ML20058F224
| ML20058F224 | |
| Person / Time | |
|---|---|
| Site: | Oregon State University |
| Issue date: | 06/30/1990 |
| From: | Anderson T, Dodd B, Higginbotham J Oregon State University, CORVALLIS, OR |
| To: | |
| Shared Package | |
| ML20058F213 | List: |
| References | |
| NUDOCS 9011080157 | |
| Download: ML20058F224 (192) | |
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.s ..V.. ...e g a , g, f, PNU o, tw.- 1 i j Annual Report l of the Oregon State University Radiation Center i and l TRIGA Reactor July 1,1989 June 30,1990 _ i To satisfy the requirements of: A. U.S. Nuclear Regulatory Commission, License No. R 106 (Docket No. 50 243), Technical i Specification 6.7(e), i ' B.- Task Order No. 3, under Subcontract No. C84110499 (DE AC07 76ERO1953) for j University Reactor Fuel Assistance AR 67 88, issued by EG&G Idaho, Inc. a C. . Oregon Department of Energy. ODOE Rule No. 30 010. ~ l l . i Written by: i s T.- V. Anderson, Reactor Supervisor [ y B. Dodd,- Reactor Administrator i J. F. Higginbotham, Senior Health Physicist ' D. S. Pratt, Health Physicist
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A. G. Johnson,' Director .j I I l i Submitted by: A. G. Johnson 1 Director, Radiation Center l Radiation Center Oregon State University _ e Corvallis, Oregon 97331 5903 Telephone: (503) 737-2341 3 i 4 October 1990 T f I l 1: Annual Report of the Oregon State University Radiation Center and TRIGA Reactor 7 Table of Contents EEL 2 l PART I OVERVIEW i A. Ac knowled g ements........................................... 1 1 l B. Executive Summary..................... ......................l2 C. I nt r o d u c ti o n..................................... ...........15 D. Overview of the Radiation Center ............ 16 E. Summary of OSTR Environmental and Radiation Protection Data............ 19 1. Liquid E f fluents Released .................................. 1 9 j 2, Airborne Effluents Released ................................110 3. Solid Waste Released..................................... 1 10 4. Radiation Exposure Received by Personnel...................... 1 11 l 5. Number of Routine Onsite and Offsite Monitoring Measurements and Sample s.......................................... 112 F. H i st o ry................................................... 1 1 3 PART 16 - PEOPLE A~. Faculty.................................................... 11 1 i B. Visiting Scientists and Special Trainees,,.......................... 114 C. O SU Graduate Students....................................... 11 5 D. Business, Administrative and Clerical Staf f.....,.................... 116 E. Reactor Operations Sta f f...................................... 11 6 - F. Radiation Protection Sta f f -..........................,............ ll-6 G. Scientific Support Staff ....... Il-7 H. OSU Radiation Safety Of fice Staf f.............,................... Il 7 1. Committees 11 8 1. Reactor Operations Committee..,.......,.................... - ll 8 .2. Radiation Safety Committee................................ 11 8 3. Radiation Center Safety Committee........................... 11-8 O 1 1 '3, Eaga
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PART 111 FACILITIES A. Rese e rch Reactor............................................. Ill 1 .1. D e scri ption............................................. Ill 1 2. Utilization................ ....... 111-5 a. instruction ...........................Ill6 ~ b. R e s e a r c h......................................... 111 9 B. Analytical Equipme nt........................................ 111-1 1 1. D e sc ri ption........................................... 111-1 1 2. U tiliz atio n............................................. Ill 1 1 ' C. Radioisotope Irradiation Sources................................. lll 15 1. De sc ri ption............................................ lll 1 5 2. Utilization... .....................lll-15 D. X Ray Machine ..............................................Ill19 1. Description... 111 1 9 2. Utilization............. 11 1 1 9 E. Laboratories and Classrooms...... ...........................11120 1. D e scri pti on........................................... 111 2 0 '2. Utilization........ ...................................-.Ill21 F. Instrument Repair and Calibration Facility.......................... 11124 1. D e sc riptio n............................................ Ill 2 4 2. U tiliza tion........................,.................... Ill 2 4 G.. Libra ries.................. ........................Ill25 1. D e scri ption............................................ Ill 2 5 2. Utilization............. ...............................Ill26 PART IV REACTOR A. O perating S ta tistics........................................... IV 1 B. Experiments Perf ormed........................................ IV-10 'C. Unplanned Shutdowns....,.. ................................IV12 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 Reactor Procedures................... IV 18 3. 10 CFR 50.59 Changes-to Reactor Experiments :.............,.. IV j E. Surveillance and Maintenance...... ............................IV-30 1. - Non Routine Maintenance........... ......................IV-30 2. Routine Surveillance and Maintenance......................... IV 30 .F. Reporta blo Occurrences....................................... IV 30 'A i I P.ag.e
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PART V - PROTECTION ~ A, Introduction................ ................................V1 B. Environmental R elea se s........................................ V 3 1. Liquid Effluents Released ............................ V-3 2. Airbome Effluents Released ..................................V-3 3. S olid Wa st e Rele a sed................................,..... V 6 C. Pe r sonnel D os e s............................................. V-8 D. Facility Survey Data......................... ................V11 1. Area Radiation Dosimeters................................ V-1 1 2. Routine Radiation and Contamination Surveys..,,................ V-16 E. Environmental Survey Data.................................... V-1 8 1. Gamma Radiation Monitoring ...........................V18 2. Soil, Water, and Vegetation Surveys.......................... V-24 F. Radioactive Material Shipments................................. V-28 G. R e f e r e nc e s............................................... V-31 PART VI - WORK A. Summary ..................................................VI-1 1 B. Teaching....................................................,VI1 c. C. - Research and Service........ ,...,,...,,......................VI-1 1, Neutron Activation Analysis............................... VI 3 2 2. Forensic S tudie s '......................................... VI-3 3 3. Irra diations............................................ VI-3 3 4. Radiological Emergency Response Services..................... VI 3 3 5. Training and instruction ..........................VI34 6. Radiation Protection Services............................... VI-3 5 7. RadiologicalInstrument Repair and Calibration................,.. VI 3 6 8. C onsult a tion........................................... VI-3 6 PART Vil - WORDS A. Publications in Print..........................................Vll1 B. T h e s e s................................................... Vi l 8 C. Reports Submitted for Publication... ............................Vll9 D. Documents in Preparatio,n. .. Vll11 1. Pu blica tio n s........................................... Vil-1 1 4: 2. Thesos.......... ...... ~ Vil-12 E. Presentations .............................. Vl l 1 3 F. Public Relations....... Vll 17 1 - LIST OF TABLES hy.g Titla Paae lli.A.1 - OSU Courses Using the OSTR............................ Ill 7 Ill. A.2 OSTR Teaching Hours .................................Ill8 lil.A.3 O STR Research Hours................................ Ill-10 111.B.1 Radiation Center Spectrometry Systems: Gamma, Low Energy Photon, Al pha...................................... t il 12 .Ill.B.2 Radiation Center Liquid Scintillation Counting Systems........ 111 13 Ill.B.3 Radiation Center Proportional Counting Systems.............. Ill 14 Ill.C.1 Cobalt-60 Irradiator Use.............................. ill-18 Ill.E.1 ' Student Enrollment in Nuclear Engineering and Nuclear Science Courses Which Are Taught or Partially Taught at the Radiation Center ............ Ill 2 2 4 - IV.A.1 OSTR Operating Statistics (Using the FLIP Fuel Core) ...........IV2 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-6 IV.A.5 OSTR Use Time in Terms of Specific Use Categories............ IV-7 i lV.A.6 OSTR Multiple Use Time....., ................IV8 IV.B.1 Use of OSTR Reactor Experiments....................... I V-1 1 .IV.C.1 -Unplanned Reactor Shutdowns (Scrams) ... IV-13 l" V.A.1 Radiation Protection Requirements and Frequencies............. V-2 a. V.B.1 Monthly Summary of Liquid Effluent Releases to the Sanitary Sewer for the year July 1,1989 through June 30,1990 .V4 V.B.2 Monthly Summary of Gaseous Effluent Releases for the Year July 1,1989 through June 30,1990......... ...V5 l LIST OF TABLES (Continued) 3: Table Til!g Pace ^V.R.3 Annual Summary of Solid Waste Generated and Transferred for the Year July 1,1989 through June 30,1990.... .........V7 V.C.1 Annual Summary of Personnel Radiation Doses Received for the Year July 1,1989 ~through June 30, 19 9 0............... V 10 - V.D.1 Total Dose Equivalent Recorded on Area Dosimeters located Within tha TRIGA Reactor Facility for the Year July 1,1989 ^ through June 3 0, 19 9 0............................... V 13 V.D 2 Total Dose Equivalent Recorded on Area Dosimeters Located Within the Radiation Center for the Year July 1,1989 through June 30,1990 ........................V-14 V.D.3 Annual Summary of Radiation Levels and Contamination Levels 1 Observed Within the Reactor Facility and Radiation Center-During Routine Radiation Surveys for the Year July 1,1989 through June 30,1990 .............................,V17 _ V.E.1 --Total Dose Equivalent at the TRIGA Reactor Facility Fence -for the' Year July 1,1989 through June 30, 19 90.,.......... V-21 V.E.2 Total Dose Equivalent at the Off Site Gamma Radiation ~ Monitoring Stations for the Year July 1,1989 through J u ne 3 0, 1 9 9 0........................,............ V-2 3 V.E.3 Annual Average Concentration of the Total Net Beta Radioactivity (Minus 3H) for Environmental Soil Water, and Vegetation Samples for the Year July-1,1989 through June 30,1990 .....................................V26-2V.E.4 Average LLD Concentration and Range of LLD Values for Soil, Water and Vegetation Saroles for the Year July 1,1989 1 through June 30,1990 ...............................V27 V.F.1 Annual Summary of Radioactive Material Shipments Originating From the TRIGA Reactor Facility's NRC License R-106 for the Year July 1,1989 through June 30,1990. ................V29 V.F.2 Annual Summary of Radioactive Material Shipments Originating From the Radiation Center's State of Oregon License ORE 0005 3 for the Year July 1,1989 through June 30,1990........ .... V 30 LIST OF TABLES (Continued) IAhlt Ilite Page VI;C.1 Institutions and Agencies Which Utilized the Radiation Center............................................VI-3 VI.C.2 Graduate Student Thesis Research Which Utilized the Radiation Center ......................VI-6 VI.C.3 Listing of Major Research and Service Projects Performed at the Radiation Center and Their Funding Agencies........... VI 12 VI.C.4 Summary of the Types of RadiologicalInstrumentation Calibrated to Support the OSU TRIGA Reactor and the Radiation Center ..................IV38 VI.C.5 Summary of RadiologicalInstrumentation Calibrated to Support Other Agencies............................... VI 39 Vit.F.1 _ Summary of Visitors to the Radiation Center for the period July 1,1989 through June 30,19 90..,,........... Vll 18 3 e h .g t m LIST OF FIGURES k 1 Floure .Thig Paae 1.D 1 Floor Plan of the Radiation Center........ ........... 18 Ill. A.1 Cutaway View of Standard TRIGA Mark 11 Core Arrangement..... 1112 Ill.A.2 Horizontal Section of TRIGA Mark 11 Reactor.................. Ill 3 Ill.A.3 Vertical Section of TRIGA Mark 11 Reactor ...................Ill4 Ill.C.1 Budd Cobalt 60 Irradiator (Vertical Section)................ 111 - 1 6 Ill.C.2 Gammacell 220 Cobalt 60 Irradiator ......................lll17 IV.A.1-OSTR Annual Energy Production Vs. Time (Annual Reporting Period) ......IV-9 i IV.E.1 Monthly Surveillance and Maintenance (Sample Form)......... IV 32 IV.E.2 Quarterly Surveillance and Maintenance (Sample Form).........IV-33 IV.E.3 Semi-Annual Surveillance and Maintenance (Sample Form)...... IV 35 - IV.E.4-Annual Surveillance and Maintenance (Sample Form)........... IV-37 V.D.1 TRIGA Facility and Radiation Center Area Dosimeter L oca ti on s......................................... V 1 2 .V.E.1 Area Radiation Monitor Locations for the TRIGA Reactor, and on the TRIGA Reactor Area Fence...........,........ V-19 i V.E.2 - Monitoring Stations for the OSU TRIGA Reactor for the Year July 1,1989 through June 30,1990................. V-22 !i k } y. } l l o ,-, 2,., , ' [.u ','. .. -. -[. .hm,, a ::. y y. r,a.j., ( " f ' # "4 ,, g [ .,s -.,. n.g yy,., f).i, n,.,. : ~ - .,7 < (./ .r. .,, ; . I, n,' \\. .i<,., y c a y .L.,lM.b.,. q,;- & g y.y.. ' - (',? ' r-. 1 y o :,y.,.. g., f 1 mdQ r 'yn -K g, ', . u .v ,? ' ' '.. / n..j y-.. .y
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j PARTl 9
OVERVIEW A.
Acknowledaements During the 1989-90 reputing period, many individuals and organizations helped the Radiation Center succeed. In recognition of this, the staff of the OSU Radiation Center and TRIGA Reactor would like to offer their appreciation to all of those v,ho contributed to the information and events containad in this report. To the University administration who consistently supported our prceram; to those who provided our funding, particularly the state of Oregon and the U.S. Department of Energy; to oe regulators; to the researchers, the students and others who used our facilities and services; to the OSU l
Physical Plant, who patiently provided invaluable assistance through their engineering, maintenance, and other supporting programs; to the OSU Security and University Police who are always there when we need them; and to the OSU Departmen; of Printing, who consistently produce a quality product; we most earnestly say thank you.
As a final note of gratitude, the staf f would like to highlight the talents and the tolerance of our secretarial staff, who performed admirably during the preparation of this report.
l C
l2 1
- B.
Executive Summary ge The OSU Radiation Center is pleased to report the completion of another successful year a year in which there was a continuation of the growth identified in previous years, as a
well as significant advances in several new areas. However, before we summarize our achievements, we would like to express our appreciation to everyone who contributed to our success. In particular, we wish to thank the university's administration for their financial and administrative support and for their encouragement. We are also most t
grateful to the U.S. Department of Energy for their valuable support through the university reactor sharing program and for the benefits we received from the DOE's important new program designed to help modernize research reactor equipment. We would also like to_ extend our gratitude to the many other organizations whc, funded
-research and technical services conducted at the Center. The resources obtained through these channels continued to create valuable opportunities f or numerous students and new researchers to use the unique facilities present at the Radiation Center.
With respect to one of the Center's most visible programs, the reactor remained busy
_ and continued to be used about 90% of the available 45 hour work week. This use frequency is the maximum possible for a one-shift operation, in order to increase the
~
availability of' the reactor within-the limits of 'our present operating schedule, we encouraged simultaneous use of the reactor's numerous irradiation f acilities. As a result, c
h for the second consecutive year we experienced a 13% overallincrease in the time the reactor was used to support more than one project, which is a further indication of the growth in demand for reactor irradiation time at OSU. However, as in previous years,
< we occasionally were required to operate beyond our normal schedule to accommodate all of our requests _for irradiations.
L t
In the area of teaching, the Radiation Center's use also remained high as illustrated by
!=
1 f
the approximately.50 OSU classes which were accommodated using Center facilities.
About one half of these classes used the reactor and about 25% of the reactor's total 3
operating hours were in direct support of such classes.
This year we are especially pleased to note that the overall number of students involved in academic projects using the Radiation Center and reactor showed a 101% increase, t
1 l-
s 13 i
More significant, however, is the fact that this increase included a 108% increase in l
students from OSU. In addition, there was a 68% increase in the number of graduate l
C
~ student theses based on work accommodated by the Radiation Center.
Growth in the volume of research performed at the Radiation Center was also prominent
- 1..
again this year. Several key indications of this expanded research effort are the number of individual Radiation Center projects accommodated, which increased 26%; the-i number of funded research projects, which increased by 29%; and the number of shipments of radioactive material for use in research, which increased by 46%.
j A particularly notable addition to the Radiation Center's facilities this year was the l-
' purchase and installation of a 7000 curie cobalt 60 gamma irradiator. This new device l
will enable the Radiation Center to perform considerably higher dose gamma irradiations-in much shorter time intervals and will thus greatly improve our capability in this area.
We are very pleased to have this new irradiator and feel confident that it will see much use.. For example, even though the new gamma irradiator was not installed until the end-of the current reporting period, the number of cobalt 60 gamma irradiations last year still increased by 36%.
w The Radiation Center also continued to be a popular place to visit, particularly for high l-I_
schools, community colleges, an'd interested citizens. We again hosted nearly 900 visitors during the course of the year, j
\\
l Scholarly publications' involving:a contribution by the Radiation Center increased in L
number by about 5%, and there were 34 presentations at professional meetings where
' the Center supported the development of the research data being reported. Considering _
the publications currently in print, those presently submitted for publication, and those in,the final stages of preparation,-there have been approximately 118 total articles
]
generated during the 1989 90 reporthg period which involved a contribution by the -
- Radiation Center, s.
j
r l4 j
9 As a result of this past year's performance, we believe that the OSU Radiation Center
' has continued to enhance its image as a regional and as a nationally recognized
[ -'
~1nstructional and research facility, and we are gratified by the fact that the number of-institutions using the' Center continues to increase each year. This year the increase in user institutions was 15%; however, it is very important to note that this increased use-did not reduce the availability of any Radiation Center facilities, particularly the reactor, to OSU, students 'or researchers, in fact, the amount of reactor time used for OSU research showed a healthy 19% increase.
As a final note, we feel that it is very important to point out that there were no items of regulatory noncompliance and no emergencies or security events relating to the Radiation Center during this reporting peciod. Furthermore, all of the increased use of the-Radiation Center 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 Center once again showed that the Center and the i
reactor can be operated safely and within the international goal of keeping personnel 6-
, doses and releases of radionuclides as low as reasonably achievable (ALARA).
ll ee
-i '
l i
1 iC 1-o
h I5' i
1 1
H C.=
Introduction d-The current annual report of the Oregon State University Radiation Center and TRIGA Reactor follows the new expanded format by including information relating to the entire 6-Radiation Center rather than just the reactor. However, the information is still cresented in such a manner that data on the reactor may be examined separately if desired. It should be noted that reactor operating data in this report relate only to the FLIP-fueled core. For a summary of data on the reactor's original 20% enriched core the reader is i
l
+
1976-77 annual report if a referred to Table IV.A.2 in Part IV of this report, or to the more-comprehensive review is needed.
2 in addition to providing generalinformation about the activities of the Radiation Center, this report is designed to meet the reporting requirements of the U.S. Nuclear Regulatory l
' Commission, the U.S. Department of Energy, and the Oregon Department of Energy.
Because of this, the report is divided into several distinct parts so that the reader may
- easily find the sections of interest. An executive summary is also included for those
~
t already familiar'with the Radiation Center's operation.
t
?h '
t
'o t
\\
t h
O
t 1
16 D.- - Qverview'of the Radiation CentrJ k
6 The Radiation Center is a uniriue facility which serves the entire OSU Campus, all other institutions within the Oregon State System of Higher Education, and many other colleges and universities throughout the nation. The Center also regularly provides special services to state and federal agencies, particularly agencies dealing with law enforcement, energy, health, and environmental quality, and renders assistance to Oregon industry, in addition, the Radiation Center provides permanent office and
-laboratory space for the OSU Department of Nuclear Engineering, the OSU Radiation Safety program, the Institute of Nuclear Science and Engineering, and for the OSU' nuclear chemistry, radiation chemistry, and geo and cosmochemistry programs. There is no other university f acility with the combined capabilities of the OSU Radiation Center in the western half of the United States.
Located in the Radiation Center are major items of specialized equipment and unique teaching and research facilities. These include a TRIGA Mark 11 research nuclear reactor;
' two ccbalt 60 gamma irradiators; a 300 kVp X ray generator; a number of state of the-
- art 1 computer based.. gamma radiation spectrometers and T.ssociated germanium g
detectors; a neutron radiography facility capable of taking still or'very high speed radiographs; and a variety of instruments for radiation measurements and monitoring, j
Specialized facilities for radiation work include teaching and research laboratories with up to-date instrumentation and related equipment _for ~ performing neutron activation -
analysis and radiotracer studies: laboratories for animal and plant experiments involving -
radioactivity; a facility for repair and calibration of radiation protection instrumentation; and' facilities for' packaging radioactive materials for shipment to national and international destinations. Fjgure l.D.1 shows the layout of these facilities at the Radiation Conter.
The Radiation Center staff regularly provides direct support and assistance to OSU
!'L
' teaching and research programs. Areas of expertise commonly involved in such efforts -
[
include nuclear engineering, nuclear and radiation chemistry, neutron activation analysis, l 8I..
neutron radiography, radiation effects on biological systems, radiation dosimetry, i
l-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.
- ,n m w e'
i L
m j.7
)
- f s
r n_.
. h U
-M fin addition to formal academic and research support, the Center's staff provides a wide -
f 9
vanety of other services including public tours and public instructional programs, and -
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E.
' Summary of OSTR Environmental and Radiation Protection Data W
~
Year July 1,1989 1
1.
Liould Effluents Released (See Table V.B.1)
Throuch June 30,1990 o
a.
Total estimated quantity of radioactivity i
released (to the sanitary sewer)'
3.34 x 10 Curies 4
b.
Detectable radionuclides in the liquid waste
' H, 51Cr, "Co, esZn,75Se 1
- c. -
Estimated average concentration of released radioactive material at the point of release 2.59 x 10'5 Ci/cc i'
d.
Percent of applicable MPC for released 2
liquid radioactive material at the point 1.0%
3 i
l of release-0.03%
1'
(
- e. -
Total volume'of liqu:d effluent relcased, including diluent, which contained an OSTR contribution' 3415 gallons r: 3 1
s-a
- 1.,
i' a
',I L
s (1). :The OSU operational policy is to subtract only detector background' from our water analysis data and not background radioactivity in the Corvallis city water.
- (2); ' Based on values listed in 10 CFR 20, Appendix B, Table 2, Column 2.
a-(3)
Based on values listed in 10 CFR 20, Appendix B, Table 1, Column 2, aoolicable to sewer disoosal.
O-
-(4)
Total volume of effluent plus diluent does not take into consideration the additional mixing with the over 7,500,000 gallons per year of liquids and sewage normally
- discharged by the Radiation Center complex into the same sanitary sewer system.
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110 l
Year July 1,1989' l01 ' t; 2.
