Mesozoic dikes in South Carolina," Geol. Soc.
Amer. Special Paper, submitted. ; t. l-
- Indicates OSTR use.
l 1
-Vli 12 D. Documents in Preoaratlan i i
- 1. Eublications
' Brandon, _ M.T., M.K. Roden and D.S. Miller, " Apatite fission track thermochronology of the Olympic Subduction Complex, Washington.
'Burchell, A., " Revised Geologic Map of the Galivro Wilderness, Galivro Mountains, Southern Arizona," U.S.G.S. Open File Report.
'Cerveny 111, P.F. and A.W. Snoke, "Thermochronological Data from Tobago, West Indies: Constraints on Cooling and Accretion History of Mesozoic Arc Rocks in the Southern Caribbean Sea," Tectonics.
,.
- England, T.D.J., N.W.D. Massey, D.S. Miller and M.K. Roden, " Apatite Fission-Track Dating of the Cowichan Fold and Thrust System, Southern Vancouver Island, British Columbia."
- Kalaswad, S., D.S. Miller and M.K. Roden, " Evolution of the Continental Margin-of Western India: New Evidence from Apatite Fission-Track Dating."
b
- Indicates OSTR use.
Vil-13
- 2. Theses Almonacid, S., " Determination and prediction of temperature abuse of fects on the microbial spoilage of refrigerated foods," Maste s thesis.
Anand, A. (1991), " Monte Carlo Design and Simulation of a Shipboard 252 Cf-Based PGNAA Analyzer for the Sensitivity Analysis of Seafloor Cores," Masters thesis, Nuclear Engineering, Oregon State University.
'D'Arcy, K.A., " Age and Composition of Precambrian Metasedirnentary Rocks of the Montana Metasedimentary Terrane: Implications for Crustal Evolution,"
Ph.D. dissertation. Donnelly, P.K., " Degradation of aromatic compounds by mycorrhizal fungi," Pn.D. dissertation.
' Horn. L., " Origin of the Lady of the Lake Layered Mafic Intrusion, Tobacco Root Mountains, Montana," Masters thesis.
Kantt, C.," Development of enzymatic treatraents for the on board preservation of shrimp," Masters thesis.
- Murphy, J., " Composition and Origin of Archean Metasodimentary Rocks of the Grevelley Range, Montana," Masters thesis.
- Indicates OSTR use. '
Vil 14 E. Presentations ' Almonacide-Morino,' S.F. and J.A. Torres (1991), " Validation and application of computer models to estimata shelf-life of chilled seafood," Pacific Fisheriec Technologists Meeting, February 17 20, Victoria, British Columbia. Binney, S.E., B. Dodd and J.C. Ringle (1991), "The Oregon HLW Transport Public ' information and involvement Prograru," Trans. Americt,nNuc/carSociety,63:357-358. Binney, S.E., D.P. Jordheim and R.E. Schonter (1991), "A Computer Code for Calculating Pu-238 Production, Quality, and impurity," Trans. American Nuclear Society, 63:423-424, Binney, S.E., M.L. Blazek, J.E. Franco, R.W. Robison and B. Dodd (February 1991),
"Public Concems about Radioactive Waste Transport in Cregon," Proceedings of the Symposium on Waste Management, Tucson, Arizona, Volume 1, pp. 359 364.
Binney, S.E., M.L. Blazek, J.E. Franco, R.W. Robison, W.J. Sanderson, D.A. Stewart-Smith and B. Dodd (April 1991), "The Oregon Experiment: Public Information and involvement," Proceedings, International High - Level Radioactive Waste Management Conference, Las Vegas, Nevada, pp. 741-747. Binney, S.E., B.- Dodd and D.D. Simmons (1991), "The Relationship of Oregonian's Values to their Concems about the Transport of Radioactive Waste," Health Physics Society Annual Meeting, Washingtoni D.C.
'Burchell, A, (1991), "Mid-Tertiary Volcano Stratigraphy and Petrogenesis of the Gal;vro
-Mountains, Southern Arizona," University of Arizona Geoscience Colloquium Abstracts with Programs.
-*Cerveny ill., P.F., R.J. Dorsey and B.A. Burns, " Apatite and Zircon Fission-Track Ages from the Sierra San Pedro Martir, Eastern Peninsular Range, Baja California, l Moxico," Abstracts with Programs, G.S.A. Cordilleran Section, San Francisco, L Califomia.
'Cox, L.J., B. Houser, E. Force, A. Burchell, M. Gettings and F. Fisher (1991), "Gaologic Mcp cf _ the Sierrita-Mogollon Corridor (AZ-NM) and implications for Mineral Resources " U.S.G.S. Research on Minera/ Resources 1991, Seventh Annua l V.E.