Airborne Effluents Released (See Table V.B.2)
Throuah June 30.1990
]
f-a.
Total estimated quantity of radioactivity released 6.5 Curies W/'
b.
Detectable radionuclides in the gaseous.
1 4' Ar (Th waste
= 1.83 hr) c.
Estimated average atmospheric diluted concentration of argon 41 at the point of release 4.1 x 10 8 Ci/cc J
d.
Percent of applicable MPC for diluted' i
concer...ation'of argon 41 at the point of release 1.0%
e.'
Total estimated release of radioactivity in-particulate form with' half lives 2
greater than 8 days None
{
Year July 1,1989
'3.
Solid Waste Released (See Table V.B.3)
Throuah June 30.10 -
i a.
Total amount of solid waste packaged and
-disposed of 15.0 ft 24Na, 48Sc,1 Cr, 54Mn, 51 b.
Detectable radionuclides in the solid' waste seCo, 58Fe,. 50Co, 52n, 7sgg,99Tc,124Sb', 2sSb, 13'l, 1 2Te,137Cs, 'd Ba,
(
La,
'4'Ce, is2
'4 Eu,
.is4Eu,182Ta
.j c.
. Total radioactivity in the solid waste 1.3 x 10'3' Curies l
b,
- (1)
Routine gamma spectroscopy analysis of the gaseous radioactivityin the stack discharge indicated-that it was virtually all argon 41.
[
~(2)'
Evaluation of the detectable particulate raoloactivity in the stack discharge confirmed its origin as naturally occurring radon daughter products, predominantly lead-214 and 1
bismuth 214, which are not associated with reactor operations.
i I
i
4 1
111 d-4 Radiation Exoosure Received by Personnel Year July 1,1989 H-(See Table V.C.1)1 Throuah June 30,199_Q a.
a.
Facility Operating Personnel (mrem)'
k'
-(1)
Average whole body 17 (2) ' Average extremities-47 (3)
Maximum whok body 135 (4)
Maximum extrem ' es 480 b'.
Key Facility Research Personnel (1)
Average whole body 2
(2)
Average extremities 10 (3) ' Maximum whole body 20 (4)
Maximum extremities.
210
...n, c.
' Physical Plant Maintenance Personnel (1)' Average whole body
<1 (2)
Maximum whole body 20 d.
Laboratory Class Students -
4 (1)
Average whole body 0
-=
(2)' Average extremities.
5-
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(3)' Maximum whole body 0
- (4)
Maximum extremities 120 i
Le.
Campus Police and Security Personnel (1)
Average whole body 3
(2)
. Maximum whole body-0 f,'
Visitors
~,
(1)
Average whole body
<1 (2)
Maximum whole body 8
I 4
\\%
\\'.
A-(1)
"0" indicates that each of the beta gamma dosimeters during the reporting period was less than the vendor's gamrna dose reporting threshold of 10 mrem or that each of the l
neutron dosimeters was less than the vendor's threshold of 30 mrem, as arplicable.
i l
l.
i 112 i
Qi 5.
Number of Routine Onsite and Offsite Year July 1,1989 3
Monitorina Measurements and Samoles Throuah June 30.1990-
.}
i m
k1
- a.
Facility Survey Data K
(1)
Area Radiation Dosimeters (Soo Table V.D.1)
(a)
Beta gamma dosimeter measurements 136 x
(b)
Neutron dosimeter-measurements 48 (2) - Radiation and Contamination Survey Maasurements (See Table V.D.3).
-6000 b.
Environmental Survey Data (1)
Gamma Radiation Monitoring (See Tables
- V.E.1 and V.E.2)
[I
'(a)
Onsite monitoring
-- OSU TLD monitors 108
--- Radiation Detection Co. TLD monitors 72
- Monthly. R/hr measurements 108 (b)' Offsite monitoring
-- OSU TLD monitors -
264 l
-- Radiation Detection Co. TLD monitors 104
. Monthly R/hr-measurements -
252 (2)
Soil, Water and Vegetation Surveys
. (See Table V.E.3)
(a). Soil samples 16 (b) -- Water samples 16
.-(c)
' Vegetation samples-56 i
r 4
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1-13 F.
History e;
A brief chronology of the key dates and events in the history of the OSU Radiation Center and the TRIGA reactor is given below:
J,
' June 1964 Completion of the first phase of the Radiation Center, consisting of l
y 32,397 square feet of office and laboratory space.
July 1964 Transfer of the 0.1 W AGN 201 reactor to the Radiation Center. This reactor was initially housed in the Mechanical Engineering Department
'i and first went criticalin January of 1959.
Oct.~ 1966
. Completion of the second phase of the Radiation Center, consisting of 9,956 square feet of space for the TRIGA reactor and associated laboratories and offices.
- March 1967 Initial criticality of the Oregon State-TRIGA Reactor (OSTR). The reactor was licensed to operate at a maximum steady state power level
[
'of 250 kW, and was fueled with 20% enriched fuel.
August 1969
.OSTR licensc110 operate at a maximum steady state power of 1 MW, t
y but could do so oaly for short periods of time due to lack of cooling.
capacity.
June.1971
'OSTR cooling capacity upgraded to allow-continuous operation at 1 p;
MW.
. April -1972 OSTR Site Certificate issued by the Oregon Energy-' Facility Siting Council.
Sept.1972 -
OSTR area fence installed.
Dec.1974-AGN 201 reactor permanently shut down.
4 March.1976 Completion of 1600 square feet of additional space to accommodate the rapidly expanding nuclear engineering program.
j:
July 1976
'OSTR refueled with 70% enriched FLIP fuel.
~
i
' July 1977-Completion of a second 1600 square feet of space to bring the 0
Radiation Center complex to its current total of 45,553 square feet.
T-Jan.1980 Major upgrade of the electronics in the OSTR control console.
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- June 1982'
. Shipment of the original 20% enriched'OSTR fuel to Westinghouse 7
Hanford Corporation.
t w
Dec.1988-
- . AGN 201 components transferred to Idaho State Univusity for use in.
j e
their' AGN 201 reactor program.
'N4 M
-g.
-June,1990 J Installation'of a 7000 CI ' Co Gammacellirradiator.
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PART11 o
PEOPLE k
This part contains a listing of all people who were residents.1 the Radiation Center or who worked a significant amount of time at the Center during this reporting period. Sections A, E and C list the academic staff, trainees and students, while sectionr. D through G give the Radiation Center's operating staff. Section H shows the OSU Radiaticn Safety Office staff and section I provides the ecmposition of committees involving Center personnel.
it should be noted that not all of the faculty and students who used the Radiation Center for their teaching and research are listed :n this part. Summary information on these people is given in Table VI.C.1, and individual names and projects are listed in Tables VI.C.2 and VI.C.3.
A.
Eaculty
=
' Johnson, Arthur G.
Director, OSU Radiation Center l
Jirector, OSU Institute of Nuclear Science and Engineering Professor of Nuclear Engineering and Radiation Health
- Binney, Stephen E.
Associate Professor of Nuclear Engineering i.
Chairman, OSTR Reactor Operations Committee
'Conrady, Michael R.
i Research Assistant Neutron Activation Analysis Specialist
'Cordell, Sharon M.
Research Assistant Radiation Protection Technologist l
1 Daniels, Malcolm Professor of Chemistry
'Dodd, Brian Reactor Administrator Professor of Nuclear Engineering
' Reactor users for research and/or teaching.
C k
l
1 61 2 i,.
Hart, Lucas P.
Research Associate, Chemistry t,
'Higginbotham, Jack F.
Senior Health Physicist Assistant Professor of Nuclear Engineering a
Klein. %ndrew C.
Assi!tr.t Professor of Nuclear Engineering
'Loveland, Walter D.
Professor of Chemistry MacVicar, Robert President Emeritus, OSU Maki, Leonard M.
Professor of Nuclear Engineering (Visiting)
'Pastorek, Christine Instructor of Chemistry Popovich, Milosh Vice President Emeritus, OSU l
t
'Pratt, David S.
Research Assistant Health Physicist Rey 9s, Jose N.
Assistant Professor of Nuclear Engineering
- Ringle, John C.
Professor of Nuclear Engineering Associate Dean of the Graduate School, OSU
' Robinson, Alan H.
Head; Department of Nuclear Engineering Professor of Nuclear Engineering
'Schmitt, Roman A.
I Professor of Chemistry l
I 6
l
- t
' Reactor users for research and/or teaching, i
i i
)
11 3
'Welker, Robert J.
Research Assistant Neutron Activation Analysis Specialist Wang, Chih H, Professor Emeritus, OSU f
L C
c
\\
- Reactor users for research and/or teaching.
I l-l14 8
8.
Vialting Scientists and Soecial Trainees p..
4 Advisor or Research
=
MatDg Field (Af filiation)
Procram Director P
' Abdur, Rahman Nuclear EnQ neering A. H. Robinson i
p (Bangladesh)
Behm, Marten -
Nuclear Chemistry W. D. Loveland (Sweden)
' Collins, Derek Oregon Episcopal School J. F. Higginbotham E
(Portland, Oregon)
. Yokoyama, Akihiko -
Nuclear Chemistry W. D. Loveland (Japan) h, O. l il.
e i
k o1 i
n, r
~
f
~
" Reactor users for research and/or teaching,
'l i
e
+
..-.m
.m.,
11 5 C.
OSU Graduate Students b
9 Degree Name Proaram f.ifj.d Advisor Al-Baroudi, Homan PhD Nuclear Engr.
A. C. Klein b
Ala, Abbas PhD Nuclear Engr.
J. N. Reyes Almarshad, Abdullah PhD Nuclear Engr.
A. C. Klein Almasoumi, Abdullah PhG Nuclear Engr.
S. E. Binney Anand, Ajay PhD Nuclear Engr.
S. E. Binney Baik, Seung-Hyuk MS Radiation Health J. F. Higginbotham Bukar, Kyari A.
MS Nuclear Engr.
A. H. Robinson Cho, Byung Oh MS Nuclear Engr.
A. H. Robinson Eichenberg, Thomas W.
MS Nuclear Engr.
J. N. Reyes Fu, Yingxian MS Chemistry M. Daniels
- Greek, Kevin PhD Nuclear Engr.
A. H. Robinson Greene, Kenneth _
PhD Nuclear Engr.
A. H. Robinson Gulshan-Ara, Zubaida MS Nuclear Engr.
A. C. Klein Heaberlin, Joan PhD Nuclear Engr.
A. H. Robinson Hicks, Thomas MS Radiation Health B.Dodd
' Hill, Esrittain E.
PhD Geosciences E. M. Taylor Jordheim, Daniel P.
MS Nuclear Engr.
S. E. Binney King, John MS Nuclear Engr.
J. N. Reyes Lafi, Abd Y.
PhD Nuclear Engr.
J. N. Reyes Lee, Hsing H.
MS Nuclear Engr.
A. C. Klein Lewis, Bryan R.
MS Nuclear Engr.
A. C. Klein a
- Liu, Yung Gang PhD Chemistry R. A. Schmitt Marks, Tim
_MS Nuclear Engr.
A. C. Klein 3-Miles, Todd L.
MS Nuclear Engr.
S. E. Binney Pauley, Keith MS Nuclear Engr.
A. C. Klein l
Pawlowski, Ronald MS Nuclear Engr.
A. C. Klein Piepmler, Edward H.
PhD Pharmacy J. W. Ayres
- Pratt, David MS Radiation Health A. G. Johnson i
l Reardon, Michael F.
MS Nuclear Engr.
S. E. Binney Saleh, Hassan PhD Nuclear Engr.
S. E. Binney
- Schilk, Alan J.
PhD Chemistry R. A. Schmitt Van Winkle, James A.
MS Nuclear Engr.
A. C. Klein
' Walker, Robert J.
PhD Geosciences C. W. Field
'Yousef, Samir MS Radiation Health J. F. Higginbotham l
Zahm, Lance MS Nuclear Engr.
A. C. Klein s
6=
- Reactor users for research and/or teaching.
11 6 D.
Business Administrative and Clerical Staff Director A. G. Johnson Business Manager S. C. Campbell Administrative Assistant E. C. Flickinger D. K. Dalton a
Office Specialists J. F. Hopkins J. R. Smith Custodian M. L. Benad Office Coordinator (Nuclear Engineering)
D. L. Cramer Word Processing Specialist (Nuclear Engineering)
R. A. Keen
. E.
Reactor Operations Stati Principle Security Officer A. G. Johnson Reactor Administrator, Senior Reactor Operator B. Dodd i
Reactor Supervisor, Senior i
i Reactor Operator T. V. Anderson Senior Reactor Operators S. E. Binney l
J. F. Higginbotham I
Reactor Operator A. D. Hall e
F.
Radiation Protection Staff Senior Health Physicist J. F. Higginbotham l
Health Physicist D. S. Pratt l
Radiation Protection Technologist S. M. Cordell i
Health Physics Monitors (Students)
D. Cook A, Evans C. Grier V. Meacham N. Moreno 1
C.Rak S. Reese i
E. Rockett J. Starr C. Vostmeyer 3
Il 7 G.
Scientific Suncort Staff j
o-
- o.-
Senior Neutron Activation Analyst R. A. Schmitt l.'
Neutron Activation Analysis Specialists M. R. Conrady i
l R. J. Walker l
l*
4 Neutron Activation Analysis b
Technicians (Students)
T. Berkman l
A. Mathis l
E. Schuefort i
M. Streck Scientific Instrument Technicians H. L. Busby S. P. Smith i
r H..
OSU Radiation Safety Office Staff
_ Tit [g Name J
Radiation Safety Officer G. A. Little Acting Radiation Safety Officer l
(May 15,1990 - June 30,1990)
R. H. Farmer
. Radiation Specialists D. L. Harlan Secretary
.K. L. Miller o.
I.
?
k t
i i
5 q
A O
k
?6 Y l
-r h
i-l L
i
ll 8 1.
Committees o
4 1.
Reactor Ooerations Committee Name Affiliation p
D S. E. Binney, Chairman Nuclear Engineering D. L. Amort Electrical and Computer Engineering T. V. Anderson Radiation Center B. Dodd Radiation Center and Nuclear Engineering J. F. Higginbotham Radiation Center and Nuclect Engineering A. G. Johnson Radiation Center and Nuclear Engineering J. C. Ringle Nuclear Engineering and Craduate School A. H. Robinson Nuclear Engineering R. A. Schmitt Chemistry and Radiation Center W. H. Warnes Mechanical Engineering 2.
Radiation Safety Committee (OSU)
Name Affiliation G. Merrill, Chairman Biochemistry / Biophysics R. Collier Oceanography J. Higginbotham Radiation Center and Nuclear Engineering D. Keszler Chemistry S. Radosevich Forest Science C. Rivin Botany and Plant Pathology 6
G. Rohrmann Agricultural Chemistry C. Schreck Fisheries and Wildlife G. Little, Secretary & RSO Radiation Safety Office 3.
Radiation Center Safety Committee Np_mne Affiliation r
W. D. Loveland, Chairman Chemistry T. V. Anderson Radiation Center H. L. Busby Radiation Center S. C. Campbell Radiation Center M. R.-Conrade Radiation Center J. G. Higgirbotham Radiation Center and Nuclear Engineering j
A. G. Jo' nson Radiation Center and Nuclear Engineering o
i.
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FACILITIES A.
Research Reactor
=
3 1.
Descriotion The Oregon State University TRIGA Reactor (OSTR)is a water-cooled, swimming pool type of research reactor which uses uranium / zirconium hydride fuel elements in a circular grid array. The reactor core is surrounded by a ring of graphite which j
serves to reflect neutrons back into the core. The core is situated near the bottom of a 22 foot deep water filled tank, and the tank is surrounded by a concrete bioshield which acts as a radiation shield and structural support. See Figures lil. A.1, Ill. A.2 and Ill.A.3.
The reactor is licensed by the U.S. Nuclear Regulatory Commission to operate at a maximum steady state power of 1.1 MW, and can also be pulsed up to a peak power of about 3000 MW.
O The OSTR has a number of different irradiation facilities including a pneumatic
[
transfer tube, a rotating rack, a thermal column, four beam ports, two sample-holding (dummy) fuel elements for specialin core irradiations, and a cadmium lined in-cora irradiation tube for experiments requiring a high energy neutron flux.
The pneumatic transfer facility enables samples to be inserted and removed from the core in a few seconds Consequently, this facility is normally used for neutron activation analysis involving short lived radionuclides. On the other hand, the rotating rack is used for much longer irradiation of samples (e.g., hours). The rack consists of a circular array of 40 tubular positions, each of which can hold two sample tubes. The rotation of the rack ensures that each sample will receive the i
o same amount of irradiation.
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111 5 i
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The reactor's thermal colurnn consists of a large stack of graphite blocks which slow down neutrons from ti.e reactor core in order to increase thermal neutron activation of samples. Graphite blocks are removed from the thermal column to 1
C i
D enable samples to be positioned inside for irradiation.
The beam ports are tubular penetrations in the reactor's main concrete shield which enable neutron and gamma radiation to stream from the core when a beam port's shield plugs are removed. Two of the OSTR's beam ports are permanently configured for neutron radiography while the other two may be used for a variety of experiments.
If samples to be irradiated require 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 i
would normally be occupied by a fuel element.
o The cadmium lined in core irradiation tube enables samples to be irradiated in a high flux region near the center of the core. The cadmium lining in the facility eliminates thermal neutrons and thus permits sample exposure to epithermal neutrons only. The cadmium-lined end of this air filled aluminum irradiation tube is inserted into an inner grid position of the reactor core which would normally be occupied by a fuel element.
2.
Utilization The two main uses of the OSTR are instruction and research. During this reporting period, the reactor was in use an average of 40 hours during a typical 45 hour work week. Hence, the reactor was used approximately 90% of the available time.
lo.
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l6 a.
Instruction 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 performed for many undergraduate students in physics, chemistry and biology classes, as well as for visitors from other universities and colleges, from high schools and from public groups.
The second instructional application of the OSTR involves education of reactor operators, operations managers, and radiation health physicists. The OSTR is in a unique position to provide such education since curricula must o'
include hands on experience at an operating reactor and in associated laboratories. The many types of educational programs that the Radiation j
Center provides are more 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 utilized 245 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.
o-b.
Research P
q The OSTR is a unique and valueale tool for a wide variety of research applications, and serves as an excellent source of neutrons and/or gamma r
radiation. The most popular experimental technique requiring reactor use is t
j
lil 7 Table Ill.A.1 OSU Courses Using the OSTR c
?
Course Number Course Name NE 111X Nuclear Engineering Orientation NE 112X Nuclear Engineering Orientation NE 203 Nuclear Radiation Detection and Measurement NE 405A Field Practices in Radiation Protection (Undergraduate)
NE 406D Design Projects (Nuclear Engineering)
NE 441 Nuclear Reactor Experiments NE 461 Radiation Protection Engineering NE 503 Thesis (Nuclear Engineering)
NE 505A Field Practices in Radiation Protection (Graduate)
CH 106 General Chemistry Laboratory CH 107 General Chemistry Laboratory CH 202 General Chemistry CH 207 General Chemistry Laboratory CH 419 Radioactive Tracer Methods CH 461 -
Experimental Chemistry 11 o'
CH 503 Thesis (Chemistry) i CH 528 Activation Analysis I
H 170 Personal Health-1 H S44 Man, Health, and Environment G 503 Thesis (Geology)
ME 503 Thesis (Mechanical Engineering)
' OC 503 Thesis (Oceanography)
PH 503 Thesis (Physics) w 6
'e
111 8 Table Ill.A.2 O
OSTR Teaching Hours I
Annual Cumulative Values for Values for July 1,1989 August 1,1976 Description Through Through June 30,1990 June 30,1990 (hours)
(hours)
Departmental 168 2804 Nuclear Engineering 113 Chemistry 49 Health & Human Performance 6
y 03 Geology 0
Mechanical Engineering '
i Oceanography 03 Physics '
i 0
t2 Special Classes and Projects '
77 435 Total Teaching Hours' ^5' 245 3239 e
(1) Use hours by these departments are not shown under " Teaching Hours," but are reflected I
under Thesis Research, both funded and unfunded.
(2) A variety of educational classes were conducted which involved one time meetings for orientation or support purpores. These included: high school science classes, new student 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 use categories.
(5) Total teaching hours reflect all time the reactor was in use for teaching, and because of this the total hours include time the reactor itself may not actually have been in operation.
1 i
k..
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111 9 I
neutron activation analysis (NAA). This is a particularly sensitive method of l
elemental analysis which is described in more detail in Part VI (section VI.C.1 ).
Part Ill.B provides a listing of equipment used in NAA at the b-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 anthropologicci materials.
During this reporting period, the OSTR accommodated 102 funded research projects which utilized 1096 hours of reactor time, and 16 unfunded research projects which utilized 76 hot's of reactor time. Details of the reactor's use specifically for research are given in Table Ill.A.3. Additionel information regarding reactor use for research, thesis and service can be b
found in Tables VI.C.1 through VI.C.3. In these tables OSTR use is indicated with an asterisk.
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Table Ill.A.3 OSTR Research Hours
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(
Annual Cumulative f
Values Values for for g
-Types of Research July 1,1989 August 1,1976 Through Through J
30,1990 June 30,1990 Inours)
(hours)
OSU Research 461 6243 Off Campus Research 711 3620 Total Research Hourso n2' 1172 9863 (1)
. Total research hours statistics:
1 o
(a):
94 % (1096 hours) of the total research hours were user funded by federal,
'l state, or other organizations.
O (b) 6% -(76-hours) of the total research hours were user 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' off-campus research hours OSTR recorded, nearly 7% (approximately. 50 hours) were in
_ direct support of research being conducted at the University of Oregon.
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8.
Analytical Enuloment 31 1.
Descriotion The Radiation Center has a great variety of radiation detection instrumentation.
i_.
Much of this equipment involves the latest in counting technology as represented
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by the fourteen state of the art gamt.'a ray spectrometers with their associated computers and Ge(Li) or intrinsic germanium detectors. Tables Ill.B.1 through lit.B.3 provide a brief listing of typicallaboratory counting devices present at the f
h:
Center. Much additional equipment for use in the classroom, and an extensive inventory of portable radiation detection instrumentation are also available.
2.
Utilization Radiation Center nuciear instrumentation receives intensive use in both teaching and research applications. In addition, service projects also use these systems and L
the combined use often results in 24 hour per day schedules for many of the l
analytical _ instruments.- Use of Radiation Center equipment extends beyond that 4
' located at the Center and instrumentation is commonly made available on a loan U
basis to OSU researchers in other departments.
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11112 ja Table Ill.B.1 Radiation Center Spectrometry Systems:
Gamma, Low Energy Photon, Alpha Rel. Effic.
Room System
(%)
B100 Adcam 1,8k Ortec, Ortec HP Ge 26.8 B100 Adcam 2,8k Ortec, PGT Ge(Li) 13.0 B100 Adcam 3,8k Ortec, Canberto Ge(Li) 19.4 B100 Adcam 4,8k Ortec, PGT Ge(Li) 13,2 Float Adcam 5,8k Ortec, Backup Analyzer N/A C126 Ace 1,4k Ortec, Nal(TI) 3x3 N/A C123 Ace 2,4k Ortec, PGT Ge(Li) 18.7 C126 2 K, ND60, Na!(TI) 3x3 N/A
'O O
A138 H.P. Scaler, Nal(TI) 2x2 N/A A146 Ace,4k Ortec, Ortec HP Ge 30.0 0-0-
A146 Ace,4k Ortec, Ortec Ge(Li) 27.0 C134 4x4 k ND Micro MCA, PGT Ge(Li) 16.2 s
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 Ortec,576A Alpha Spectrometer N/A 4
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I h-Table 111.B.2 Radiation Center Liquid Scintillation Counting Systems b
Room System C126 Beckman, Betamate C126 Beckman, Betamate C126 Beckman, Betamate C126 Beckman, Betamate i
B136 Beckman, LS 7500 j
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Radioisotooe Irradiation Sources a
1.
Descriotion The Radiation Center is now equipped with two cobalt 60 gamma irradiation facilities which are capable of delivering high doses of gamma radiation to a wide a
variety of materials. During June 1990 a new Gammacell 7000 Ci cobalt 60 gamma irradiator was installed at the Radiation Center. This is a significant new facility which considerably expands the useful range of gamma doses available to researchers. The new irradiator will provide dose rates of the order to 900 krad/h compared to about 18 krad/h delivered by the old Budd irradiator. These two irradiators complement each other, so that the one which delivers the most appropriate dose rate for a particular experiment will be used.
Typically, the irradiators are used by researchers wishing to perform mutalian 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 damage studies, and other such applications. In addition to the a
cobalt 60 irradiator, the Center is also equipped with a variety of smaller cobalt 60, cesium 137, radium 226, plutonium beryllium,andotherisotopicsealed sources of various curie levels which are available for use as irradiation sources.
p 2.
Utilization During this reporting period there was a diverse group of projects using the cobalt 60 irradiator. These projects included the irradiation of a variety of biological cells as well as the irradiation of flowers, seeds and leaves, in addition, the irradiator was used for radiation dosimeter analysis, soil sterilization, and materials evaluation. Data showing uses of the irradiator for this reporting period are given in Table Ill.C.1.
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l 11118 Table lil.C.1 Cobalt 60 Irradiator Use Purpose of Dose Range Number of Use Time Irradiation Samples (rads)
Irradiations (hours) 5 9x10 5x10' 10 5626 Sterilization Soil 2x10 1.1x10' 6
15 3
BotarJe91 Onion Studies flowers, bean seeds, quince leaves 3
8 Biological Collagens, 1x10 4.5x10 58 795 Studies spleen cells,-
dried protein,
- bacteria, culture Dosimeter TLDs, other 35 - 3x10 36 44 Analysis dosimeters 5
8 Materials Wood, golf 3x10 - 1.6x10 10 1080 o~
Evaluation balls TOTALS 120 7560 L
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1 til 19 D.
X Rav Machine 1.
Descriotion A General Electric Maxitron 300 kVp X Ray generator is located in the Radiation Center. This davice is situated in a shielded roorn which is large enough to accommodate a wide variety of experiments. The machine is capable of operating at 300 kVp and 20 mA, and devices for calibrating the beam intensity are available.
2.
Utilization The X Ray machine continued to be used as a radiation sourco where students could perform state required radiation surveys of a fixed X ray machineinstallation and carry out other safety checks required for such a facility.
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I 111 20 E.
Laboratories and Classrooms 1.
Descriotion The Radiation Center is equipped with a number of different radioactive materials laboratories designed to accommodate classes offered by various OSU academic 7
1 departments or off campus groups, i
instructional facilities available at the Center include a laboratory especially equipped for teaching radi0 chemistry and two nuclear instrumentation teaching laboratories equipped with modular sets of counti".g equipment which can be
- configured to accommodate a variety of experiments involving the measurement of many types of radiatian. The Center also has two student computer rooms equipped with microcomputers and terminals which are linked to other computers, both on and off campus.
-In addition to these dedicated instructional facilities, many other research laboratories and pieces of specialized equipment are regularly used for teaching.
C In,particular, classes are routinely given access to appropriate state-of-the art y
gamma spectroscopy equipment located in Center i boratories. A number of
- f classes also regularly use the reactor and the reactor bay as an integral part of i
,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 e
suitable for graduato classes and thesis examinations. As a service to the student body, the Radiation Center also provides a stud ant study room / lounge as well as an office area for the student chapter of the.4merican Nuclear Society.
This reporting period saw the beginning of a new thermal hydraulics laboratory in the space previously used by the AGN reactor. This laboratory is being developed a
by a member of the nuclear engineering faculty and involves the construction of several scale loops to meet.ne research needs of the nuclear industry.
)
i 111 21 2.
Utilization All of the laboratories and classrooms are used extensively during the academic
-t year. For example, a listing of 50 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 l
I by the reactor during the reporting period. in addition, several laboratories are-used for research projects throughout the year, e
D 4
o
-1 e-i y..
k 4
4-
+
e.
lll 22 Table Ill.E.1 Student Enrollment in Nuclear Engineering and Nuclear Science Courses Which Are Taught or Partially Taught at the Radiation Center p
Number of Students y
Course Credit Course Title Fall Winter Spring 1989 1989 1990 Nuclear Engineering Courses j
'NE 111X 3
Introduction to Nuclear Engineering 18
'NE 112X
'3 Introduction to Nuclear Engineering 14
~
i l'
NE 103 3
Intro. Nuclear Engineering & Comp.
11 NE 201 3
Nuclear Energy Fundamentals 21 NE 202 -
3 Nuclear Radiation and Matter 18
'NE 203 3
Nuclear Radiation Detection & Measurement 17 NE 361X 3'
Nuclear Reactor Systems 12
'NE 405A+
13 R&C/ Field Practice Radiation Health 1
NE 406 16 Projects.
1 2
- *NE 406D 16 Individual Design Project 5
10 3
NE 407 1
Seminar 10 11 9
NE 415 4
Principles of Radiation Safety 18 NE 421 3
Nuclear Reactor Analysis & Computation 10 l
NE 422 3
Nuclear Reactor Analysis & Computation 11 NE 423 3
Nuclear Reactor Analysis & Computation 12 NE 430 3
Nuclear Fuel Cycle 26 NE 431 3
Reactor Thermal Hydraulics 12 NE 432 3
Nuclear Reactor Design 13 c;
NE 433 3
Nuclear Reactor Design 13 NE 434 3
Nuclear Reactor Design 12
NE 441 3
Nuclear Engineering Experirnents 11
- NE 461 3
Radiation Protection Engineering 16 3
o.
NE 465
. 3 Nuclear Rules & Regulations 14
- NE 501.
1 15 Research 3
- *NE 503 1 15 Thesis 16 17 14 i
NE 505 1 15 Reading & Conference 1
1
'NE 505A -
1-3 R&C/ Field Practice Radiation Health 1
NE 506 1-15 Projects 1
1 3
NE 507 1
Seminar -
3 1
NE 511 3
Neutron Transport Theory 8
l NE512 3
Advanced Nuclear Reactor Theory 8
l
'NE 532 3
Advanced Nuclear Reactor Design 3
NE 533 3
Advanced Nuclear Reactor Design 3
NE 534 3
Advanced Nuclear Reactor Design 3
i I
NE 542 3
Advanced Thermal Hydraulics 10 NE 581N 3
ST/ Advanced Numerical Techniques 1
= NE 583W 3-ST/ Radioactive Waste Management 16 NE 589X 3
ST/ Radioactive Matenal Transport 9
o fu i
D..
l
11123 Table lit.E.1 (Continued)
Number of Students Course
. Credit Course Title Fall Winter Spring a.
1989 1989 1990
?
Chemistry Courses
'CH 106 +
5 General Chemistry 33
'CH 107 2
General Chemistry Lab 8
52
'CH 202' 3
General Chemistry
'CH 207 2-General Chemistry Lab 6
- CH 419 -
4 Radioactive Tracer Methods
'CH 461 3
Experimental Chemistry 24
'CH 503 1 16 Thesis (Chemistry)
- *CH 528 4
l Activation Analysis Other Courses
'G 503 1 16 Thesis (Geosciences) 3 3
3
'ME 503.
1 16 Thesis (Mechanical Engineering) 1 1
1
'OC 503 1 16 Thesis (Oceanography) 1 1
1
'PH 503 1-16' Thesis (Physics) 4 4
4
'OSTR used occasionally for demonstration and/or experiments.
- *0STR used heavily, t
+ Class held Summer Term 1989, o.
i d'
t I
e s-S
lll 24 F.
Instrument Reoair and Calibration Facility a
1.
Descriotion The Radiation Center has a facility for the repair and calibration of essentially all o
types of radiation monitoring instrumentation. This includes instruments for the detection and measurement of alpha, beta, gamma and neutron radiation, and e7 compasses both high range instruments for measuring intense radiation fields and low range instruments used to measure environmentallevels of radioactivity.
The Center's instrument calibration capability is described more completely in Section VI.C.7 of this report.
I 2.
Utilization The Center's instrument repair and calibration f acility is used regular'y throughout each year and is absolutely essential to the continued operatior of the many different programs carried out at the Center, in addition, the tbsence of any comparable facility in the state has led to a greatly expanded instn, ment calibration program for the Center, including calibration of essentially all adiation' detection I
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 I.
Health Division's Radiation Control Section, the Oregon Department of Energy, the L
Oregon Public Utilities Commission, the U.S. Environmental Protection Agency, the U.S. Bureau of Mines, and the U.S. Forest Service.
Additional information regarding instrument repair and calibration efforts, is given in Tables VI.C.4 and VI.C.5.
lo 1
ll
11125 G;
Mbraries 1.
Qngriotion The Radiation Center has libraries containing significant collections of texts, research reports, and videotapes relating to nuclear science, nuclear engineering, j
and radiation protection.
The Radiation Center is also a regular recipient of t, great variety of publications from commercial 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. Therefore,_ Center libraries maintain a current collection of leading research and regulatory documentation in the nuclear area, in addition, the Center has a collection over 50 sets of nuclear power reactor safety _ analysis and environmental reports specifically prepared by utilities for their facilities.
The Center maintains an up-to date set of reports from'such organizations as the -
c --
International Commission on Radiological Protection, the National Council on Radiation Protection and Measurements, and the International. Commission on
- l
. Radiological Units. Sets of the current U.S. Code of Federal Regulations for the g
U.S. Nuclear Regulatory Commission, the U.S. Department of Transportation and other appropriate federal' agencies, plus regulations of various state regulatory agencies 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 uses videotapes for most of the technical orientations which.
are required for personnel working with radiation and radioactive materials. These tapes are produced, recorded and edited by Radiation Center staff, using the e'
Center's videotape equipment and the facilities of the OSU Communication Media Center.
4 b
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11126' r
ni is
- 9
- F e
2.
Utilization
.=
ld Radiation Center libraries are use'd mainly to provide reference material on.an -
t
-,as needed basis: however, they receive extensive use during the academic year.
[
1-il in addition, the orientation videotapes are used intensively'during the beginning of 9;
each term, and periodically thereaf ter.
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PART IV REACTOR o
os A.
Operatino Statistics For the current reporting period, the operating statistics for the OSTR remained stable at a high reactor use rate. Coerating data by individual category are 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 42.2 megawatt days (MWD). The cumulative thermal energy generated by the FLIP core now
. totals 486.4 MWD from August 1,1976 through June 30,1990. Reactor use time-averaged approximately 90% of the normal nire-hour, five day per week schedule.
Tables IV.A 3 through IV.A 6 detail the operating statistics applicable to this reporting period.
e O-The reactor core excess reactivity remained about the same during the current reporting n
period even though a number of significant changes occurred in the core. These w
changes and their contributions to reactivity change are listed below.
1.
Consumption of the erbium burnable poison in the fuelincreased reactivity.
2.
Removing a fuel element because of cladding deformation decreased reactivity, and installation of a new replacement fuel element increased reactivity.
3.
Fuel burnup decreased reactivity.
4.
Installation of a new transient rod to replace the original one increased the rod worth but decreased excess reactivity.
e lb le 1
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.,w Table IV.A.1 OSTR Operating Statistics (Using the FLIP Fuel Core) for the Period August 1976 -June 1984 Operational Data August 1,1976 July 1,1977 July 1,1978 July 1,1979 July 1,1980 July 1,1981 July 1.1982 July 1,1983 for Through Ttwough Through Through Tirough Through Through Ttwough FLIP Core June 30,1977m June 30,1978 June 30,1979 June 30,1980 June 30,1981 June 30,1982 June 30,1983 June 30,1984 Operating Hours 875
-819 458 875 1255 1192 1095 1205 (critical)
Megawatt 451 496 255 571 1005 999 931 943 Hours Megawatt 19.0 20.6 10.6 23.8 41.9 41.6 38.8 39.3 Days Grams '*U 2
Used 24.0 25.9 13.4 29.8 52.5 52.4 48.6 49.3 Hours at Full Power 401 481 218 552 998 973 890 929 (1 MW)
Numbers of Fuel Elements 85 0
2 0
0 1
0 0
Added or Removed (-)
Numtier of irradiation 44 375 329 372 348 408 396 469 Requests (1) The reactor was shutdown on July 26,1976 for one month in order to completely refuel the reactor with a new FLIP fuel core.
m
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Table IV.A.1 (continued)
' OSTR Operating' Statistics (Using the FLIP Fuel Core) for the Period July 1984 - June 1990 Operational Data July 1,1984 July 1,1985 July 1,1986 July 1,1987 July 1,1988 July 1,1989 July '1,1990 l July 1,1991 for Through
~ Through Through Tivough -
Through Through Through
' Through FLIP Core June 30,1985 June 30,1986 June 30,1987 June 30,1988 June 30,1989 June 30,1990 June 30,1991 June 30,1992 Operating Hours 1205 1208 1172 1352
-1170 1136 (critical)
Megawatt 946 1042 993 1001 1025 1013 Hours Megawatt 39.4 43.4 41.4 41.7 42.7 42.2 Days Grams u
49.5 54.4 51.9 52.3 53.6 53.0 23e Used Hours at Full Power 904 1024 980 987 1021 1009 (1 MW)
Numbers of Fuel Elements 0
0 0
-2*
O
-1, + 1
- Added or Removed (-)
Number of inadiation 407 403 387 373 290 301 Requests (1) No fuel elements were added, but one fueled follower control rod was replaced.
(2) Two fuel elements were removed due to cladding deformation.
(3) One fuel element removed due to cladding' deformation and one new fuel element arAed.
2 th 1.
-u 6-4
=
.+.
6 s.
- 0.:
e Table IV.A.2 OSTR Operating Statistics with the Original (20% Enriched) Standard TRIGA Feel Core TOTAL:
Operational Data Mar 8,67 Jul 1, 68 Jul 1, 69 Apr 1,70 Apr 1,71
. Apr 1, 72 Apr 1, 73 Apr 1,74 Apr 1, 75 Apr 1,76 for 20%
Through Through Ttwoogh Tivough Through Ttwough Ttrough Ttwough Through Tiwoogh March 67 Enriched Jun 30,68 Jun 30,69 Mar 31,70 Mar 31,71 Mar 31,72 Mar 31,73 Mar 31,74 Mar 31,75 Mar 31,76
. Jul 26, 76 Through (4)
July 76 Core (1)
(2)
(3)
Operating Hours 904 610 567 855 598 954 705 563 794 353 6903 (criticall Megawatt 117.2 102.5 138.1 223.8 195.1 497.8 335.9 321.5' 408.0 213.0 2553.0 Hours Megawatt 4.9 4.3 5.8 9.3 8.1 20.7 14.1 13.4 17.0 9.0 106.4 Days Grams u
6.1 5.4 7.2 11.7 10.2 26.0 17.6 16.8 21.4 10.7 133.0 23e Used Hours at 856 Full Power 429 369 58 (250 kW)
Hours at Full Power 20 23 100 401 200 291 460 205 1700 (1 MW)
Number of Fuel Elements 70 2
13 1
1 1
2 2
2 0
94 A.dded to (Instial)
Core Number of irradiation 429 433 391 528 347 550 452 396 357 217 4100 Requests Ntrnber of 202 236 299 102 98 249 109 183 43 39 1560 Pulses (1)
Reactor went critical on March 8,1967 (70 element core; 250 kW). Note: This period length is 1.33 years as initial criticality occurred in March of 1967.
(2)
Reactor shut down August 22,1969 for one month for upgrading to 1 MW (did not upgrade cooling system). Note: This period length is only 0.75 years as there was a chan in the reporting period from July-June to April Mach.
(3)
Reactor shut down June 1,1971 for one month for cooling system upgrading.
(4)
Reactor shut down July 26,1976 for one month for refueling reactor with a new full FLIP fuel core. Note: This period length is 0.33 years.
k E
I
IV-5 c-Table IV.A.3 Present OSTR Operating Statistics
=
Annual Values Cumulative Values 1
Operational Data for for for July 1,1989 August 1,1976 FLIP Core Through Through j
June 30,1990 June 30,1990 MWH of energy produced 1,013 11,671 MWD of energy produced 42.2 486.4 Grams 2ssU used-53.0 610.7 Number of fuel elements added to
(+) or removed from (-) the core
-1, + 1 85 + 3 FFCR"3 Number of pulses 7
1,155 i
Hours reactor critical 1,136 15,282 Hours at full power (1 MW) 1,009 11,367 Number of startup and shutdown 253 3,518 checks Number of irradiation requests 301 5,301 Ff
.' processed (2)
Number of samples irradiated 2,886 62,001 (1) Fuel Follcwer Control Rod.-
(2) Each irradiation request could authorize from 1.to 120 samples. The number of samples per irradiation request averaged 9.6 during the current reportin0 period,
>=
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5 IV-6 i
Table IV.A.4 OSTR Use Time in Terms of Operational Functions Annual Values Cumulative Values for for July 1,1989 August 1,1976 Through Through
- June 30,1990 June 30,1990 OSTR Operational Function (hours)
(hours)
Checkout, core excess and -
427 5,229 shutdown Reactor in use"'
2,183 22,233
-l Total reactor use time 2,610-27,462 (1)
This function includes preclude time, multiple reactor experiment time, and the time the reactor is in use for teaching but not necessarily operating. (Preclude time is the time the reactor is not available for regular use due to performance
- of surveillance.and maintenance items, such as fuel element inspections, transient rod lubrication, control rod calibration, power calibration, as well as sample loading and unloading time.)
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9 L
IV 7 1
l W
e Table IV.A.5 OSTR Use Time in Terms of Specific Use Categories a
l~
Annual Values Cumulative Values for for July 1,1989 August 1,1976 OSTR Use Category Through Through June 30,1990 June 30,1990 (hours)
(hours)
Teaching (departmental and 245 3,239 cthers)U' l
OSU research<2) 461 6,243 t2 Off-campus research )
711 3,620 Forensic services 1
155( '
Reactor preclude time 923 9,269 Facility time (di 242 4,714 l9 Visitor demonstration (5) 27 222 o
Total reactor use time 2,610 27,462 (1)
See Tables Ill.A.2 and Ill.E.1 for teaching statistics.
(2).See Table Ill.A.3 for research statistics.
(3)- Prior to the 1981-1982 reporting period, forensic services were grouped under another use category and the cumulative hours have been compiled beginning with the 1981-3 l-1982 report.
~
(4) The time OSTR spent operating to meet NRC facility license requirements.
'-(5)-
This is the time that the reactor was used specifically for visitor open house (demonstration) events. The remainder of the visitors viewed the reactor during times t
when the reactor was being operated for regularly scheduled research and teaching.
=
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Table IV,A.6 4
l OSTR Multiple Use Time
[
UI i
l Annual Values Cumulative Values b
for for July 1,1989 August 1,1976 Number of Users Through Through j
June 30,1990 June 30,1990 (hours)
(hours)
Two-216 1,371 Three 90 368 Four-14 116 l
Five 0
10 i
Six 0
23
'Seven 0
4 j
Total multiple use time 3 20<2>
1,892(3) l (1) Multiple use time is that time when two or more irradiation requests are being 13 concurrently fulfilled by operation of the reactor.
g (2) This represents 28% of the total hours the reactor was critical during this reporting period.
1 (3) This represents 12% of the total hours the reactor was critical since startup with FLIP fuelin August of 1976.
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60 g*
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40 O
C Reportina Period 1976-77: 19.0 MWD O
1977-78: 20.6 MWD 3
1978-79: 10.6 MWD O
1979-80: 23.8 MWD O) 1980-81: 41.9 MWD 0
1981-82: 41.6 MWD 1982-83: 38.8 MWD
~2 20 g
1983-84: -39.8 MWD 1984-85: 39.4 MWD 1985-86: 43.4 MWD
\\
1986-87: 41.4 MWD 1987-88: 41.7 MWO 1988-89: 42.7 MWD 1989 90: 42.2 MWD 0
l
-l l-
- l
--l
- l -- - l -
- l -l- -- l - - - 1
--l
- l
- l -
l- - -
76-77 78-79 80-81 82-83 84-85 86-87 88-89 90-91 77-78 79-80 81-82 83-84 85-86 87-88 89-90 Time (Annual Reporting Period)
_5 m
Figure IV.A.1 OSTR Annual Energy Production Vs. Time (Annual Reporting Period)
i IV 10 B.-
Exoeriments Performed
{
c:
' During the current reporting period there were 11 approved reactor experiments available j
for use in reactor related programs. The following list of reactor experiments identifies the 11 approved experiments.~ Missing numbers signify reactor experiments which are in the inactive file and are not currently being used.
)
A-1 Normal TRIGA Operation (No Sample Irradiation).
{
B3 Irradiation of Materials in the Standard OSTR Irradiation Facilities.
B 11 -
Irradiation of Materials involving Specific Quantities of Uranium and Thorium in the Standard OSTR trradiation Facilities.