McKelvey Forum, U.S.G.S. Circular 1962.
'Dodd, B. (1990), " Teaching and Training Applications of the OSU TRIGA Reactor,"
! Proceedings, American Nuclear Society Topical Meeting, The Safety Status and Future of Non-Commercial Reactors and Irradiation Facilities, Boise, Idaho.
"Dodd, B. and J.F. Higginbotham (1990), " Dose Commitment Due to Airborne release of Radioactive Materials from Research Reactors," TRTR-90, University Park, ,
PennsWvania. l
- Indicates OSTR use.
Vil 15
'Dorsey, R.J. and B.A. Burns, " Tectonic implications of Lower to Middle Miocene Sedimentary end Volcanic Rocks in Northern Baja California, Mexic n" Abstracts with Programs, G.S.A. Cordilleran Section, San Francisco, California.
'Elliott, W.C., J.L. Aronson, M,K. Roden and D.S. Miller (1990), "The formation of illite in the Appalachian Basin: A test of the f!uid expulsion hypothesis," Geol. Soc.
America, Abstracts with Programs, 22, p. A62.
'Fodor, R.V., A._N. Sial and E.H. McKee, "High TiO2 (> 3 wt.%) Cretaceous dikes of northeastern Brazil: geochemistry and petrology," International Dike Conference, Adelaide, Australia, September 12-17,1990.
'Grunder, A L. (1991), "High Unperature hydrothermal circulation during middle tertiary magmatism in eastern Nevada " Geological Society of America, Abstracts with Programs, 22:22.
'Higginbotham, J.F. (June 1991), " Refurbishment of the Oregon State University Rotating Rack," Transactions of the American Nuclear Society, 63:25-26.
'Hoernle, K.A., H.U.' Schmincke and G. Tilton (1990), "A blob model for the multi-cycle evolution of a Canary Island volcano," lAVCEl, Mainz,- Federal Republic of Germany.
'Hoernle, K.A., G. Tilton and H.U. Schmincke (1990), "The 15 m.y. isotouic evolution
, of Gran Canaria, Canary Islands," EOS Trans. Am. Geophys. Union 71, No.
- 43:1696.
Kantt, C., J. Bouzas and 'J.A. _Torres (1991), " Microbial challenge tests and browning
-of a glucose oxidase / catalase solution used for the on-board preservation of
, shrimp," 52nd Annual Meeting of the Institute of food Technologists, June .1-5, l- Dallas, Texas. , Klein,- A.C., B.R. Lewis and R.A. Pawlowski (August 12-17,1990), " Advanced l: Thermionic Reactor Systems Design Code," Proceedings,25th Intersociety Energy j Conversion Engineering Conference, Reno, Nevada, Vol. 2, pp. 305-309. l- Klein, A.C., L.L. Zahm,' S.E. Binney, J.N. Reyes, J.F. Higginbotham, A.H. Robinson, M. l Daniels and R.B. Peterson (October 22-24,1990), " Anomalous Heat Output from l Pd Cathodes without Detectable Nuclear Products," Proceedings, Anomalous Nuclear Effects in Deuterium / Solid Systems Workshop, Provo, Utah. Klein, A.C. and A.I.A. Almarshad (October 14-19,1990), "A Semi-Empirical Model for Diffusion of Oxygen in Zirconia," Proceedings,. Symposium on High Temperature-
. - Chemistry of the Electrochemical Society, Seattle, Washington.
Klein, A.C. and T.S. Marks (January 1991), "An Experimental Approach to Compare
- Wicking Stabilities of Fabric Materials for Heat Pipe Applications," Proceedings,
_ Eighth Symposium on Space Nuclear Power Systems, Albuquerque, New Mexico,
.pp. 869-874.
- Indicates OSTR use. '
m
. Vil-16 Klein, A.C., B.R. Lewis, R.A. Pawlowski and K.J. Greek (Januev 1991), " Advanced Thermionic Reactor Systems. Design Code," Proceedings, Eighth Symposium on Space Nuclear Power Systems, Albuquerque, New Mexico, pp. 222-227.
Klein, A.C. and T.S. Marks (January 1991), " Material Compatibility issues for Fabric Composite Radiators," Proceedings, Eighth Symposium on Space Nuclear Power Systems, Albuquerque, New Mexico, pp. 32.0-325. Klein, A.C., H. Al-Baroudi and K.A. Pauley (January 1991), " Experimental Simulation of - the Bubble Membrane Radiator Using a Rotating Flat Plate," Proceedings, Eighth Symposium on Space Nuclear Power Systems, Albuquerque, New Mexico, pp. 723-727. Klein, A.C., R.A. Pawlowski and H.H. Lee (June 1991), " Low Power incore Thermionic Space Reactor Design Concepts Using Advanced Technology," Proceedings, international Conference on Emerging Nuclear Energy Systems, Montorey, Califomia, pp.1011.