B12 Exploratory Experiments, f
B 21 Beam Port No. 3 Neutron Radiography Facility: Amendment No.1 to B 21; Neutron Holography.
B 23 Studies Using TRIGA Thermal Column.-
i B-24 General Neutron Radiography.
n I
B 25 Neutron Flux Monitors.
B 29 Reactivity Worth of Fuel.
)
B 30~
NAA of Jet. Diesel, and Furnace Fuels.
B 31 TRIGA Flux Mapping.
{
- Of the approved experiments on the a:tive list, five were used during the reporting
.l period. A tabulation of information relating to reactor experiment use is given in Table IV.B.1, and includes a listing of the experiments which were used, how often each was l
i used, and the general purpose of the use. Presently,25 experiments are in the inactive I
file and could be reapproved for use if needed.
I n
- O -
.j i
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b
1, IV 11 o:
Table IV.B.1 s:
Use of OSTR Reactor Experiments"'
7 Reactor Experiment Facility c2 D
Number :
Research Teaching Forensic Time )
TOTAL A1 0
33 N/A 65 98 B3 127 25 1
N/A 153 B 11 13 0
0 N/A 13 B 12 -
1 0
0 N/A 1
B 23 0
1 0
N/A 1
TOTAL 141 59 1
65 266 (1)
This table displays the number of times reactor experiments were used for a particular purpose.
(2)
~The following tabulation gives the number of each reactor experiment used and its P-corresponding title:
A 1-Normal TRIGA Operation N.-
B3 trradiation of Materials in the Standard OSTR Irradiation Facilities o
B 11 Irradiation of Materials involving Specific Quantities of Uranium and Thorium in the Standard OSTR Irradiation Facilities B 12 Exploratory Experiments B 23-. Studies Using TRIGA Thermal Column (3)- ' The time OSTR spent operating to meet NRC facility license requirements.
D'
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- IV 12 1
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- C.
Unolanned Shutdowns J
t
? ;.
v i JThere 'were.five unplanned reactor shutdowns (scrams) during the current reporting.
w period.; Table IV.C.1 contains a summary of the unplanned shutdowns including a brief ;
.F y
+l.
,d'escription of the cause of each.'
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IV 13 Table IV.C.1 Unplanned Reactor Shutdowns (Scrams)
Number of Type of Scram Occurrences Cause of Shutdown Manual 2
Stack monitor filter failure. Replacing the expired filter tape remedied the problem. Reactor operation was resumed.
t
' Manual 1
Transient rod low air pressure. Replacing the failed air hose between the solenoid valve and the transient rod corrected the problem.
I Manual 1
Bulk water high temperature. The reactor was scrammed and cooling expedited. The cooling system was found to be functioning at less than full capacity due to a closed make up valve. The valve was opened and reactor operation was resumed.
' Sa'fety Channel '
1 The scram set point on the safety channel was reached as the reactor was approaching full power with an P
experiment located in core. The flux perturbation caused by the in core experiment resulted in lower readings on
-s the linear and % power channels relative to the reading
'/
l, on the safety channel.-
p LQ.
1 f
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i 1
IV 14 j
' D.'
Chances to the OSTR Facility, to Reactor Procedures, and to Reactor Excoriments Performed Pursuant to 10 CFR 50.59 The information contained in this section of the report provides 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 applicable safety evaluation. Although it may not be specifically stated in each of the following safety evaluations, all actions taken under 10 CFR 50.59 were implemented only after it was established by the OSTR Reactor Operations Committee (ROC) that the proposed activity did not require a change in the facility's Technical 1
Specifications and did not introduce or create an unreviewed safety question as defined in 10 CFR 50.59(a)(2).
i 1.
10 CFR 50.59 Chanaes to the Reactor Facility I
There were four changes to the reactor facility which were reviewed, approved, and performed under the provisions of 10 CFR 50.59 during the reporting period.
W a.
AIR FLOW ANNUNCIATORS FOR THE REACTOR BAY VENTILATION' SYSTEM s=
(1)
Description Until recently, the method of. detecting operating' abnormalities or failure of the reactor bay ventilation system was through annunciators -
linked to the electrical power for the air supply and exhaust fan -
motors, and through damper annunciators associated with the air-operated ventilation system dampers. The reactor operations staff has suppfemented these annunciators by installing air pressure sensors in-the air supply and exhaust ducts for the reactor bay ventilation system.
t The pressure sensors were installed in the ducts in locations where y
they will: detect a significant decrease or total loss of air flow due to 5
any cause, installation involved drilling a small hole in the supply duct l:
sheet metal and using an existing tap in the exhaust duct. The air I*
l P
L i
IV-15 pressure sensors and associated switches were connected to the I
control room annunciator panel so that a lack of flow for any reason i
s:
will sound and illuminate a " ventilation low flow" annunciator.
f (2)
Safety Evaluation There are no negative safety implications associated with the installa-tion of the air pressure sensors and switches. Indeed, they will e
enhance safety by reducing the already small probability that any
. ventilation. system failures will go unnoticed. The basis for this conclusion stems from the fact that the new pressure switches will detect changes in or loss of ventilation air flow from any cause W not I
.- just from a loss of electrical power or a loss of instrument air pressure l
to the ventilation system dampers.
b.
REPLACEMENT OF THE ANNUNCIATOR PANEL DAY / NIGHT SWITCH k
(1)- Description L
In order to put the new " ventilation low flow" annunciator mentioned in.D.1.a onto the day / night switch,it was necesary to replace the old I.
switch with a new one which had more contacts. To do this, the switch location on the reactor console also needed to be changed. The old conductivity monitor (which was no longer used) was removed from the left console tower and a new panel was installed. The new f
day / night switch was installed in this panel. This has the additional advantage of placing the new switch in a more convenient location on the left console side cabinet.
(2)
Safety Evaluation This change of a switch and its location on the console has absolutely lc no safety implications whatsoever. 'Even though the original switch was located on the console, it did not interact in any way with any I
reactor safety circuitry or instrumentation, b-l l
l
IV 16 c.
ARGON' VENT FAN REWIRING
-(1)
Description The reactor staf f had the electrical circuit to the argon vent fan rewired y
so that if the entire reactor bay ventilation system shuts down, or if S
only the reactor bay exhaust fan shuts down, the argon vent fan will l
also stop automatically. In addition, as part of the rewiring effort the electrical power for the argon vent fan was routed through a timer so j
that the argon fan will not restart until af ter a preset interval. During this delay interval, power will first be restored to the reactor building exhaust fan, and this system will be allowed to reach full operating capacity before the argon fan starts.
-(2)
Safety Evaluation These facility changes were made to enhance safety, and are part of the Center's commitment to the ALARA program. Ensuring that the argon vent fan automatically stops whenever the-r ; tire reactor bay a
ventilation system shuts down or when the reactor bay exhaust fan shuts down will prevent the undiluted nase of any small amounts of c.
4 argon-41 which may be in the argon ventilation system piping. It will also relieve the reactor operator from having to shut off the argon fan manually in the event of'a ventilation system shutdown. In both
[
cases, the amount of argon 41 released during shutdown of the reactor bay ventilation system will be reduced.
Starting the argon vent fan after a preset time delay will ensure that any argon-41 in the argon ventilation system piping will not be drawn out until the reactor bay ventilation system' is working at its full capacity. Thus, argon-41 concentrations will continue to be very low
).
at the point of release. In addition, there is alreaay a control room annunciator for the argon vent fan, so the operator is aware of the argon vent fan status at all times.
b l
J
IV 17 d.
~ ROTATING RACK ANNUNCIATOR e
(1)- Description The reactor operations staff installed an annunciator which will alert the reactor operator if the rotating rack should stop turnin2 The hardware to initiate the signal for the annunciator consists of:
(a)
A permanent magnet attached to the large gear wheel on the i
rotating rack drive train.
(b) - A magnetic field sensor mounted on the rotating rack drive
- housing, j
-i (c)
An adjustable time delay receiver that will receive a signal from the magnetic field sensor, i
y,
. The time delay will trigger the annunciator panel if it does not receive k
a periodic signal from the magnetic field sensor.
.{
(
-(2)
Safety Evaluation
.The installed electronic circuit is separate from all other reactor controls and circuits and, therefore, willin no way be detrimental to reactor safety. -In fact, it may slightly enhance safety by alerting the
)
reactor operator when (and if) the rack stops rotating. The circuit will only interact with a selected annunciator window. 'If, for some reason, the circuit should fail, then there will either be a continuous annuncia-l tor or no annunciator at all (which is the present arrangement). The correct functioning of the annunciator is automatically tested each time the rotating rack is turned off (approximately daily).
IV 18 l
2, 10 CFR 50.59 Chanoes to Reactor Procedures 9
There were seven changes to reactor procedures which were reviewed, approved, i
and performed under the provisions of 10 CFR 50.59 during the reporting period.
i n.
y a.
REVISION OF OREGON STATE UNIVERSITY TRIGA REACTOR OPERATING PROCEDURE-(OSTROP) 18--ENCAPSULATION REQUIREMENTS
'(1)
Description The reactor operations staff expanded the encapsulation requirements f
as detailed in OSTROP 18. These requirements were originally written with the rotating rack and the pneumatic transfer system in mind and I
were, therefore, silent with respect to encapsulation requirements for other facilities. - For these reasons, the encapsulation requirements-were ' completely reevaluated.
Instead of one table. showing all l
encapsulation requirements, there are now five individual tables which
~ detail the acceptable encapsulations for each of the OSTR irradiation i
facilities, in addition, the' narrative description of encapsulation-requirements, limitations, and other pertinent considerations contained in paragraphs 1) and 2) were slightly revised to accommodate the new b
tables, and a new-paragraph 3) was added regarding specific _ ROC o-approval of encapsulations. A new paragraph 4) was also added to indicate that more rigorous encapsulations of a currently approved type -
t may be used in lieu of less stringent polyethylene encapsulation.
]
(2)
Safety Evaluation l
It is difficult with such a large revision to specifically discuss every single encapsulation change. Thereftre, the principles and philosophy of the changes will be cddressed.
j o'
i The general philosophy of the new encapsulation requirements is that they should be stated in a manner which will give experimenters as much flexibility as possible consistent with the known limitations of D.
the various containers. This philosophy leads to the different catego-ries in the tables.
i IV-19
{
The decision to split up the original encapsulation table into several different tables which are specific to certain irradiation f acilities makes it possible to take into account factors such as neutron and gamma flux levels, neutron spectra, the temperature in the various irradiation facilities, and methods commonly used to handle irradiated samples.
This added detail enhances safety in that it enables the encapsulation to be more specifically tailored to the type of facility rather than to some generic standard. For example,it was recognized that it was not always desirable in order to ensure containment using polyethylene 1
vials, to allow irradiations longer than about 10 to 12 minutes in the rabbit facility when the reactor was at high power levels (e.g.,500 to 1000 kW) and cadmium covers were being used. Therefore, there is now a 100 kWh limit for polyethylene encapsulated, cadmium covered samples in the rabbit.
5-The second general principle used in the reevaluation was that etable
_ solid materials generally need only one level of containment, whereas liquids, powders and similar loose matorials need. two levels of-
- L containment. In this manner, containment appropriate to the material or substance being irradiated is achieved. However, with respect to this policy _it.should also be noted that in almost every case the containment specifications are in addition to the extra containment provided by the standard TRIGA tubes or by the rabbit tubes used to hold the_ encapsulated ssmples during irradiation.
For the rotating rack and pneumatic transfer facilities, the desired --
integrated neutron flux also affects the encapsulation requirements.
Experience and testing has shown that there are limits to the capabili-
[
ties of the various sizes of polyethylene vials used in these facilities.
Therefore, these limitations are build into the new tables.
M
IV 20
':.o nnal f actor considered was whether or not cadmium covers will be
[
used. 'The heating the extra gamma flux associated with the use of cadrnium covers degrades polyethylene vials and, therefore, enca psula-tion is more restrictive when cadmium is used.
There are no known limitations to quartz and aluminum encapsulations; however, an administrative limit of 35 MWh has been chosen for routine approval, if needed, a greater irradiation time may be approved through the "Other Encapsulation Methods" option.
A new paragraph 3) has been added which allows for variances from these encapsulation requirements if the experiment has gone through the ROC approval procedure described in OSTROP 18,5. This does not reduce safety in any way because the experiment approval procedure requires specific ROC approval and is, therefore, even more rigorous.
A new paragraph 4) has also becn added, and simply clarifies that
= more rigorous forms of currently approved encapsulations may be used in lieu of polyethylene. The only possible impact this can have is to enhance safety.
In conclusion, all of the encapsulation' changes were made according to the philosophy and principles outlined above. In this manner, it is f#.
- hit each new table describes appropriate and safe levels of contalr.inent described in the tables are based on actual experience in use and/or testing, and have been found to prevent radioactive material
. release under the stated conditions of use.
4 61 4
7e
- 7.,
IV 21 b.
REVISIONS TO THE OSTR AND RADIATION CENTER EMERGENCY
}
RESPONSE PLAN JULY 1989 (1)
Description in response to a previms amendment to the OSTR emergency plan, the USNRC iequired an amindment to revise the line of succession for the Senior Health Physicist (SHP) position, it was the Commission's opinion that the Radiation Center Director should not be included in the SHP line of succession. Hence, the position of Reactor Operator was substituted for the RC Director. Other changes included: adding the OSU Office of Environmental Health and Safety to the list of support agencies, updating the administrative title for the Public Information Officer to Assistant Vice President for University Relations, and including a typed version of Figure 3.2.
(2)
Safety Evaluation The aforementioned changes do not decrease the effectiveness of the U
emergency response plan. With respect to the SHPline of succession, the Reactor Operator is the most acceptable choice to replace the RC I
Director when considering the available statt members and their current commitments to the emergency response plan. The Reactor Operator position is regularly trained and ex1 mined in the topics of radiation protection and emergency response and consequently can fulfill the basic responsibilities of Senior Health Physicist.
The addition of the OSU Environmental Health and Safety office increases the effectiveness of the plan by including additional, skilled personnel who may be able to help in specific situations.
The administrative title change and the typing of Fi ure 3.2 clearly do nct 0
[
decrease the effectiveness of the plan.
IV 22 c.
REVISIONS TO THE OSTR AND RADIATION CENTER EMERGENCY RESPONSE PLAN 0CTOBER 1989 (1)
Description f
As a result ot the annual review of the emergency response plan on September 29,1989, it was decided to make a number of small changes in the OSTR and Radiation Center Emergency Response Plan.
These changes are detailed below.
Front Cover -
The last revision date was updated.
The typographical error in the spelling of " service" Page 12 was corrected.
l Under the heading " City of Cervallis Police Depart.
Page 3 3 ment", the sentence from "The City of Corvallis Police Department will be involved in emergency..."
[
. was changed to "The City of Corvallis Police Depart.
ment could be involved in en emergency..."
i i
Page 314 -
The diagram on the iDte 4 ace of the various on and.
off site emergency orce.,1zations was updated to include the OSU Department of Environmental Safety, i
the name of OSU Campus Security was changed to OSU Campus Police and Security and the Federal Radiological Monitoring and Assessment Plan box'
)
was changed to Federal Emergency Management Agency (FRMAP).
l 1
Changes were also made to the Emergency Response Plan Implement-o ing Procedures to update telephone numbers, and allow for personnel turnover..
I t
IV 23 I
(2)
Safety Evaluation 9
s There are clearly no safety implications ci any of the changes to the emergency plan, as they do not affect any response actions. Most of the changes merely were made to keep the plan current. The City of
)
Corvallis Police will not necessarily always respond to an emergency as the OSU Police now have increased capabilities and will normally be asked to respond to any significant emergencies.
d.
REVISION TO THE OSTR AND RADIATION CENTER EMERGENCY RE-SPONSE PLAN -June 1990 1
(1)
Description it was determined that the decontamination equipment maintained at the OSU Student Health Center was no longer a necessary part of the existing emergency response plan for the OSU TRIGA reactor and Radiation Center. Therefore, the emergency response plan was revised in order to delete all references to the Student Health Center decon-a tamination facility. Other minor changes to the plan were needed to correct a typing omission, to change the name of the OSU Department of Information and to update the plan to ensure that it was consistent a-with other reactor procedures. All of these changes are detailed l
below.
Page 3 4 The sentence under Good Samaritan Hospital begin-ning: " Arrangements have also been made..." was a
deleted.
.j Page 3 5 The section headed: "OSU Student Health Service" was deleted.
41 o
The words " Department of Intormation" was changed to " News and Communication Services" in two o
locations.
i l
J.
1 IV 24 Page 3-10 The words " Director of the OSU Department of p
information" were changed to " Assistant Vice Presi-i dent for University Relations" in the first paragraph.
o Page 314 That section of Figure 3.2 which shows the OSU Student Health Center was deleted.
" Department of Information" was changed to " News
?
and Communication Services".
t Page 7 3 Allof the prefixes associated with airborne radioac-tivity concentrations were inadvertently omitted on this page. Therefore, this page was reissued with the i
prefixes inserted.
i A
Page 7-10 Section 7.2.4.1).1) -- The last sentence: "This infor-3 mation is indicated on a personnel status board j
maintained in the control room." was deleted, o
Page 8 6.
Paragraph 8.3.2.c) was replaced with:
"Iniured oersonnel will normally be decontaminated and then j
dispatched to the Good Samaritan Hospital."
Page 8 7 Paragraph 8.3.3.c) was replaced with: "In the event that these showers a:e not accessible or available, there are further personnel decontamination facilities A
1 at the Good Samaritan Hospital."
l o.
Paragraph 8.3.4.b) was deleted and subsequent paragraphs renumbered.
le.
l 3
a l-
~
t t
IV-??
D Page 10-1 The wording "and OSU Student Health Center" was a
deleted from paragraph 10.1.b).iv).
D y
Page 10 3 The wording " Student Health Service decontamina-tion room and those in the" from paragraph 10.4.2.c) was deleted.
r p
Page 10 4 Section 10.4.2.e) was changed to read: "The emer.
r gency evacuation horns are functionally tested each quarter."
Paragraph 10.4.3.b) was deleted and the following paragraph renumbered.
. Section 10.4.3.c) was changed from " annually" to
" semiannually".
y I..
Page B 1 Section B.'2.b) was deleted and subsequent sections r
a, o
renumbered, i
i Pages B 2 through B-14
!~
These pages were replaced with a revised example of the inventory checklist which did not reference the I
Student Health Center.
t 12)
Safety Evaluation A recent reevaluation of the procedures'to be used in the event of personnel injury involving contamination highlighted the fact that h-virtually no use would be made of the facility at the OSU Student Health Center. There are many decontamination facilities at' the f
Radiation Center which would be used in preference to the Student Health Center, if these were unavailable due to the nature of the U-
p 1
IV 26 J
b' accident or if injuries requiring immediate medical attention were involved, then the f acilities which have been established at the Good 3
Samaritan Hospital would normally be used. in addition, the decontam-i
)
ination kits which are maintained in the Corvallis Fire Department's Hazmat vehicle would also be available if needed. Therefore,it was
)
concluded that the OSU Student Health Center's decontamination facility could be decommissioned with no reduction in the of fectiveness of the existing emergency plan. Appropriate changes to the plan were made to implement this conclusion.
The revisions to the plan relating to the Department of information's name change to News and Communication Services have no safety implications whatsoever. All of the expected responses remain the same.
The change to page 7 3 was merely correcting a typing omission 3
which occurred when the page was revised. The plan itself, the alarm set points and the detection limits were not actually changed, so O
clearly there are no safety implications associated with this correction.
' Airborne concentration action levels in the plan and in the implement-ing procedures were, and are, still correct.
l i
The personnel status board referred to on page 710 had not proven to be necessary and, therefore, it was felt that its use could be discontinued. Because there is normally only one or two people in the reactor bay at any one time, the reactor operator can easily keep track of where they are. During classes, the escorting instructor is responsj-i ble for the evacuation of his students if required, it is felt that this a
6; change does not. reduce the effectiveness of the emergency plan or l
t compromise safety in any way.
.j i
t i
e 1
IV 27 l
l P-Initial difficulties with the condition of the evacuation horn batteries r
resulted in a switch to monthly routine maintenance of the batteries and monthly testing of the horns. After several years of experience, 7
y it was determined that the horn testing frequency could be reduced to quarterly, with no loss of confidence in the horns' ability to function when needed. This is largely due to the fact that the evacuation horn battery maintenance will remain on a monthly frequency. Again, it is felt that this change does not reduce the of fectiveness of the emergen-cy response plan.
The final change in the emergency plan on page 10 4 reflected the f act that the emergency equipment inventories at various locations are now checked on a semiannual rather than an annual basis. This is clearly an improvement in the plan.
e.
REVISION OF THE REACTOR OPERATIONS COMMITTEE CHARTER AND h
OSTROP 6-ADMINISTRATIVE AND PERSONNEL PROCEDURES f
(1)
Description t
As a result of the annual review of the Reactor Operations Committee (ROC) Charter, the reactor staff made one minor revision to section 11.2 of the ROC Charter and to the corresponding wording from the charter which is contained in section 6.4.B.2 of OSTROP 6.
Additional wording was inserted af ter the existing statement that "All members shall have equal voting rights and responsibilities." The new wording j
n added the phrase, "In situations where a committee member has a -
conflict of interest, it shall be committee policy that the individual abstain from voting on the issue."
I, 4
(2)
Safety Evaluation j
Addition of the conflict of interest statement has no direct relationship to any specific safety issue and certainly does not introduce any new 3
IV 25 4
i N
or unreviewed safety questions. Any safety related impact of the new o:
statement is only positive and thus enhances safety by removing any a
non objective voting which might potentially occur in the presence of a conflict of interest.
f.
CHANGE TO OSTROP 10 RELATING TO CONTROL ROD CALIBRATION AND THE CADMlUM LINED IN CORE IRRADIATION TUBE (CLICIT)
(1)
Description OSTROP 10.7.B.6 stated that if the control rods have been recalibrated since the CLICIT was last used, and if, as a result of the calibration, the worth of any rod changed by more than 2 cents, then all of the rods must be recalibrated with the CLICIT in the core before the CLICIT could be used. It was recognized that this limitation was not needed t-and could be relaxed. without compromising safety or without
' conflicting with the OSTR Technical Specifications. Therefore, this b
section of OSTROP 10 was eliminated and 10.7.B.7 was renumbered to 10.7.B.6.
E.
g DJ Y
(2)
Safety Evaluation Technical Specification 4.3.1 only requires that the reactivity worth of each control rod and the' shutdown margin (SDM) be measured annually and following significant core or control rod worth changes.
Therefore, calibrating the rods once each year, with and without the e
CLICIT in the core, will meet this requirement.
The only time the control rod worth curves are used for routine steady state operation is in the determination of the core excess and the SDM to ensure that the SDM remains greater that $0.57, it is clear that if a
the reactor has sufficient SDM without the CLICIT installed, then because the CLICIT adds only negative reactivity, there will be more than sufficient SDM with it in the coro. Hence, there are no safety, i
y i
3 IV.29 I r j
t 0
license or operational needs to recalibrate the control rods with the D.
CLICIT in the core more frequently than required by the Technical Specifications (i.e., once a year, or after other significant core or control rod changes).
g.
REVISIONS TO THE FUEL ELEMENT HANDLING PROCEDURES l
(OSTROP 11)
(1)
Description It was recently recognized that OSTROP 11 addressed the insertion L
and removal of the sample holding dummy fuel element, but did not address the insertion and removal of the cadmium lined in core irradiation tube (CLICIT). The purpose of this change was to incorpo-1 rate necessary fuel handling procedures associated with the use of each of these devices in the same section of OSTROP 11, namely section D.2.
D;
.'(2) ~ Safety Evaluation b
This change updated the OSTR fuel element handling procedures, and therefore, contributes to increased safety by generating additional written procedures which supplement those presently in place. The fuel handling procedure for insertion and removal of the CLICIT is the j
ga!ng as that approved for the sample holding dummy fuel element, i
and this procedure has been used for many years with no difficulty.
This procedural change does not in any way change the authorization n
process for fuel element movement. Therefore, use of the revised procedures still requires the normal review and authorization detailed -
in other sections of OSTROP 11.
l o:
3.
'10 CFR 50.59 Chances to Reactor Exoeriments There were no changes to reactor experiments during this reporting period.
N i.
t IV 30 I
l E.
Surveillance and Maintenance 1.
Non-Routine Maintenance 3
-July 12,1989 Replaced the bearings in the reactor primary pump and o
repaired the primary pump shaft.
)
July 31,1989 Removed a fuel element with cladding deformation from the reactor core and replaced it with a new spare fuel element.
July 31,1989 Removed the old transient control rod from the reactor core and inserted a new transient control rod in the same core L
position.
.Aug.18,1989 Replaced a failed printed circuit board in the emergency power invertor.
Aug.29,1989 Replaced a transistor in the panel control circuit board of the control room annunciator panel.
Sept.13,1989 Installed two additional latches on the reactor bny main access double doors.
Nov.1,1989 Replaced the analog meter for the stack monitor gas channel.
'Nov.27,1989 Replaced the stack monitor pump.
l Jan 4,1989 Installed a new magnetic starter for the reactor bay ventilation System supply fan.
Jan.4,1990 Rerouted electric power to the argon ventilation fan 4
through the reactor bay exhaust fan contactors.
Jan.4,1990 Installed a time delay restart relay on the argon ventilation fan.
Jan.4,1990 Installed two pressure switches downstream of the reactor bay supply fan and the exhaust fan for monitoring ventila-tion system flow.
9,;
-Jan.7,1990 Equipped the reactor building east side door with a new alarmed crash bar assembly.
Jan.22,1990 Installed an additional latching device on the roof hatch l0 l-door of the reactor building.
b-l l
1
IV 31 Jan.22,1990 Installed a new control room day night switch.
0 March 13,1990 installed a television monitor in the control room for D.
viewing the east P.A. door.
j o
March 26,1990 Replaced three number indicating tubes in the control rod 5
position indicator panel.
April 26,1990 Replaced the transient rod air hose between the solersoid valve and the transient rod.
May 21,1990 Welded a cracked seam along a bottom plate of the thermal column door.
June 6,1990 Replaced the photo multiplier tube in the particulate channel of the continuous air monitor.
June 1.8,1990 installed a new drive motor for the rotating rack and cleaned and adjusted the rotating rack clutch assembly.
i 2.
Routine Surveillance and Maintenance The OSTR has an extensive routine surveillance and maintenance (S&M) program, f.
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+
p tions.
. F.
Renortable Occurrences There were no reportable occurrences during the reporting period, i
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Figure IV.E.1 Monthly Surveillance end Maintenance (Sample Form)
SURVEf ttANCE & PAINTENtNCE FOR THE MONTM OF 0$iROP 13 SURVEltLANCE & MAINTENANCE 10 BE PERFORMED 1IFIT5 AS FOUND B
CEE O
TED 5
MAlltRJN UP:
inches
- 1
' FUNCTIONAL CHECK OF RE ACTOR WATER LEVEL At*RMS MOVEMENT DN:
faches s3 INCHE5 Antt:
M 2 MEASUREMENT OF THE REAC10R PR! MARY WATER pH 3 MEASUREMENT OF THE Butt 5HIELD TANK WATER pH INVERTER 5.G. DISCS tfP 4 EMERGENCY power SYSEM 5.G.' >I.250 BATTERY CHECKS GENERATOR 3 g CORR: NOME ti'/J f D: FUtt 5 kVACUATION HORN & P. A. EPER6ENCY SYSTEM 5.S.- >I.250 BAffERT LHECKS VOL15 > 12V DC CORR: NONE 6
INSPECTION OF THE BRtf5HE5 ON THE PNEUMATIC CHARM WHEN TRANSFER SYSTEM BLOWER MOTOR 1/4* LEFT 1
GREEN t!GHT ButB REPLACEMENT 75 EATT 8 CHANGE LAlY SUSAN FILTER FILIER CHANGED 9 (UBRICAIE THE TRIGA TUBE LOADING 100* (REEL)
USE GUN CIL NEED O!L7 10 RE ACTOR IDP CAM Dil LEVEt CHECK OSTROP 13.30
- EED Dit?
Il PROPANE TAMK LIQUID LEVEL (NECK (1 fUtt)
>501
- 12 3UtK WATER TEMPERATURE ALARM CHf CK FUNCTIONAL 13 PRIMARY PbMP 8 EARING 5 OIL LEVEL (*4CK 051 ROP 13.33 NEED Olt ?
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- License Regtstrement.
6
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- Date act to be e needed for 1trease erge?irements 15 equal to the date CM eted last month plus st a es*e65.
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Quarterly Surveillance and Maintenance (Sample Form) esracP neltcesimmEsf.
sunwituuri a munansct een fu emmian er i
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TARGET
'OATE NOT TO
'Att Mmats 3
$URVEfttANCE 3 27mTERANCE TO BE PERFORMED LIMITS-AS FOUW DATE SE ERCEEDE0**
COMPttiE9 INITIALS 16 FUNCTIONAL CHECK OF EVACtfATION ALARMS Att FumCTIONAL IF SU9MI1510N OF $AFEGttARDS 10G BY P.S.O.
. SUBM!i IF NEW ERTRIES 18 STACK MONITOR ALARM CiliCUIT CHECK 5 ALA8De CN ComiACT..
19
- License Requirement
- Physical Security Plan Requirement
" Date not to be esteeded for license requirements is equal to ttee date (capleted last quarter plus fove months.
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u o- ~ np Figure IV.E.3 Semi-Annual SuEveillance and Maintenance (Sample Form) 051 ROP 15 SEMI-AEENAL SEIBUEILIANCE & MIGIUWluCE Pet TANGET DATE NOT TO DATE RE Msts s SURfEf ttANCE & MINTENANCE 10 BE FERFORMED t!MITS AS F0tmo.
GATE SE EECEEDED**
COMFt E TED
. INITIALS
- 1 TUNCTIONAL a) NEtfiRON SOURCE COUNY RAIE INTERLOCE CufCr5 0F 15 ces a2 b) TRANSIENT ROD AIR INTERLOCK NO PULSE b
c) PULSE PROHIBIT ABOVE I tu 11 6W c
d' TWO ROD WITHORAWAt PRON] SIT
] enly d
el PutSE MODE RdD MovtMENT INTERt0Cr 20 MOVE 4 NT e
f) MIIMUM Putst REAcilvlif IN5ERTION LIMIT i 32.50 F
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- 2 PERIOD SCRAM g
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TEST
'3 CONTROL ROD TRAN5
$AFE
$2IM REG WITHDRAWAL,
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c) INSERTION 150 set c
- 4 PtstSE COMPAR!$0N (PREVIOUS PUL5E): FUL5E #
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m
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-5 REACTOR BAf VEN11tATION SYSTEM $Nui DOWN TEST y
- 6 CAttBRA!!ON OF THE FUEL ELEfENI TEMPERATURE CMNNEL 22*C
- 7 MTER!Als BALANCE REPORT / FUEL MNAGEMENT E EN
- 8 CLEAtlNG & LUBRICATION OF TRANSIENT ROD CARRIER INTERNAL BARREL g(ag g
- 9 ttrbRICATION OF '8Att-Inff DR!vE ON TRANSIENI ROD CARRIER fif 0t 10 (UM? Call 0N OF THE ROYAIING PJtCK BEARING 5 10 W Olt OttEd il CONSOLE CPtCE LIST (OSTROP 15.13) g,g 12 CON $1 ANT AIR MONITOR RECOR'TR MINTENANCE 13 utSTRONICS RECURDER ZERO & CALI"RAll0N CHEtts I4 STANDARD CONTROL ROD HOTOR CHECK 5 01t10 15 f tuRE fett TEMPERATURE INSTRUMENT *D' CELL CHECK C
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PART V l0 PROTECTION e
[
A.
Introduction P
This section of the report deals with the radiation protection program at the OSU Radiation Center. The purpose of this program is to ensure the safe use of radiation and radioactive materials in the Center's teaching, research, and service activities, and in a similar manner to ensure the fulfillment of all regulatory requirements of the state of Oregon, the U.S. Nuclear Regulatory Commission, and other regulatory agencies. The comprehensive nature of the program is shown in Table V.A.1, which lists the program's major radiation protection requirements and the performance frequency for each item.
l The radiation protection program is implemented by a staff consisting of a Senior Health Physicist, a Health Physicist, a Radiation Protection Technologist, and one to five part-time Radiation Protection Technicians (see Part li.F). Assistance 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 current requirements of Nuclear Regulatory Commission (NRC) Facility License No.
R-106 (Docket No. 50 243) and the Technical Specifications contained in that license.
The material has also been prepared in compliance with Oregon Department of Energy Rule No. 345 30 010, which requires an annual report of environmental effects due to research reactor operations. A summary of required data for the OSTR is provided in Part 1.E for quick reference.
l Within the scope of Oregon State University's radiation protection program, it is standard operating policy to maintain all releases of radioactivity to the unrestricted io environment and all exposures to radiation and radioactive materials at levels which are 6
consistently "as low as reasonably achievable" (ALARA).
A C
l l
l
t V2 s
Table V.A.1 O
Raoiesion Protection Program Requirements and Frequencies j
o y
FREQUENCY RADIATION PROTECTION REQUIREMENT Daily / Weekly / Monthly Perform routine area radiation / contamination monitoring, j
l Weekly Perform gamma spectroscopy of the (OSTR) continuous air monitor particulate filter.
Monthly Perform routine response checks of radiation monitoring instruments, j
Monitor radiation levels ( R/hr) at the environmental monitoring stations.
Collect and analyze TRIGA primary, secondary, and make-up water, j
Exchange personnel dosimeters and inside area monitonng dosimeters, and review exposure reports.
l Inspect laboratories.
Check emergency safety equipment.
Perform neutron generator and tritium assembly contamination survey.
Calculate previous month's gaseous effluent discharge, s
As Required -
Process and record solid waste and liquid effluent discharges.
Prepare and record radioactive material shipments.
Survey and record incoming radioact!ve materials receipts.
Perform and record special radiation surveys.
Perform thyroid and urinalysis bicassays.
5 Conduct orientations and training.
Issue r.adiation work permits and provide health physics coverage for maintenance L
operations.
L 1
[
Quarterly Prepare, exchange and process environmental TLD packs.
Collect and process environmental soil, water and vegetation samples.
Conduct orientations for classes using raoioactive materials.
Collect and analyze sample from reactor stack effluent line.
Exchange personnel dosimeters and inside area monitoring dosimeters, and review i
exposure reports.
Semi-Annual Leak test and inventory sealed sources.
Conduct floor survey of corridors and reactor bay.
Calibrate portable radiation monitoring instruments and personnel pocket ion chambers.
I
- s inventory and inspect Radiation Cente. equipment located in the Corvallis Fire l.
Department Har/ Mat van and at Good Samaritan Hospital.
Annual Calibrate reactor stack effluent monitor, continuous air monitors remote area i
radiation monitors, water monitor, and air samplers.
Measure f ace air velocity in laboratory hoods and exchange dust stop filters and HEPA filters as necessary.
D.
Inventory and it'spect Radiation Cerrter emergency equipment.
o; Conduct f acility radiation survey of the cobalt 60 irradiators and X ray machine.
3 Conduct personnel dosimeter training.
a
=
V3 B.
Environmental Releases The annual reporting requirements in the OSTR Technical Specifications state that the h
licensee (OSU) shall include "a summary of the nature and amount of radioactive effluents released or discharged to the environs beyond the effeefve control of the licensee, as measured at, or prior to, the point of such release or discharge." The liquid y
and gaseous effluents released, and the solid waste generated and transferred are discussed briefly below. Data regarding these effluents are also summarized in detail in the designated tables.
1.
Liouid Effluents Released Whenever possible, liquid effluent is analyzed for radioactivity content at the time it is released to the collection point (a holdup tank). However, liquids are always analyzed for radioactivity bef ore the holdup tank is discharged into the unrestricted area (the sanitary sewer system). For this reporting period, the Radiation Center and reactor made only two liquid effluent releases, both to the sanitary sewer. All
=
a Radiation Center and reactor facility liquid effluent data pertaining to these two -
releases are contained in Table V.B.1.
o 2.
Airborne Effluents Released Airborne effluents are discussed in terms of the gaseous component and the particulate component.
a.
Gaseous Effluents Gaseous ef fluents from the reactor f acility are monitored by the reactor stack effluent monitor Monitoring is continuous (i.e., prior to, during, and after reactor operations). It is normal for the reactor facility stack offluent monitor to begin operation as one of the first systems in the morning and to cease O
operation as one of the last systems at the end of the day. Allgaseous effluent data ior this reporting period are summarized in Table V.B.2.
,0
v e
su
<_r a us
-e e
Table V.B.1 Monthly Summary of Liquid Elfluent Releases to the Sanitary Sewer for the year July 1,1989 through June 30,1990"'
(OSTR Contribution Shown in 0 and Bold Print)
Specific Activity Average For Each Detectable Concentration Percent of Radionuclide in tre Total Quantity of Released Applicable Total Volume Waste, Where tfe of Each Detectable Radioactive M FC for of Liquid Date of Total Ouantity Release Radionuclide Material at Released Effluent Discharge of Radioactivity Detectable Concentration Was Released in the the Point of Radeoactive Released (Month &
Released Radionuclides
> 1 x 10 pCi/cc Wacte Release Material Ircluding Yearl (Curies) in the Waste (pCi/ccl (Curies)
{ Ci/cci
(%)
Diluent
4 AUG 89
'H 5.75 x 10' 3.11 x 10
Cr 1.04 x 10 '
5.77 x 10 s 2.1 %*
Radiation 3.12 x 10 4 Center "Co 2.20 x 10 '
O.06 %"'
Plus OSTR
Se 8.22 x 10
1660
( HI (5.43 x 10')
(2.94 x 10*)
OSTR (1.8 E *
Cr )
(-)
(1.04 x 10 ')
(5.44 x 10')
Contribution (2.94 x 10*)
(" Col
(-)
(1.76 x 10')
(0.05%)p, to Above
(Sel
(-)
(1.31 x 10')
APR90
'H 1.08 x 10' 7.17 x 10' 0.8#
Radiation 6
1.17 x 10 7.74 x 10 Center
- Zn 5.14 x 10 '
O.03 %"'
Plus OSTR
Se 4.99 x 10*
1755
( H)
(-)
(3.66 x 10')
OSTR (0.5 9 Contribution (4.03 x 10')
( Col
(-)
(4.51 x 10')
(6.06 x 10*)
('Zni
(-)
(5.14 x 10 ')
(0.02%)"'
ts Above
(Sel
(-)
(3.11 x 10*'
Annual
'H Total for
Cr 1 2 %"'
N Radiation 3.89 x 10' "Co 3.89 x 19 3.m x 10' Applicable O.04 %
Center Zn Plus OSTR
Se 341!.
('H)
OSTR
(Cr)
- Not (1 0%)
(3M x 101 (2.59 x 109 (Ok)3%)"'
Contribution (3.34 x 10*)
("Co)
Applicable 13 Above
("Zn)
(Se) 41) operational pokcy is to subtract ordy detector background from our water analysis data and ret bac6 ground rahoactiway in the Corvalks ciey water. There were no Equid etfksent releases dunne months (2)
The total volume of hquid effksent plus detuent does not take into consideration the additional sniming with the over 7.500,000 gallons per year of Equids and sewage normafy discharged by the Rad *atkyn Corner complex into the same sarutary sewer system.
(3)
Cesed on vakses Ested in to CFR 20, Appendix B. Table 2. Cohann 2.
(!)
Based on wasues hsted in to ciR 2o, Appendex B. Table 1, Coksmn 2, which are appiscable to sewer desposal.
p b
=
=
V5 Tab le V.B.2 Monthly Summary of Gaseous Effluent Releases
(
for the Year July 1,1989 through June 30,1990"'
Estimated Average Percent of the Atmospheric Applicable Total Diluted MPC for Diluted Total Estimated Concentration of Concentration Date of Estimated Quantity of Argon-41 at of Argon 41 at Discharge Radioactivity Argon 41 Point of Release Point of Release I
(Month &
Released Released (2)
(Reactor Stack)
(Reactor Stack) 1 year)
(Curies)
(Curies)
(vCl/ml)
(%)
]
- JUL 89 0.47 0.47 3.5 x 10 8 0.9 %
AUG 89 0.51 0.51 3.9 x 10 8 1.0%
I SEP 89 0.85 0.85 6.5 x 10'8 1.6%
1 OCT 89 0.57 0.57 4.2 x 10 e 1.0%
^ NOV 89 0.53 0.53 4.1 x 10 8 1.0%
DEC 89 0.67 0.67 4.9 x 10 8 1.2%
i JAN 90 0.50 0.50 3.7 x 10 0 0.9 %
FEB 90 0.35 0.35 3.0 x 10 8 0.7 %
MAR 90 0.50 0.50 3.8 x 10 8 0.9 %
?.
APR 90 0.62 0.62
- 4.8 x 10 8 1.2%
8 MAY 90' O.43 0.43 3.3 x 10 0.8 %
- JUN 90 0.47 0.47 3.6 x 10'8 0.9 %
a ANNUAL VALUE 6.5 6.5 4.1 x 10 8 1.0%
(1)
Airborne effluents from the OSTR contained no detectable particulate radioactivity resulting from reactor operations, and there were no releases of a radioisotopes in airborne effluents in concentrations greater than 20% of the applicable MPC value. (20% is a value taken from the OSTR Technical Specifications.)
(2)'
- Routine gamma spectroscopy analysis of the gaseous radioactivity in the OSTR stack discharge
' indicated the only detectable.radionuclide was argon 41.
)
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f
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I
t V6 1
[
b.
Particulate Effluents Particulate effluents from the reactor facility are also monitored by the reactor facility stack effluent monitor.
Evaluation of the detectable particulate radioactivity in the stack effluent confirmed its origin as naturally occurring radon daughter products, within a range of approximately 1 x 10* pCi/cc to 3 x 10'" Ci/cc. This particulate radioactivity is predominantly lead 214 and bismuth 214, which is not g
associated with reactor operations.
There was no release of particulate effluents with a half life greater than 8-days and therefore the reporting of the average concentration of radioactive particulates with half lives greater than eight days is not applicable.
3.
Solid Waste Released p;
Data for the radioactive material in the solid waste generated and transferred during this reporting period are summarized in Table V.B.3 for both the reactor
- )
i facility and the Radiation Center. Solid radioactive waste is routinely transferred to the OSU Radiation' Safety Office. Until this waste is disposed of by the Radiation Safety Office, it is held along with other campus radioactive waste on the University's state of Oregon radioactive materials license.
. Solid radioactive waste is disposed of by the University Radiation Safety Office by transfer to the University's radioactive waste ' disposal vendor, Allied Ecology Services, Inc., for burial at their installation located near Richland, Washington.~
i e
,a 1
I*
s 1
V7 l
1 l
j 4<
Table V.B.3 6
Annual Summary of Solid Warte Generated and Transferred i
for the Year July 1,1989 through June 30,1990 b.
Volume of Total Quantity Dates of Solid Waste Detectable of Radioactivity Shipment to Origin of Packaged Radionuclides in Solid Waste Allied Ecology Solid Waste (Cubic Feet) in the Waste (Curies)
Services, Inc.")
L
~
24 Sodium 4eScandium 65 Manganese 58Cobalt solron
' Cobalt
'62inc 75 Selenium
. TRIGA 90Technicium 1.3 x 10'8 Reactor 15 124Antimony Dec. 7, H89 Facility 125Antimony May 8, M Wiodine 132 Tellurium 137 Cesium
'dOBarium l'0 u
Lanthanum
Cerium -
y 5s2 Europium y.
15d Europium m2 Tant. slum
Carbon
Scandium Radiation 59 1ron 9 0 x 10
May 8,' 1990 Center 15
- soCobalt.
Laboratories 140Lanthanum 164 Europium (1)
All Radiation Center and OSTR solid radicactive waste is routinely transferred to the OSU Radiation Safety Office, where it is held on the University's State of Oregon radioactive materlats license, along -
L
_ with other campus waste, prior to shipment to Allied Ecology Services, Inc. by the Radiation Safety Office.
1 1-y r-
i i
v8 C.
Personnel Doses The OSTR annual reporting requirements specify that the licensee shall present a 6
summary of the radiation exposure received by facility personnel and visitors. For the purposes of this report, the summary includes all Radiation Center personnel who may
- )
have received exposure to radiation. These personnel have been categorized into six groups: facility operating personnel, key facility research personnel, physical plant maintenance personnel, students in laboratory classes, police and security personnel, and visitors.