- Knaus, R.M., " Instrumental Neutron Activation Analysis to Measure Short-Term Accretion and Erosion in Wetlands Using Rare Earth Element Soil Horizon l Markers," J. Radioanal. Nucl. Chem., in press; Proceedings, International Conference on Activation Analysis andits Applications, Beijing, China, October 15-19,1990.
- Knaus, R.M., "The Application of f-Elements in Ecological Research," European Journal of Solid State Inorganic Chem., 26:379; First Internation Conference on f-Elements, Pro. Gram and Abstracts, September 4-7,1990.
*Kowallis, B.J., E.H. Christiansen and A.L. Deino (1990), " Age of the Cenomanian-Turonian boundary in the Westem Interior of the United States," Seventh -
international Conference on Geochronology, Cosmochronology, and11sotope : Geology, Canberra, Australia.
' Lewis, S.E., S.S. Hughes, M.J. Bartholomew and R.J. Walker (1991), " Geochemical Comparison of Representative Plutonic Suitos from a Proterozoic (Appalachian Blue R;dge) Magmatic Arc," Geologic Society Of America, Abstracts with Programs,in press. .
' ' Lewis, S.E., S.S. Hughes, M.J. Bartholomew and R.J.~ Walker (1991), " Lower Crustal l Evolution of Middle Proterozoic rocks in the Central Virginia Blue Ridge during Grenville - methamorphism,* Geological Society of America, Abstracts with Programs, NE-SE Section Meeting, v. 23, no.1, p. 59.
*Mogk, D., P. Mueller and J.L. Wooden (1990), "Archean magmatic and tectonic accretion n the northem Wyoming Province, SW Montana, USA," Limpopo Field !
Conference. *
- Indicates OSTR use.
l
J t Vil 17
'Mueller, K.A., " Cenozoic Exhumation of the Northern Ruby-East Humboldt Metamorphic Complex, Northeast Nevada: Kinematic, Temporal and Geometric Constraints,"
Abstracts with Programs, G.S.A. National Convention, San Diego, California.
'Mueller, P.A., D.W. Mock, K. D'Arcy, A. Heatherington, J. Hofle, J. Murphy, P.
Thurston and J. Wooden (1990). " Crustal evolution in the Montana metasedimentary terrane,* Taylor Colloquium / Origin and Evolution of Planetary Crusts) Abs., p. 23.
'Neal, C.R., L.A. Taylor, R.A. Schmitt, Y.-G. Liu and J.O. Eckert (1991), " Cumulate i lithologies and melt rocks from Apollo 17 breccias: Corralation cf whole rock and l mineral chemistry, including deep-seated spinel troctolite, chemistry and petrogenesis," Proc. Lunar Planet. Sci. Conf. 22nd, in press.
'Neal, C.R., L.A. Taylor, R.A. Schmitt, Y.-G Liu and J.O. Eckert (1991), "A plethora of highland lithologies from the Serenitatis Basin: a window to crustal processes and compositions," Proc. Lunar and Planetary Science, 22nd, submitted.
~
Nelson, B.K. (September 1990), " Isotopic and chem! cal studies of the origin of continental crust," Dept. des Sciences de la Terre, Universite de Montpellier, Montpellier, France.
' Nelson,- B.K. (1991), "Curstal growth in central Europe-Isotopic evidence from the Bohemian Massif," Geol. Soc. America Annual Meeting, San Diego, California.
Piepmeier, E., "Pharmacokinetics of Parenteral Thrombomodulin Analogues," Western Regional. American Association of Pharmaceutical Scientists Meeting, Reno, Nevada, March 1991. Reyes, J.N. and T.W. Eichenberg (1990), " Scaling and Design of a Transparent Two-Phase Natural Circulation Loop," Transactions of the Ainarican Nuclear Society, 62:683-685. Reyes, J.N. and T.W. Eichenberg- (November 1990), " Scaling and Design of a Transparent Two-Phase Natural Circulation Loop," Sixth Proceedings of Nuclear ThermalHydraulics, American Nuclear Society 1990 Winter Meetiag, Washington, D.C., pp.113-121.
' Roden, M.K., - M.T. Brandon and D.S. Miller (1990), " Apatite fission-track -
, thermochronology of the Olympic Subduction Complex, Washington," Geol. Soc. f America, Abstracts with Programs,22, p. A324. L 'Schieber, J., "A comparison of provenance clues from -interbedded shales and L sandstones of the Mid-Proterozoic New: Land Formation, Belt Series, Montana, USA," AGU meeting, San Francisco, California, December 1990.