Facility operating personnelinclude the reactor operations and health physics staff. The dosimeters used to monitor these individuals include monthly X ray, beta, and gamma (XS(GH film badges, quarterly track etch / albedo neutron dosimeters, either monthly or quarterly TLD (finger) extremity dosimeters, and pocket ion chambers.
i Key facility research personnel consist of Radiation Center staff, faculty, and graduate students who perform research using the reactor, reactor activated materials, or using
)
5 other research f acilities present at the Center. The individual dosimetry requirements for these personnel will vary with the type of research being conducted, but will generally j
include a monthly or quarterly M(G) film badge and TLD (finger) extremity dosimeters.
if the possibility of neutron exposure exists, researchers are also monitored with a track etch / albedo neutron dosimeter.
Physical Plant maintenance personnel are normally issued a gamma sensitive pocket ion i
chamber as their basic monitoring device. A few Physical Plant personnel who routinely
{
perform maintenance on mechanical or refrigeration equipment are issued a quarterly i
XS(G) film badge and other dosimeters as appropriate for the work being performed.
Students attending laboratory classes are issued quarterly XB(G) film badges, TLD (finger) extremity dosimeters, and track-etch / albedo or other neutron dosimeters, as appropriate. Students or small groups of students who attend a one time laboratory demonstration and do not handle radioactive materials are usually issued a gamma sensitive pocket ion chamber.
a 4
V t
V9 7
OSU police and security personnel are issued a quarterly XB(G) film badge to be used I
during their patrols of the Radiation Center and reactor facility.
1 k
Visitors, depending on the locations visited, may be issued a gamma sensitive pocket lon chamber. OSU Radiation Center policy does not normally allow people in the visitor l
category to become actively involved in the use or handling of radioactive materials.
i 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 person.1el radiation exposures in excess of the I
limits in 10 CFR 20 or state of Oregon regulations during the reporting period.
Ui O
f jt h
1 q:
01 l
1, 14 i
V 10 w
Table V.C.1 I
(
Annual Summary of Personnel Radiation Doses Received f
For the Year July 1,1989 through June 30,1990 i
e Average Annual Greatest Individual Total Person mrem l
Dose"I Dose"8 For the Group"3 Whole Whole Whole l
Personnel Group Body Extremities Body Extremities '
Body Extremities (mrem)
(mrem)
(mrem)
(mrem)
(mrem)
(mrem)
Facility Operating Personnel -
17 47 135 480 375 1030 Key Facility Research Personnel 2
10 20 210 80 330 Physical Plant l
Maintenance Personnel
<1 N/A
-20 N/A 44 N/A o
Laboratory Class Students 0-5 0
120 0
240 h
Campua Police and Secusity Personnel 3
N/A 20 N/A 80 N/A E
Visitors -
<1 N/A 8
N/A 68 N/A
,(1) "0" Ircicates that each of the beta gamma dosimeters 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 tnan i
the vendor's threshold of 30 mrem, as appli.able. "N/A" indicates that there was no extremity monitoring
-conducted or required for the group, i
i i
I i
'$ L l
0-te -
V 11 D.
Facilltv Survev Data The OSTRTechnical Specifications require an annual summary of the radiationlevels and i
levels of contamination observed during routine surveys performed at the facility.
[
However, the Center's comprehensive area radiation monitoring program encompasses
- the Radiation Center as well as the OSTR, and therefore monitoring results for both facilities are reported.
1.
Area Radiation Dosimet n Area monitoring dosimeters capable of integrating the radiation dose are located at strategic positions throughout the reactor facility and Radiation Center. All of.
these dosimeters contain at least a standard personnel type beta gamma film pack.
In addition, for key locations in the reactor f acility and for certain Radiation Center g
laboratories a CR 39 plastic track etch neutron detector has also been included in the monitoring package. Figure V.D.1 shows the locations of the dosimeters in the reactor building and Radiation Center.
The total-dose equivalent recorded on the various reactor facility dosimeters is listed in Table V.D.1 and the total dose-equivalent recorded on the Radiation
'[
Center area dosimeters is listed in. Table V.D.2.
Generally, the characters following the MRC (Monitor Radiation Center) designator shc'v the room number or location. The. highest recorded dose' equivalent was measured in B119,- the source storage room. Monitoring at this location commenced on August 4,1989 when small sources from the shielded sealed source storage room (Hot Cell) were '
-temporarily stored in the NAA permanent storage file cabinets while the Hot Cell.
was painted. Although the measured dose equivalent at the B119 location was-3500 mrom for the third quarter of 1989 (equivalent to 2.5 mrem /hr), the dose equivalent at MRCFE 7, at the unrestricted fence boundary, was essentially a
background (see Figure V.E.1 and Table V.E.1).' The small sources were returned to the Hot Cell at the end of this period. The NAA permanent storage file cabinets f
were moved from B119 to B116 in March of 1990 to permit additional shielding to be placed between the cabinets and the outside wall, o
1 Figure V.D.1 TRIGA Facility and Radiation Center Area Dosimeter Locations MRCTWH MRCTEN Reactor Facility 3rd Floor Reactor Facility 2nd Floor V
V MRCTTOP
>MRCTW MCTME p\\
~
~~
]"
D104 D104 R
or ay Reactor Reactor
(
Bay i
( )
iW,I/
iv Bay E
>MRCTSW MRCTSE d a
h gU a
d MCD-200 E
I A
V MRCD-300d
[
MRCD-10[
g 302 g
T 4 p a >
==
-==
gf g
~
D204 32,,Dg D106 a
D102 D100 D206
,A MRCB-1 98 A Timh.E l
g '21 V
D104 Reactor Bay MCBRR
" B_
NtC C123 i Reactor Facility 4th Floor I
MtCB-11 2 5
Mg-119-14
.12.,
, _8 g
nortn i
'Eoading Dock I a B119 I lB123 A,
C122 NB 9p j 200- L233 D400
- 13) g 116-3N 4MRCB-120 0400A 5 s C'
a v
Y A130 V
4
^
132 g
B11 E
gB pCB-122 0 16tC300XRAY MtCB< 124-Q A MCB-12 2-2 l C121 g
MCC Al2B A l 7
1 V
~'
-134 MCB-114 B126A MRCC-124 "VMCA-126 l g
E130 A126 i A134 B114 B1268 C124 C-120 o
E El I
E E
> MtCC-126 E102
- MCB-1g A136 8108 B128 C126 A124 C120 h
E104 E124 4tCC-1184 U.b B106 l 8130 C128 M
VMtC-C1 0-3 h
"~ %
dR*$'n'
~
n20 2
B104 B132 C130 E10l 6------
g C13Mj l
[ WB A1200 g
g I
E E118
(
C116
{C115 E112'EI14"'
A120.,;
A144 B102 B134 C132 1
AMRI -J 120
@ CC-134 ggt 21
.MtCA-14
$ kB-100 A P' 6--
C114 A
Lj A116,
A146 B100 B136 C134 6--
C108 m
h..... --. *Ig
- 5..,7 ' 3{
A xem rom
.y
~
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>3 a
! I h_
5
^ E*! !O L'Ln 5
2 2
E. s.
g m
m m
V 13 Table V.D.1 Total Dose Equivalent Recorded on Area Dosimeters Loc 4 ted Within the TRIGA Reactor Facility for the Year 7
(.
July 1,1989 through June 30,1990 Total Recorded Dose Equivalent Monitor TRIGA Reactor (1)(2) 1.D.
Facility Location xB(G)
Neutron (See Figure V.D.1)
(mrem)
(mrem)
MRCTNE D104:
North Badge East Wall 35 0
MRCTSE-D104:
South Badge East Wall 0
0 i
MRCTSW D104:
South Badge West Wall 65 0
l MRCTNW.
D104:
North Badge West Wa!!
90 0
MRCTWN D104:
- West Badge North Wall 15 0
t
.MRCTEN D104:
East Badge North Wall 115 0
MRCTES/
D104:
East Badge South Wall 215 0
MRCTWS D104:
West Badge South Wall 410 0
MRCTTOP D104:
Reactor Top Badge 435 0
MRCTHXS D104A: South Badge HX Room _
435 0
MRCTHXW D104A: West Badge HX Room 80.
0-k MRCD 302
,D302:
Reactor Control Room 225 0
MRCD 302A D302A:
Reactor Supervisor's Office 25 (3)
N/A i
(1) ~ The total recorded dose equivalent values do not include natural background contribution and,
except as noted, reflect the summation of the results of 12 monthly beta gamma dosimeters or. four quarterly fast neutron dosimeters for each location. A total dose equivalent of "0" 4
indicates that each of the dosimeters during the reporting period was less than the vendor's gamm'a dose reporting threshold of 10 mrem or that each of the fast neutron dosimeters was less than the vendor's threshold of 50 to 100 mrem. as applicable.- "N/A" indicates that there was no neutron monitor at that location.
1
-(2)
These. dose equivalent values-do not represent radiation exposure through an exterior wall directly into an unrestricted area.
l 2
l.
- (3)
The total recorded dose equivalent reflects the summation of four quarterly beta-gamma-ll
. dosimeters.
v
\\
I t
Q
,e
i V 14 Table V.D.2
-t f
c-Total Dose Equivalent Recorded on Area Dosimeters H
Located Within the Radiation Center for the Year i
{
July 1,1989 through June'30,1990 Total Recorded Radiation Center Dose Equivalent (1)
Monitor Facility Location xB(G)
Neutron I.D.
(See Figure V.D.1)
(mrem)
(mrem)
MRCA100 A100:
Receptionist's Office O(2)
N/A MRCBRF A102H: Frt Personnel Dosimetry Stor. Rack 0(2)
N/A' MRCA120 A120:
Stock' Room 0(2)
N/A
.MRCA120A A120A: NAA Temporary Storage O (2)
N/A MRCA126 A126:
Campus RSO's Isotope Receiving Lab 105(2)
N/A MRCCO 60 A128:
Cobalt 60 Irradiator Room 180 (2)
.N/A MRCA130 A130:
Shielded Exposure Room 0(2)
N/A MRC300XRAY A132:
X Ray Console Room 25 (2)
N/A MRCA134 2 A134:
NAA Research Office 230 (2)
N/A MRCA138' A138:
Health Physics Laboratory 0(2)
N/A 6-MRCA146' A146:
Gamma Analyzer Room (Storage Cave) 125 (2)
N/A j
MRCB100 '
. B100:
Gamma Analyzer Room (Storage Cave) 100 (2)
N/A MRCB114 B1-14:
a Lab.(Radium 226 Storage Facility) 1820 45 MRCB1161 B116:
Storage Rm (NAA Permanent Storage) 35 (2)..
N/A
[
- MRCB116-2 B116:
Storage Rm (NAA-Permanent Storage) 1130(2)
N/A 1
MRCB1.16 3 B116:
Storage Rm (NAA Permanent Storage) 25 (2)
N/A MRCB1191 B119:
Source' Storage Room 15(2)
N/A MRCB119 2 B119:
Source Storage Room 5610 (3)
N/A MRCB119A B119A: ; Sealed Source Storage Room.
4210 3050
~ MRCB120 B120:
-Instrument Calibration Facility 55 (2)
N/A MRCB122 2 B122:
Radioisotope Storage Hood 1250 (2)
N/A I
'MRCB122-3 B122:
. Radioisotope Research Laboratory O '(2)
N/A
- MRCB1241, B124:
Radioisotope Research Lab (Hood) 0 (2)
N/A' B
MRCB124 2 B124:
Radioisotope Research Laboratory 0(2)
N/A MRCB124 6 B124:
Radioisotope Research Laboratory 0(2)
N/A MRCB128
.B128:
Instrument Repair Shop 15(2)
- N/A MRCB132 B132:
Radioisotope Research Laboratory 980 (2)
N/A MRCC100 C100:
Radiation Center Director's Office 0(2)
N/A c
MRCC106 H C106H: East Loading Dock 20 (2)
N/A 7
MRCC118 C118:
Radiochemistry Laboratory 0(2)
N/A MRCC120 C120:
Student Counting Laboratory 0(2)
N/A g
MRCC126N C123:
Gamma Analyzer Room (Storage Cave) 590 (2)
N/A 1
MRCC123S C123:
Gamma Analyzer Room 20 (2)
N/A
.See footnotes next page.
.t,
i t
V 15 i
+
Table V.D.2 (continued) e Total Dose Equivalent Recorded on Area Dosimeters i
Located Within the Radiation Center for the Year
(;
July 1,1989 through June 30,1990 Total Recorded Monitor Radiation Center Dose Equivalent (1)'
l.D.
Facility Location xB(G)
Neutron (See Figure V.D.1)
(mrem)
(mreni.'
MRCC124 C124:
Student Office / Lounge 0 (2)
N/A MRC126 C126:
Student Counting Laboratory 20 (2)
N/A i
MRCC1301 C130:
Radioisotope Laboratory (Hood) 15 0
.MRCC130 2 C130:
Radioisotope Laboratory 0
0 MRCC130-3 C130:
Radioisotope Laboratory 0
0 i
MRCC134 C134:
Gamma Analyzer Room (Storage Cave) 95(2)
N/A lMRCD102 D102:
Pneumatic Transfer Terminal Lab 135 0
MRCD102 H D102H: - 1st Floor Corridor at D102 '
0 0
MRCD106 H -
D102H: 1st Floor Corridor at D106 145(2)
N/A MRCD200 D200:
Senior Health Physicist's Office 130 (2)
N/A e-
-MRCBRR' D200H: Rear Personnel Dosimetry Storage Rack 0(2)
N/A f
MRCD204 H ~
D204H: 2nd Floor Corridor at D204 15 0
MRCD300 D300:
- 3rd Floor Conference Room 15 0,j
)'~
- except as noted, reflect the summation of the results of 12 monthly beta-gamma dosineters
' (1)J ' The total recorded dose equivalent values do not include natural background contribution and, or'four quarterly. fast neutron dosimeters for each location. A total dose equivalert of ~ "0" indicates that each of the dosimeters during the reporting period was less than the vendor's
-gamma dose reporting threshold of 10 mrem or that each of the fast neutron dosimeters was
- h..
less than the vendor's threshold of 50 to 100 mrem, as applicable. "N/A" indicates that there
.was no neutron monitor at that location.
1 g
i l
(2') The ' total recorded' dose equivalent reflects the summation of four quarte'rly beta gamma-dosimeters.
(3): LThe-total recorded dose equivalent reflects the summation of four quarterly beta gamma
' dosimeters that commenced on August 4,1989 (see text).
$h i
i Q
i J
~l l
l-l V 16 l
2.
Routine Radiation and Contamination Survevs
~..
6 The Center's program for routine radiation and contamination surveys consists of
)
daily, weekly and monthly measurements throughout the TRIGA reactor facility l
I and Radiation Center. The frequency of these surveys is based on the nature of I
y the radiation work being carried out at a particular location or on other factors
-l which indicate that surveillance over a specific area at a defined frequency is 4
desirable.
(
The primary purpose of the routine radiation and contamination survey program is 0
. to assure regularly scheduled surveillance over selected work areas in the reactor facility and in the Radiation Center, in order to provide current and characteristic data on the status of radiological conditions. A second objective of the program is to assure frequent on the spot personal observations (along with recorded data),
j which will provide advance warning of needed corrections and thereby help to ensure the safe use and handling of radiation sources and radioactive materials.
A third objective, which is really derived from successful execution of the first two k
objectives, is to gather and document information which will help to ensure that -
l all phases of the operational and radiation protection programs are meeting the f
goal of _ keeping radiation doses to personnel and releases of radioactivity.to the J
environment "as low as reasonably achievable" (ALARA).
- The annual summary of radiation and contamination levels measured during routine 1
1 facility surveys for the applicable reporting period is given in Table V.D.3.
o' i
O
V-17 Table V.D.3 t
Annual Summary of Radiation Levels and Contamination Levels Observed Within the Reactor Facility and Radiation Center During Routine Radiation Surveys for the Year July 1,1989 through June 30,1990
?'
Whole Body Contamination Radiation Levels Levels"8 i
2 (mrem /hr)
(dpm/100 cm )
Accessible Location (See Figure V.D.1)
Average Maximum Average Maximum TRIGA Reector Facility:
Reactor Top (D104) 1 150
<500
<500 Reactor 2nd Deck Area (D104) 5 52
<500
<500 Reactor Bay SW (D104)
<1 12
< 500
< 500 Reactor Bay NW (D104)
<1 19
<500
<500 i
Reactor Bay NE (D104)
<1 15
<500
<500 Reactor Bay SW (D104)
<1
'10
<500
<500 Class Experiments (D104,D302) '
<1 4
< 500 ~
< 500 Demineralizer Tank--
j Outside Shielding (D104A)
<1 3
< 500
< 500 1
Particulate Filter---
4 Outside Shielding (D104A)
<1 4
< 500 '
<500 1
Radiation Center, NAA Counting Rooms (A146,B100,C134)
<1 3
<500
<500-W-
Health Physics Laboratory (A138)
<1
<1
<500
' < 500 1
e Co Irradiator Room (A128)'
<1 4
<500
<500 Radiation Research Labs
- (B114,B122,B124,8132,C130)
<1 9-
<500 1000(2)
Radioactive Source Storage (B119A)'
<1 12-
<500-
< 500 Student Chemistry Laboratory
-(C 1,181 -
<1
<1
<500
.< 500 Student Counting Laboratories
-(C120,C126).
<1
<1
<500
' < 500 Operations Countino Room (C123) 21
<1
<500
<500 Pneumatic Transfer Laboratory (D102)
<1
<1
<500
<500 (1) < 500 dpm/100 cm2 = Less than the lower limit of detection for the portable survey instrument used.
W
' (2) The contamination shown for this location assumes 100% smearing officiency and was immediately removed.
As a result, the average contamination level at this location during the reporting period was,.for all practical y
2 purposes, < 500 dpm per 100 cm,
D.
1
l t
V 18 E.
Environmental Survev Data L
The annual reporting requirements of the OSTR Technical Specifications include "an
]
ennual summary of environmental surveys performed outside the facility."
l f
i 1.
Gamma Radiation Monitorino l
)
a.
On-site Monitoring Monitors used in the on-site gamma environmental radiation monitoring program at the Radiation Center consist of the reactor facility stack effluent monitor described in section V.B.2 and nine environmental monitoring I
~
stations located on the fence surrounding the reactor facility (see Figure V.E.1). These stations consist of a standard metal mailbox attached to the ~
l fence at a height of four feet.
Each fence environmental station is equipped with an OSU supplied and 7
processed TLD area monitor (normally three Harshaw LiF TLD 700 chips per
'Li monitor in a plastic "LEGO" mount). These monitors are exchanged and l
e k
processed quarterly. The total number of TLD samples for the reporting l
period was 108-(9 stations x 3 chips per station per quarter x 4 quarters per k
year).. A summary of this TLD data is shown in Table V.E.1.
Each fence environmental station also utilized a CaSO TLD monitoring l
4 1
packet supplied and processed by Radiation Detection Company (R.D. Co.),
- Sunnyvale, Califomia. Each R.D. Coi packet contained two CaSO TLDs and f
4 was exchanged quarterly for a total of 72 samples during the reporting j
period (9 stations x 2 TLDs per station per _ quarter x 4 quarters per year).
A summary of Radiation Detection Company's TLD data is also shown in l
Table V.E.1.
- I f
E F
Monthly measurements-of the direct gamma exposure rate, in micro-l 1
p l '
roentgens por hour ( R/hr), were also made at each fence monitoring station.
i l
H These measurements were made with an Eberline Instrument Company
)
p b
micro R per hour survey meter containing a 1" x 1" Nal detector.
L
[.
?
}
i i
V 19 Figure V.E.1 Area Radiation Monitor Locations for the TRIGA Reactor, and on the TRIGA Reactor Area Fence N=
l PERIMETER FENCE e
e c -
MRC FE3 MRC FE2 0FFICE S MRC FE4-MRC FE1e f-fC
\\
e
( MRC TNE MRC TSE r
e e
R A DI ATION MRCTEN g TRIGA REACTOR CENTER BAY L
BUILDIN G
(
~.
b I
n MRC TWN $
MRCTSW l;
e 3
S
~
j HX $ MRC THXS y
MRC TNW/
g l.
g ROOM
+
MRC THXW S MRC FESC
]
[
Ll0UID R. A.WA ST E
- gne HOLDIJP TANK i) 1.
l*-
.MRC FE6
(
3 1
TRANSFORMER MRCFE99 h
STATION MRC FE7 MRC FE8 i
i l
e G
O' 50ft u
V 20 l.b A total of 108 R/hr measurements were taken (9 stations per month x 12 months per year). The total calculated dose equivalent was determined by i
averaging the 12 separate R/hr measurements, multiplying this average by C:
8760 hours per year, and then by converting microroentgens to millirem. A summary of this data is shown in Table V.E.1.
From Table V.E.1 we have concluded that'the doses recorded by the dosimeters on the TRIGA facility fence can be attributed to natural background radiation,' which is about 110 mrem per year for Oregon (Refs, i
1, '2).
i b.
Off site Monitoring The off-site gamma environmental radiation monitoring program consists of
. twenty monitoring stations surrounding the Radiation Center (see Figure V.E.2) and one station located 5 miles to the south at the Corvallis Airport.
,, z N
Each off s (e radiation monitoring station is equipped with an OSU supplied
(
. and processed TLD monitor. Each monitor consists of three (MRCTE 11 has 7
six) Harshaw LiF TLD-700 chips in a plastic "LEGO" mount. The mount is sealed in a PVC tube which is taped to the station's post about four feet i
above the ground'(MRCTE 21 and MRCTE 22 are mounted on the roof of the
. EPA Lab and National Forage Seed Lab, respectively). These monitors are l
exchanged and processed quarterly, and the total number of TLD samples
..during the current 1 year reporting period was 264 (20 stations x 3 chips per I
station per quarter x 4 quarters per year plus 1 station x 6 chips per station per quarter x 4 quarters per year). A summary of the OSU off site;TLD data is provided in Table V.E.2. Thirteen of the off-site radiation monitoring stations also have a thin weather tight aluminum box mounted to the post b
at approximately four feet above the ground (these stations do not have an
'"L" at the end of the station identification number). The aluminum box 4
contains a packet with two C#0 TLDs supplied and processed quarterly by 4
o-the Radiation Detection Company. The total number of R. D. Co. TLD
V-21 Table V.E.1 Total Dose Equivalent at the TRIGA Reactor Facility Fence for the Year July 1,1989 through June 30,1990 Total Calculated Fence Dose Equivalent Environmental Total Recorded Total Recorded Based on the Monitoring Dose Equivalent Dose Equivalent Annual Average Station Based on R.D. Co.
Based on OSU R/hr 13 (See TLDsm TLDs(2x3)
Exposure Rate )
Figure V.E.1)
(mrem)
(mrem)
(mrem)
MRCFE-1 94 8628 80-2 23 MRCFE 2 100 8723 86 21 MRCFE 3 101-91 2 3 85 23 MRCFE-4 106 91 2 5 92 28 hARCFE 5 88 82 6
75226 MRCFE 6 93 83 2 4 79238 MRCFE 7 95 8626 80223 MRCFE-8 92 8524 75220 hARCFE 9 88 781 7 69217
-(1) - Radiation Detection Company (R.D. Co.) TLD totals include their annual natural background contribution _of 72 mrem for the reporting period. Average Corvallis area natural background using Radiation Detection Company TLDs totals 90 mrem for the same period.
_(2)
OSU fence totals include a measured natural background contribution of 70-10 mrem.
- s (3) 2 values represent the standard deviation of the total value at the 95% confidence level.
9<
a f-1 M-a
22 Figure V.E.2 Monitoring Stations for the OSU TRICA Reactor For the Year July 1,1989 through June 30,1990 s-b) c3 C"~U C 9 dD C bh C]CD c
7 K
df sx 1g g a
D::o, d,,,m e o ' O. h
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V 23 Table V.E.2 e-Total Dose Equivalent at the Off Site Gamma Radiation Monitoring Stations g.
for the Year July 1,1989 through June 30,1990 Total Calculated Off Site Dose Equivalent Radiation Total Recorded Total Recorded Based on the Monitoring Dose Equivalent Dose Equivalent Annual Average Station"'
Based on R.D. Co.
Based on CSU yR/hr (See Figure TLDs*
TLDs*""
Exposure Rate"'
l
'V.E.21 (mrem)
(mrem)
(mrem) v MRCTE 2L 85 t 6 49212 t
MRCTE 3 97 69 10*'
86220 MRCTE 4 85 9023 73 2 15 108 30 85 2 15 MRCTE-SL MRCTE 6 95 97 t 10 86220 MRCTE 7L '
85 2 6 88 23 MRCTE 8
-103 103 t 7 96221 MRCTE 9 101 90212 94218 MRCTE-10 83 81 1 9 65 2 13 hARCTE-11 81 7724 63 213-MRCTE-12 101 101 2.11 95 218 116
- 10 78 17 MRCTE 13L 96211 66 15 y~~
- MRCTE-14L MRCTE 15 89 9829 78225
- MRCTE 16L 103 17 83110 MRCTE 17 89 9229
.70212 OL MRCTE 18L '
10525 75217 MRCTE 19 99 118 2 12 94 17
. MRCTE 20L 112 211 84 2 13
'MRCTE 21 71
'80 2 5 46 212 MRCTE 22 79 8423 55 12 (1)
Monitoring stations coded with an 'L" cont eined one standard OSU TLD 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 include their annual natural background contribution of 76 miem for the reporting period.- Average Corvallis a.ca natural background using Radiation Detection Company TLDs tntds 83 mrem for the same period.
(3)
OSU off site totals include a measuicd natural background contribution of 82 2 34 mrem.
(4)
'2' values represent the standard deviation of the total value at the 95% ccMidence level.
(5) ' The total dose equivalent for three quarterly monitonny periods only. The TLD packet was lost or stolen during one quarter.
g-4 7
1 V 24 samples for the reporting period was 104 (13 stations x 2 TLDs per station per quarter x 4 quarters per year). A summary of Radiation Detection Company's TLD data for the off-site monitoring stations is also given in Table V.E.2.
a 6.
In a manner similar to that described for the on site fence stations, monthly measurements of the direct gamma exposure rate in microroentgens per hour
( R/hr) are made at each of the twenty one off site radiation monitoring stations. As noted before, these measurements are made with an Eberline Instrument Company micro-R per hour survey meter containing a 1" x 1" Nal detector. A. total of 252 R/hr measurements were made during the reporting period (21 stations per month x 12 months per year). The total dose equivalent for each station was detarmined by averaging the 12 separate pR/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 Table V.E.2.
Y Af ter a review of the data.in Table V.E.2, we have concluded that,like the fj dosimeters on the TRIGA facility fence, all of the doses recorded by the off site dosimeters can be attributed to natural background radiation, which is about 110 mrem per year for Oregon (Refs.1,2),
1 2.
Soil. Water. and Veactation Survevs The soil, water and vegetation monitoring program consists of the collection and
. analysis of a limited number of samples in each'cctegory on a quarterly basis. The program monitors highly unlikely radioactive material releases from either the-TRIGA reactor facility or'the OSU Radiation Center, and also helps indicate'the general trend of the radioactivity concentration in each of the various' substances
.f sampled. See Figure V.E.2 for the locations of the sampling stations for grass (G),
i*'
soil (S), water (W) and rainwater (RW) samples. Most locations are within a 1000 i.
foot radius of the reactor facility and the Radiation Center. In general, samples are collected over a local area having a radius of about ten feet at the positions L
indicated in Figure V.E.2.
V 25 There are a total of 22 quarterly sampling locations: four soil locations, 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 j
water samples, and 56 vegetation samples).
o 1
The annual average concentration of total net beta radioactivity (minus tritium) for samples collected at each environmental soil, water, and vegetation sampling location (sampling station) is listed in Table V.E.3. Calculation of the total net beta disintegration rate incorporates subtraction of only the counting system back-ground from the gross beta counting rate, followed by application of an appropri-ate counting system efficiency.
n The annual average concentrations were calculated using sample results which exceeded the lower limit of detection (LLD), except that sample results which were less than or equal to 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.for each sample category for the current reporting period.
As used in this report, the LLD has been defined as the amount or concentration j
k" i
of radioactive material (in terms of Ci per unit volume or unit mass)in a represen-i tative sample, which has a 95% probability of.being detected.
2 Identification of specific radionuclides is not routinely carried out as part of this-monitoring program, but would be conducted if unusual radioactivity levels above natural background were detected. However, fro n Table V.E.3 it can be seen that;
.the levels of radioactivity detected were consistent with naturally-occurring-i radioactivity and comparable to values reported in previous years.-
M
$~
f.
1
e-V-26 Table V.E.3 s:
3 Annual Average Concentration of the Total Net Beta Radioactivity (Minus H) for Environmental Soil, Water, and Vegetation Samples e
y for the Year July 1,1989 through June 30,1990 Sample Location Annual Average Concentration 3
(See Figure Sample of the Total New Beta (Minus H)
Reporting V.E.2)-
Type Radioactivity (1)
Units
-1 W Water (2) 2.57 x 10 8 z 6.20 x 10'8 pCl/cc 4W Water (2) 2.57 x 10 8 2 6.20 x 10 8 pCi/cc i
.11 -W Water (2) 2.57 x 10 8 6.20 x 10'8 Ci/cc 19 RW '
Rainwater (2) 2.57 x 10 8
- 6.20 x 10'8 pCi/cc 3S Soil 8.65 x 10'5 1.45 x 10'5 vCl/ gram of dry soil 5-S Soil 7.76 x 10'5 21.37 x 10 Ci/ gram of dry soil 5
- 20 S Soil 8.50 x 10'5 t 1,39 x IO'S Ci/ gram of dry soil 21 S Soil '
8.80 x 10'5 2 1.52 x 10'5 Ci/ gram of dry soil 2G Grass 4.65 x 10 4.98 x 10'5 pCi/ gram of dry ash 4
4 2 4.25 x 10'5 Ci/ gram of dry ash 6G Grass 2.63 x 10
'7-G Grass 4.18 x 10 2 4.96 x 10'5
. Ci/ gram of dry ash 4
L8 G Grass 3.53 x 10 4.64.x 10'8 -
pCi/ gram of dry ash 4
i' 9-G Grass 3.34 x 10 4.93 x 10
- Ci/ gram of dry ash 4
5 10 G Grass 3.81 x 10 4.98 x 10'5 Ci/ gram of dry ash 4
12 G Grass,
4.50 x 104
- 3.79 x 10'8 Cl/ gram of dry' ash 4
4 13 G -
Grass 4.54 x 10 4.74 x 10
- Ci/ gram of dry ash -
i o-4 5
14-G '
Grass 4.39 x 10 4.56 x 10
- Ci/ gram of dry ash
-15 G Grass 2.76.x 10 3.55 x 10'S pCl/ gram of dry ash 4
4 2 4.53 x 10'5 pCl/ gram of dry ash 16 G
' Grass 3.16 x 10 17-G Grass 4.59 x 104
- 4.17 x 10'5 pCi/ gram of dry ash 1
a 4
3.54 x 10'5 Ci/ gram of dry ash i
18 G '
Grass 3.61 x 10 1
22 G Grass
~ 4.02 x 10 2 4.29 x 10~5 pCi/ gram of dry ash j
4 (1) - t values represent the standard deviation of the average value at the 95% confidence level.
8 (2)' Less than lower.lirnit of detection of 2.57 x 10-8 6.20 x'10 pCl/cc.
s I<
i i
4 '.
'99 i
9 i
f-
i V 27 i'
Table V.E.4 4
Average LLD Concentration and Range of LLD' Values for j,
l, Soil, Water and Vegetation Samples for the Year U
July 1,1989 through June 30,1989 Sample Average Range of Reporting Type LLD Value LLD Values Units 5 to 2.45 x 10'S Cl/ gram of dry soil Soil 1.87 x 10
1.19 x 10 8
2.02 x 10 8 to 2.79 x 10 e pCl/cc
' Water 2.57 x 10 4
Vegetation 5.19 x 10'5 2.90 x 10-5 to 1.24 x' 10 uCl/ gram of dry ash 6
p.. '
j' 5
.a f
4' 8
O I
V 28 1
F.
Radioactive Material Shioments A summary of the radioactive material shipments orginating from the TRIGA reactor facility, NRC license R 106,is shown in Table V.F.1. A similar summary for shipments originating from the Radiation Center's state of Oregon radioactive materials license o
ORE 0005-3 is shown in Table V.F.2.
L.
t k
f^.-
b-3
. s :'
l i,'-
o' 1-l
V 29 Table V.F.1 Annual Summary of Radioactive Material Shipments Originating From the TRIGA Reactor Facility's NRC License R-106 for the Year July 1,1989 through June 30,1990 g
Number of Shipments Total Type A Quantity Shipped To
' Activity Limited Quantity White Yellow Yellow Total l
I ll Ill OSU Physics Dept.
5 1
Corvallis, Oregon 1.0 x 10' 4
OSU Oceanography Corvallis, Oregon 2.6 x' 10 2 7
7
-Univ. of Oregon Eugene, Oregon 4.2 x 10 2 8
39 31 t
NEA, Inc.
4 4
4 Beaverton, Oregon 9.2 x 10 Univ. of Washington Seattle, Washington 1.0 x 10'8 1
1 Battelle Pacific p1 lNW Laboratories 1.6 x 10 2 4
4 Richland, WA -
- Lawrence Berkeley Laboratory-
' 2.0 x 10'5 1
1 Berkeley, CA
' Brigham Young Univ.
~,
Provo, Utah.
9.0 x 10'5 2
2 Univ, of Wyoming 9
Laramie, Wyoming 1.4 x 10' 8
1
'Dartmouth Univ.
'Hanover, NH 3.0 x 10'5 1-1 Rensselaer Poly.
. institute 1.5 x 10" 5
5 Troy, New York TOTALS 8.8 x 10 2 30 0
48 0
78 O
V 30 1
9:
Table V.F.2 o
Annual Summary of Radioactive Material Shipments Originating From the Radiation Center's State of Oregon License ORE 0005 3 For the Year July 1,1989 through June 30,1990 p
1 Number of Shipments Total Type A Quantity-
. Shipped To Activity Limited (Curies)
Quantity White Yellow Yellow Total l
II
. lll
'OSU Physics Dept.
4 1
Corvallis, Oregon 1.3 x 10 1
1
-OSU Oceanography 4
4 Corvallis, Oregon 3.5 x 10 4
OSU Chemistry Corvallis, Oregon 3.0 x 10-5 1
1 OSU Pharmacy 4
15 Corvallis, Oregon -
1,1 x 10 15 Oregon Health Div, fj Hermiston/ Albany,CR-3.3 'x 10'3 2
2 h.-
Univ.' of Oregon
- Eugene, Oregon 5.3 x 10'5 2
2 Battelle Pacific NW. Laboratories 4.0 x 10'5 1
1 Richland; WA,
t
' Lawrence Berkeley -
Laboratory -
9.3 x 10'5 2
1 1
4 Berkeley, CA UC San.Diego q
San Diego, CA 1.6 x 10'8 2
2
- Univ.'of Missouri-Columbia, Missouri 2.2 x 10-5 5
5
'l
. Univ. of Maryland e._
Baltimore, MD 9.0 x 10'S 1
1 TOTALS 4.2 x 10 34 1
3 0
38 3
l
't I
.o.
.i V 31 G.
References 1.
U.S. Environmental Protection Agency, " Estimates of lonizing Radiation Doses in p
the United States, 1960 2000," ORP/CSD 721, Office 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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i l
t PART VI WORK A.
Summarv i
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 purpose of this part is to summarize the teaching, research and service efforts carried out during the current reporting period.
B.
Teachina i
The most important responsibility of the Radiation Center and reactor is to support OSU's academic programs, imptomentation 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 period, the Radiation Center accommodated 50 g
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 OSU teaching programs (not including research) utilized 245 hours of' reactor time. Tables Ill.A.1 and Ill.E.1 plus section VI.C.5 provide more detailed information on the use of the Radiation Center and :eactor for instruction and tr aining.
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 and a project sheet is generated. This sheet includes such information as the project number, data about the person and institution requesting the work, a description of the
. project, Radiation Center resources.needed, the Radiation Center project manager, estimated costs for the project, and the funding source.
4 I
l l
l i
VI 2 0-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 k
the number of academic personnel involved, the number of students involved and the 4
number of 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 lists information -
relating to the personnel and institution involved, the type of project, and the funding i
agency. Projects which used the reactor are indicated by an asterisk.
In addition to identifying specific p* ojects 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, s.
t t
e:
C O
L i
vi 3 Table VI.C.1 la Institutions and Agencies Which Utilized the Radiation Center Number of C
Number of Number of Uses of Number of Faculty Students Center Institution Projects involved involved Facilities
' Oregon State University"'
Corvallis, Oregon 49 58 67 204 oi!
U.S. Environmental Protection Agency Corvallis, Oregon 1
0 0
4 2
CH M Hill Corvallis, Oregon 1
0' O
2 Corvallis Clinic Corvallis, Oregon 1
0 0
8 M. Bloomfield Corvallis, Oregon 1
1 0
2 l
l U.S. Bureau of Mines i!
- Albany, Oregon 1
0 0
1
. Oregon Department of Energy lo :
Salem, Oregon 1
0 0
6 b-Sun Seeds
- Brooks, Oregon 1
0 0
4 O
University of Oregon Eugene, Oregon 13 14' 9
18
. Springfield Utility Board-Water Dept.-
Springfield, Oregon '
1 0
0 1
' U.S. Environmental Protection Agency Newport, Oregon 1
'1 0-1 l Levitronics, Inc.
Tualatin, Oregon 1
0 0
1
- 'NEA. Inc.
l Beaverton, Oregon '
1 0
0 4
' Intel Corporation Hillsboro, Oregon 1
0 0
-2 ion Health Sciences University
'and, Oregon 3
5-0 23 o'
'nstitute, OHSU irtland, Oregon 1
1 0
3
,1e OSTR.
3 c-(1) ' Use by Oregon State University does not include any teaching activities or classes accommodated by the Radiation Center.
i VI-4 i
4 --
Table VI.C.1 (Continued)
Number of Number of Number of Uses of Number of Faculty Students Center institution Projects involved Involved Facilities Reed College Portland, Oregon 1
2 1
1 Oregon State Health Division Portland, Oregon 1
0 0
3
' Oregon State Police Portland, Oregon 1
0 0
1 W. Chism 1 '
Vancouver, Washington 1
0 0
3
-Southem Oregon State College Ashland, Oregon 1
1 1
1
' University of Washington.
Seattle, Washington
-3 3
8 5
'Battelle Pacific Northwest Laboratories Richland, Washington 3
0 0
3 l
' Westinghouse Hanford Richland, Washington 1
0 0
1
'M.B. Research Burnaby, BC, Canada 1
0 0
1 n-
'Humboldt State University-Arcata/ California 2
1 1
2
' Lawrence Berkeley Laboratory Berkeley, California -
1 1
0 1
' Stanford University
. Stanford, California 1
1 1
1
- Brigham Young University
- Provo, Utah 1
1 0
2 i
' Univ, of Califomia, Santa Barbara
- Santa Barbara, California -
2 2
1 2.
i
- Univ, of Califomia Los Angeles Los Angeles, California 1
1 1
1 i
s*-,
University of Wyoming Laramie, Wyoming 2
4 0
11
'U.S. Geological Survey Denver Colorado 1
0 0
1 3
- Used the OSTR,
VI 5 Table VI.C.1 (Continued)
Number of Number of Number of Uses of o.
Number of Faculty Students Center institution Projects involved involved Facilities
' South Dakota School of Mines and Technology, Rapid City, S. Dakota 1
2 1
1
' Texas Tech. University Lubbock, Texas 2
1 1
2
' University of Texas-Arlington Arlington, Texas 2
2 0
2
' Rice University Houston, Texas 2
3 1
2
' Trinity University-San Antonio, Texas 1
1 1
1
' Louisiana State University -
Baton Rouge, Louisiana 4
3 3
4
{
' University of Tennessee Knoxville, Tennessee -
1 1
0 2
--* University of Rochester
=
Rochester, New York 2
2 2
2
' City University of New York New York, New York 1
1 0
1
State University of New York Albany, New York 1
1 0
1
'NationalInstitute of Standards and Technology, Washington, D.C.
1 0.
0 1
[-
' University of North Carolina Greensboro, North Carolina -
1 1
1 1
' North Carolina State University Raleigh, North Carolina 1
2
-1 1-
'Rensselaer Polytechnic Institute Troy, New York 3
3 0
5-
' University of Florida Gainesville, Florida 2
1 2
4 r
'Dartmouth College Hanover, New Hampshire 1
2 0
1
' Australian Museum Sydney, Australia 1
0 0
1 e.
TOTALS 129 123 103 355
- Used the OSTR.
. u_. r ~
v.
ox
. p.y
-- - - - =
. o "
u o =-
.l Table VI.C.2 j
Graduate Student Thesis Research Whch Utikred the Radiation Center i
Sttdent's Name
' Program Acaic Department FactAty Advisor Thesis Tcpec OREGON STATE UNIVERSITY l
Al-Baroude D.
PhD Nuclear Engmeering Klein Heat Repection System in Space Reactors Ala, A.
PhD Nuclear Engineering Reyes An Expenmental Investigation of Two-Phase Natural Circulation in a Passnrely Safe Reactor System Almarshad. A.
PhD.
Nuclear Engswing Klem Modehng of Ouide Growth on Zwaloy Fuel Rod Claddog Almasoenni, A.
PhD Nuclear Engineering Benney Monte Carlo Desp of Seafloor Core Analyses System I
Anand.A.
Pte Nuclear Engineenng Binney Dessgn of Marme Sample Analysts Systems Ba*, S.
MS Radiation Health -
Higgmbotham
" Set"Y Ouantification in Es.<wonmental Samples Using Beta Particle Spectroscopy with Actrve Gamma Ray Descrwnination Bukar, K.
MS Nuclear Engineenng Rotwison Comoarison of Various Flux Calculational Methods in Nodal Codes Cho,B.
MS Nuck.Jr Engmeering Rotynson Nodal Methods for Calculatog Nuclear Reactor Transients Control Rod Pattems, l
and Fuel Pm Powsrs 1
- Davidson, G.
MS Geosciences Lawrence Geochemical Charactentation of Two Suture Zones (for Process Comparison)
- Dundon,L.
PhD Physics Gardner High Pressure Perturbed Angular CorrelateZrO, Eichenberg, T MS Nuclear Engmeering Reyes Numerical Analysis of Condensation induced Water Hammers in Honront9 Pomg Systems Fu. Yengxian MS Chemistry Darweis Time MesJved Laser Spectroscopy of Nuc ; Acsds
- Fuchs, H.
MS Physics Gardner Pertubated Angular Correlation Spectroscopy of Condensed Matter (at Elevated Tempi
- Greek, K.
PtO Nuclecr r cring Hobwtson Development of an Obvect Onented Expert System for PWR Core Reload Greene, K.
PhD Nuclear Engmeering Robrison Process Monitorwg and Control with Expert Systems in Nuclear Engwemng Gulshan-Ara. Z, MS Nuclear Engineering Klem Space Nuclear Reactor
- Gui-ian, W.
PhD Physics Krane y-y Angular Correlations for '"Er Thesis research which utihred the OSTR.
C3
._m.
v v
4
~.
, a Tabh VLC.2 (Contmued)
Stadent's Name Program ActrA,T c Department Factity Advisor Theses Topsc Gutenberger, S.
PhD Mscrutanugy Rohevec Kiumg of Bactenal K+dney Disease A Krewtedged Based Approach for Morwtormg ard Setuateart Assessmer4 at FJuciear Heaberle, J.
PhD Nuclear Engmeermg Hobeson Power Plants Hcks. T.
MS Rad:ation Health Dodd Radiatson Protection Optwntrats m of a Broad tscense Fac&ty
- Hm, B.
PhD Geoscences Taylor Controis on Saiscsc Magma Evolution in the Centraf H<gh Cascades of Oregon Jordhe.m, D.
MS Nuclear Engmeerog Beney Production of "Pu
- Kausar, A.
MS Geosciences D ties Trace Dement Co.4 tents from Varcus Ore Deposrts an Pakistari u
Kmg I MS F4uclear Engmeermg Reyes A Study of Bucyant Backflow instatAtees an a 1/S Scale Reactor Geometry Lafs, A.
PhD FJuclear Ergineereg Reyes A General Theory for Floodmg implementog the Cuspoid Catastrophe Lee,H.
MS fJuclear Engmeenng Kle m Systems Analysrs for an Advanced Thermrorwc Reactor Leung,K.
PtB Mscrotxology Bottomley Rherotern Ecology Lewis. B.
MS Nuc: ear Engmeerng Klem hCore FJeutronc A. atysis of an Advanced Thermsorwc Reactor
- Lau, Y.