'Shannon, W.M. and C.G. Barnes (1991), "Petrogenesis of Middle Proterozoic aikaline A-type granites, Franklin Mountains, El Paso, Texas," Geol. Soc. Amer. Abst. with Programs 23, p. 93.
- indicates OSTR use.
~ . _ .. - ._ . ~ . . . _ . _ . _ _ _ . _ . . _ _ _ ._ -
Vil 18 -
'Snyder, G.A., L.A. Taylor, R.A. Schmitt and Y. G. Liu (1991), "Petrogenesis of the western highlands of the Moon: Evidence from a diverse group or whitlockite rich -
rocks from the Fra Mauro Formation," Proc. Lunar Planet. Sci. Conf. 22nd, in press. ,
'Streck, M.J. and A.L. Grunder (1991), "Th Rattlesnake Ash-flow Tuf f, eastern Oregon:
zoning and a large compositional gap,' Jeo.'opics' Society of America Abstracts with Program, 22:101. i i l
- Indicates OSTR use.
Vil19 F. Public Relations The continued interest of the general public in the TRIGA reactor is evident by the number of people who have toured the facility. In addition to many unscheduled visitors and interested individuals who stopped in without appointments because they were ir. the vicinity, a total of 572 people were given pre planned and scheduled tours during this reporting period. The Gulf crisis resulted in some general open houses being cancelled because of security considerations. See Table Vll.F.1 for statistics on scheduled visitors, I
i Vll-20 l l Table Vll.F.1 i Summary of Visitors to the Radiation Center No. of Date - Visitors Name July 11,1990 1 Al Mobley, Governor Candidate July 12,1990 3 Teledyne Wah Chang, Albany . August z,1990 10 Radiation Center / Nuclear Engineering Advisory Board August 10,1990 25 American Society of Civil Engineers - Minority High School Students August 21,1990 4 Friends of Faculty September 25,1990 1 U.S. Air rorce September 25,1990 3 KGW-TV fron Portland October 4,1990 25 Oregon Episcopal School Science Students October 5,1990 1 Japan Atomic Eneigy Research Institute October 5,1990 4 Westinghouse Hanford October 9,1990 1 Brad Slavin, OSU Student October 9,1990 4 Oregon Metallurgical Corp., Industrial Radiography Class October 23,1990 3 NROTC--OSU November 6,1990 25 Chemistry 219 Class November 15,1990 10 Society of American Military Engineers November 20,1990 1 Jack J. Fix, Pacific NW Laboratories, Richland, Washington November 21,1990 4 Scott Anderson's Family December 13,1990 1 Norm Lewis, Editor, Corvallis Gazette-Times January 14,1991 6 Reed College Reactor Operator Training Class January 17,1991 -12 Chemistry 462 Students January 17,1991 1 Belaid Mahiou February 7,1991 40 OSU Public Health Class (Man / Health and Environment H344) February 8,1991 10 Roy Rathja and High School Students
-.._ ._ _ ___.._. _. ~ ._ _ _ _ -
l - Vll 21 Table Vll.F.1 (Continued) No. of Date Visitors - Name ; February 9,1991- 20 Beaver Open House February 13,1991 29- Wilson Elementary School February 13,1991 2 Coke Evans--Portland Valve and Fitting February 14,1991 2 General Atomics (Bill Hyde and Manager) February 18,1991 2 J. Sparks and N. Sparks February 27,1991 20 St. Thomas Moore Schno!, Portland March 1,1991 50 Mom's and Dad's Club March 5,1991 1 China National Nuclear Corporation ,. March 8,1991 15 Oregon Department of Energy L March 13,1991- 21 Coquille High School- Physics Students March 18,1991 20 State Future Farmers of America Convention l April 9,1991: 7 Group of OSU Students Linn-Benton Community College Science April 11,1991 15 Students April 24,1991 12 Yamhill/Carlton Higli School Physics Students May 4,1991' '20 Mom's Weekend Open House May 7,1991 40 OSU Public Health Class (Man / Health and Environment H344) May 9,1991-- 35'- Newport High School Students , May 10,1991 30 PH 313, Energy A'ternatives Class May _13,1991 3 OSU Students Mav.14,- 1991 - 6 Nuclear Engineering Graduate Review Council May 20,1991 1 Mr. Jurnalis Kamil'
-1 May 21,1991 11 SvJeet Home High School Students May 23,1991 5 Col Young Middle School Students June 24,1991 10' Oregon High School Teachers TOTAL 572
- , ... ._. _}}