PhD Nuclear Engmeereng Schmrtt A Chemscal ard Petrogravec Study of Refractory th From KABA (CV3)
Chondnte Lisch, B.
PhD Food Scece & Tech.
Perner Passage of Focd Components Through the GI Tract of a Rat Marks. T.
MS Nuclear Engmeermg Klem Space Reactors
- Mathis. A.
MS Geew.ccs Grunder Age. Stratigraphy arw3 Petrogenesis of Rock from Hart Mountars M.les. T.
MS.
FJuclear Engmeenng Bmney MCFJP KCODE Calculations PatAey, K.
MS Nuclear Engmeenng Klem Flued and Thermal Calculatorts for Bdble Membrane Radiaton for Space ferlear Power Applications Pawlowski, R.
MS Nuclear Engmeenng Klem Temperature and Power Performance for T6..--, c Fuel Elements m an Advanced Space Power Plant Psepmeser, E.
PhD Pharmacy Ayres in Vrvo Behavsor of Detergent Solubdited Punhed Thrombomoduim on int'avermus Inrection into Rats Thesis research wtuch utdcred the OSTh M
wm
_s.
o.
Table VI C.2 (Contoued)
Student's Name Program Academic Department Faculty Advisor Theses Topic
- Pratt, D.
MS Radetson Health Johnson Undeoded
- Pyle, D.
PtO Oceanography Clwiste/Coller Trace Dement Analysis of Basaltic Glasses-Sowheast Irvjsan R4ge Saleh, H.
Pte Nuclear Engineerng Binney Fdtermg of Nai Detector Output
- Scterk, A.
PhD Cterrwstry Schmett INAA of Meteonte Materials
- Sctmeraer. R.
MS Physics Gardner Angular Correlation Exp. Wittwn the PAC Program
- Turrer, S.
MS Nuclear Engineering Binney Production of Medical Radxxsotopes Van Winkle, J.
MS Nuclear Engineenng Kleen Ox dation of Zircalloy-4 in Pressurized Water Reactor Conditions
- Walker, R.
PtO Geosciences Field Magmatism ar'd M.nerafszation of the Ash Peak area, Anzona; Petrotterr= cal Interpretations
- Yousef, S MS Nuclear Engineering Hggmbotham INAA of Beological Matenal for Se'ernum Zatun, L MS Nuclear Engineering Ken Cold Fusson Experiments Uf41VERSITY OF OREGOtJ
- Brandon, A.
PIO Geosciences Goles Late Cretaceous Gearmtes of Southeastern Bntish Columtxa Bryson, R.
MA Anthropology Ayres Geoctemical Sourcing of Littuc Matenals from Pohnpei Island. Micronessa Kataoka. O.
MA Anthropology Ayres Geocherrucal Sourcing of Littuc Materials from Pohnpei Island, Mrcronessa Mauricio, R.
MA Anthropology Ayres Geochemical Sourceg of lettuc Matenals from Pohnpei Island, Mecronessa Olmo, R.
MA Anthrepology Ayres Grud.cual Sourcing of Lattuc Matenals from Pohnpei Island, Macronessa
- Radosevich, S.
PtO Anthropology Lukacs Trace Gements in Ancsent Human Bone
- Skirmer, C.
PtO Anthropology Aikens Geotogic and Archaeological Obsidian From Westein Oregon
- Sonnenthal, E.
PtO Geosoences McB<ney Geochemical Evaluation of the Skaergaard irrrrusion. East Greenland
- Thesis research wtuch utilized the OSTR.
I&
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- -.u Table VI C.2 (Continued)
Student's Name -
Program Academec Department Faculty Advisor Thesis Topic HUMBOLDT STATE UNIVERSITY z.;
- Elder, D.
MS Geology Cashman Redefinition of Early Mesosoc Terranes Central Klamath Mountains, Califorrwa STANFORD
- DeBari. S.
Pte Geosciences Mahood Petrogenesis and Physical Evolution of tte Fiambala Gathronorite, Norttmestem Argentina UNIVERSITY OF CALIFORNIA-SAN FRANCISCO Williard, R PhD Hunt Nut known.
UNIVERSITY OF CAtlFORNIA-SANTA BARBARA
- Hoernie, K.
Pto Geology Tilton Petrochemistry of Volcaruc Rocks From tte Canary Islands UNIVERSITY OF CAtlFORNIA-LOS ANGELES
- Nelson, S.
PtO Earth & Space Science. Davidson Tertiary Magmatism of tte Colorado Plateau UNIVERSITY OF COLORADO
- Ball, T.
PtO Geology Farmer Isotope Study of Early Protozoc Crustal Growth in Souttem Wyoming
- Harrington, R.
Pts.
Geosciences Stern Pliocene and Quaternary Volcarwcs of tte Souttern Andes in Central Otwle UNIVERSITY OF NEW MEXICO
' Bryan, C.
Pto Geology Elston Petrogeneses of Volcarwc Rocks. SW New Mexico ard SE Arizona
- Tiesis research wtuch utilized the OSTR.
50 k-t w.c t
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4 Table VLC 2 (Contmuedl Student's Name Program Academic Department Faculty Advisor Theses Topic SOUTH DAKOTA SCHOOL OF teNES AND TECHNOLOGY -
- Fritch, E. -
MS ShearerFatterson Petrogenetic Relatons Between Gold Mbneralization and loneous intrussons in tte Black Hes, South Dakota TEXAS TECH. UNIVERSITY
- Jotoson, K.
MS
- Geosciences Barres Ongin of Gabbro and Peralummous Granstes, Klamath Mountams, Cairfomia RICE UNIVERSITY -
i Olsen Determme Element Mobikty m the Formation of Migmatetes
- Closman, C.
MS Geology TRINITY UNIVERSITY
- Pearce, P.
BS Geology Smith 1 Investigation into Crystat Fractionation and Magma Mixing LOUIStANA STATE UNIVERSITY -
- Sweeney, K.
MS Nuclear Science Center L Knaus' Recent Sediments From Wetlands Bordermg Northern Gulf of Mexico UNIVERSITY OF ROCHESTER
- Faggart, B.
PhD Geosciences Basu Crust-Mantee Geochemicas Interactions "Redgway, K.
PhD Geosoences DeCelles Determine Source Areas of Sediment Fellmg Along Denali Fat #t, Yukon Terntory, Canada UNIVERSITY OF NORTH CAROLINA
- Mdier, J.
PhD Geology G8arner Cenozoic Magmatism of the SW United States
- Thesis research which utdized the OSTR.
7
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' Table VI.C.2 (Continuedi :
- Student's Name
- Prograrn -
Academic Department Faculty Advesor Thesis Topic NORTH CAROLINA STATE UNIVERSITY
'Gandhon,G.
MS '
Manne. Earth and Fodor Mantle Charactenstes Beneath Northem Brazd
' Atmospheric Soence t#JtVERSITY OF FLORIDA '
- Murphy, J.
. MS.
Geology MueNer Madison Range Archean Rocks from Southem Montans
- Weyand. E.
MS Geology Muet:et Madison Range Archean Rocks from Southern Mawana l
- Thesis research which utilized the OSTP '
7s A
Table VI.C.3 Listmg of Major Research ard Service Projects Performed at the Radiation Center and Their Fundog Agencies Project Department ard Number User (s) Name institution Project Title Descnption Fundog Agency 118 G. Larson National Park Service, Crater Lake Study of the primary productiot. of phytoplanktort in Forestry, OSU OSU Cooperative Stud-Crater Lake usmg "C labelled substances.
ies Unit
- 165 J. Cooper NEA, Inc.
Pollution Studies NAA of sediments ard filter papers.
NEA, Inc.
192 N. Kerkvliet Vet Cd.d..e OSU Mece kradiation kradiation of mice in "Co irradiator.
Vet Med cme
- 231 H. Wollenberg Lawrence Berkeley GRP Project Fission track determination of urarwum distnbution Lawrence Berkeley S. Flexser Laboratories and abundance in fractured heated rock.
Laboratories
- 321 J. Steidtmann Geology, Unrversity of Foreland Investigation Fission track determination of the location of zwU, University of P. GroII Wyommg 2"U and Th in natural rocks and minerals.
Wyommg G. Lefebre
- 322 M. Roden Geology Rensselaer Fission Track Fission track determination of the location of Geology, Rensselaer R. Doneleck Polytechnic Institute Research urarwum and thorium in natural rocks and minerals.
Polytecfwuc Institute D.S. Miller
- 335 B. Kowalles Geology, Brigham Young BYU Fission Track Fission track dating of natural rocks and muerals.
Geology, Bogham University Study Young Urmversity
- 374 K. Tabbutt Earth Science, Dart-Fission Track Stud es FissM t ack irradiations in the thermal column.
Dartmouth College mouth College
- 377 B. Idleman Dept. of Earth Sciences.
Fission Track Age Fission track irradiations of apatites ard riccons in Western Carolma Western Carolma Univer-Dating the thermal column for age dating.
Uruversity sity
- 398 R.A. Schmitt Chemistry, Geology, Hegh Cascade Mafic INAA of mmerals separated from eclogete rock sam-Radiation Center, S_S. Hughes OSU Platform pies from Afnca.
OSU (Unfunded Researctd
'415 R.A. Schmitt Radiation Center, Pakistan Thrust Belt INAA study of maior and trace elee s nts in finnalayan Joint Radiation Cen-S.S. Hughes Geology, OSU rocks from the fold-ard thrust belt in Northern Paki-ter, OSU and NSF stan.
Grant
- Projects vwtuch utilized the OSTR.
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-.. ~,
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y,
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__.... y
- y y.,
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.. m Table VI.C 3 (Contmuedi Project
. Department and Number User (s) Name Institution Protect Title Descriptoon Fundwg Agency 422 S. Kaattari Microbiology, OSU Fish Lymphoctye Irradiation of fish fymphocytes in the "Co irradiator.
Microbiology M. Arkoosh irradiation
- 427 J. White Bureau of Mmes-Albany Netride inJusions in Development of INAA arw] neutron radeographic tech-U.S. Bureau of Titanium Alloys ruques to detect rwtride inclussons in titaruum alloys.
Mmes-Albany
- 428 R. Sctwnitt Chemistry OSU Meteorites INAA of metecrite samples.
NASA Y.-G.Liu
- C33 J. Longshore Humboldt State Univer-Trace Element Analy-Petrologscal and structuralinterpretation of volcanic USDOE (Reactor sity sis of Basalts and rocks from N. Cahforrua and S. Oregon.
Use Sharel Rhyoletes
- 441 P. DeCelles Geologeal Sciences, Meocene Volcaruc Use of INAA to study miocene volcanic influences on USDOE (Reactor University of Rochester Influences on Sedr-sedimentation in S. Cahfornia.
Use Sharel mentation
- 442 D. Miller Geology, Rensselaer Thermal History and Use of fission track analysis to determme age of USDOE (Reactor M. Roden Polytechnic Institute Age Determination in rocks.
Use Sharel R. Doneleck Rocks
- 443 J. Gardner Physics, OSU
Hf Angular Correla-Perturbed angular correlation measurements of con-Physics tion Experiment densed matter.
- 444 R. Duncan Oceanography, OSU "Ar **Ar Dating Produce 'Ar from K to measure radiometric ages Oceanography 8
on basaltic rocks from ocean basins.
- 445 R. Sctwnstt Geology / Chemistry, OSU INAA of Meteonte Determination of chemical compositoon for purposes NASA A. b ctulk Materials (Mokoia) of genetic modellwig/ trace element behavior.
- 452 R. Sctwnett Chemistry, OSU NAA of Sedwnent Determine Al content in selected sedwnent samples NASA Y.-G. Liu Samples from the Pacific Ocean.
- 455 S. Radosevich Anttwopology, University INAA of 20 TUFT Determmation of trace element contents in TUFT USDOE (Reactor J.Lukacs of Oregon samples samples.
Use Share)
- Projects which utilized the OSTR.
w m
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ur-
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Table VI.C.3 (Continuedi Project Departrrwent and -
Number User (s) Name Institution Project Title Description Fundeng Agency
'461 C. Aikens Antfwopology. University Characterizatson of Characterization of Western Oregon obsidan artifacts USDOE (Reactor C. Skinner of Oregon W. Oregon Obsidan by INAA of obsidan archaeological material.
Use Sharel Artriacts
- 462 C. Hun Geology. Unive,sity of Basaltic Feeder Dikes INAA to determme mmor and trace element content USDOE (Reactor Oregon for Picture Gorge of P>cture Gorge basatt samples.
Use Sharel Basatt Flows 467 H. Knaus Nuclear Science Center, Sod Horizon Markers INAA of Sm and Dy tracers in fresh water wettand USDOE (Reactor Louisiana State Universi-in Fresh Water Wet-habitat-peat samples.
Use Sharel ty lands 475 W. Ayres Anthropology. Uruversity Geochemical Sourcing INAA of basaltic bud &ng and quarry matenals for USDOE (Reactor of Oregon of Lithic Materials geochemeal characterization.
Use Sharet from Pohnpei Island.
Micronesia
'476 G. Farmer institute for Research in Cenozoic Volcarsc Characterization of mantle sources for magmas con-USDOE (Reactor Environmer'tal Scence.
Rocks in the Mogave tnbutmg to Mojave Desert volcarwc rocks.
Use Sharel University of Colorado Desert
- 478 A. Johnson Radiation Center Radiation Center Tours of the Ra&ation Center and reactor for vanous USDOE (Reactor Tours school (non OSU) groups on an as4equested basis.
Use Share) 479 D. Livesay CH M-Hdi Liquid Scintillation LSC counteng of samples for gross cr and S.
CHpl HeR 2
Countog (LSC) 480 A. Johnson Radiation Center -
RC Technical Support Tectwwcal support to tte state of Oregon to assest in Radiation Center B. Dodd to Oregon DOE and emergency preparedness for the MiE-TROJAN facili-J. Hegginbotham Department of Human ty.
Resources 481 L Winans Oregon Health Sciences Calibration of Rasa-Survey instrument cat *bration for the Oregon Health Oregon Health Scs-Uruversity tion Survey instru-Sciences Unrversity.
erces Urwversrty ments
- Projects which utilized the OSTR.
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Table VLC 3 (Contned)
Project Department and Number User (s) Name -
- Institution Project Tette Desenption Fun &ng Agency 482 D. Fox Vollum Institute. Oregon Cahbration of Ra&a-Survey instrument cahbration for the Vo#um Institute Vollum Institute Health Sciences Uni-tion Survey Instru-'
for Advanced Becmedical flesearch.
versity ments 483 J. Betschart Nuclear Engmeering.
Environmental Rasa-Perform envwonmental radiation measurements usmg Radation Center and OSU tion Monitoring at and other tectuwgues.
Honors Program Coal and Nuclear Plants-Honors 484 J. Higginbotham Radiation Center. OSU NAA Apphcations of a investigations into the utiktation of a Cf reutron Ra&ation Center S. Yousef Cf Sealed Source source for Neutron Actsation Analysis.
- 486 B. Singer Geology and Geophys-kradation of Geologe-kra& ate and shop rock samples to University of Wyo-Urvversity of Wyo-ics, University of Wyo-cal Samples ming mm ming 488 G. Little Ra&ation Safety Office.
Cabbration of Portable Cahbrate portable radiation survey instruments for Ra&ation Center OSU Survey instruments radiation users on OSU campus 489 N. Goevehnger Oregon State Health Cahbration of Rada-Casebrate portable radation survey instruments for Ra&ation Control Division. Radiation Con- -
tion Control Section Oregon Ra&ation Control Section.
Section 0S50 trol Section Portable Survey in-struments
- 491 R. Walker Geology, OSU Taylor Creek Rhyo-Determmata.vt of partition coeffkients for sarudines Ra&ation Center htes from the TayAv Creek thyohtes. New Mexico.
(Unfunded Research;
'496 G. Goles Geological Science, Picture Gorge Basalt Geocherr.ical study of melt segregation in thick 6ffer-USDOE (Reactor E. Sonnenthat Urwversity of Oregon Geochemistry ential flows of Picture Gorge basalt.
Use Sharel
- 499 P. DeCelles Geological Science, Uni-Paleocene to Eocene INAA of shale samples from Southeast Beattooth USDOE (Reactor versity of Rochester Synorganic Se& men-uphf t and Bighom Basin, Wyoming.
Use Sharel tary Rocks in Wyo-ming
- Projects which utilized the OSTR.
5 C1
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Table VI.C.3 (Contwiued)
Project Department and Number User (s) Name institution Project Title Description Fundwig Agency
- 501 C. Hull Geological Scsence, Disequehbrium Dating Mlot study to determine the feassbilety of disegurhbri-Geoloycal Science.
University of Oregon '
of Hydrothermal Cal-um dating of hydrothermal calcites.
University of Oregon cite
'504 B. Nelson Geo6ogical Sciences.
Chemecal Evolution of INAA to characterite the western margin of the U.S.
USDOE (Reactor University of Washing-Metamorphosed Sedi-Use Sharel ton ments and Basalts 506 J. Gardner Physics, OSU
.J
- of Angular Corre-Investigate microscopic structures and defect dynam-Physics, OSU H. Fuchs lation in Studies of ics of zwconia and its alloy by PAC.
R. Schwenker Zirconia and Zircorna Alloys 509 W. Barbat Levitronics (11)
Enhanced Bectrical Irradiation of phosphor bronze wire with XIV radia-Radiation Center Conductance in Metal tion to induce enhanced electrr,al conductance.
- 512 J. Higginbotham Nuclear Enganeering, Seierwum Concentra-NAA of water sampler af ter physical and chermcal Radration Center S. Yousef OSU tion in Oregon Sub-concentration of selen!um in the samples surf ace Ground Wa-ters.
515 M. Penner Food Science and Tech-Passage of Food INAA of rat feces to assess the rate of passage of Co Food Science and B. Luick nology OSU Components Through and Cr labelled food substances through the GI tract.
Techra9gy, Radia-the GI Tract of a Rat teon Center
- S16 W. Leeman Earth Sciences Div.,
Cascade Range Lavas INAA to assess tuneW compositional varia-Nateonal Scsence Rice University tions.
Foundation 519 B. Livingstone USEPA--Corvalks Instrument Calibration Cahtrate EPA portable radiation survey meters.
USEPA--Curvalhs J. Gile P. Monaco
- 521 J. Vance Geological Science, Uni-Fission Track Studies Thermal column irrediation of rircon and other sam-University of Wash-versity of Washington pies to induce frssion fracks in catcher foils for dat-ington, Dept. of ing.
Geolorcal Science I
- Projects which utilized the OSTR.
c)
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Table VI C.3 (Cont nued)
' Project Oepartment and Number User (s) Name Institution Project Title Description Fundmg Agency
- 522 S. Hughes Geology / Chemistry, OSU Characterization of Evaluate neutron flux intensaties, flux gradients and Radiation Center OSTR inf. ore Cd-temperatures inside Cd4sned irradiation tube.
Lined Irradiation Tube
- 524 L Taylor University of Tennessee Elemental Character-INAA of gedW samples for all detectable ele-University of Ten-iration of Mineral ments.
nessee--Geolog6I Separates and Bulk Science Rocks
- 530 L Duncan U.S. Forest Servke Bu-Forest Fire Investiga-INAA of one metal fragment and samples to be re-Bureau of Land R. Hogue reau of Land Manage-tion moved from chain saw.
Management ment
- S33 R. Collier Oceanography, OSU Sed.n.ents and Crust INAA for trace elements in Crater Lake sediments Oceanography R. Conard Materials from Crater and crust materials.
Lake 535 B. Nash U.S. Bureau of Moes-Instrument Calibration Calibrate Bureau of Mines portabac radiation survey U.S. Bureau of Albany meters.
Mwc-Albany Re-search Center
- 536 K. Krane Physics, OSU y-y Angular Correla-Prepare Er, Tm tracers for test G+ sol separations USDOE (Reactor for use in "# r y-y angular correlation study.
Use Sharel W. Loveland tions for "'Er E
- 537 R. Schmitt U.S. Bureau of Menes -
Gold in Novaculite INAA for determination of gold content in novactate U.S. Bureau of B. O'Connor from Arkansas.
Mines
- 541 B. Coll.er Marine Geology Ocean-Trace Elements in DNAA for trace elements in southern Oregon Coast Oceanograpty B. Conard ography, OSU Sediment Cores from sediment cores.
Southern Oregon Coast
- 542 R. Lawrence Geology, OSU Pakastani Grarmtes INAA to determine magor and trace element content Geology, OSU of granites from Pakistan.
- 544 B. Tansy _
NEA, Inc.
Reactor Irradiation of irradiation of sediments and filter papers, followed by NEA, Ire.
Samples for INAA shipment or on-site analysis, as appropriate).
- - Projects which utilized the OSTH.
y a
4 4
y m
.----mi<
1
_g Table VI_C 3 (Contmued)
Project Department and Number User (s) Name Institution Project Title Descnption Fundrng Agency
- 545 P. Mueller Geology, Urwversity of Complete INAA of Perform complete INAA on rart, geologc samples.
University of Florida Florida Geologic Samples
- S46 J. Doerges Radiation Safety anu Tantalurn Were Activa-Irradiate 10 pieces of I stw diameter Ta-181 wire to Uriversity of Wyo-Hazardous Materials tion for implanting in actueve Ta-182 activety of 100 pCi per wire station.
mmg Office. Uruversity of Toads (for Trackmg)
Wyom ng 547 B. Boese EPA, Newport Survey Instrumer:t Cahbrate GM and other portable survey meters.
USEPA Cahbration
- 548 R. Schmitt Chemistry, Radiation Major and Trace De-INAA of very smalllunar glass samples.
NASA Y.-G. Uu Center. OSU ment Study of Lunar Volcarmc Glasses 549 G. Little Radiation Safety, OSU Radiation Protection
Se shrpping package swipe activity determination.
Radiation Center
- 550 R. Walker Radiation Center, OSU Petrochemistry of Trace element determmation of alkah basalt nepheh-Radsation Center K.Honnie Urww. of Cahfortua, Volcaruc Rocks Asso-rute, tholevite, basarwte, magearite, and carbonatite Santa Barbara ciated with the Ca-lavas from the Canary Islands.
nary Island's Hot Spot 551 G. Keller V.P. for Research and Kiev Sod Analysis Gamma spectroscopy of soil from Kiev, USSR.
Radiation Center Graduate Studes. OSU 552 H Muren Sun Seeds Egg Transformation in inadsate ormon flowers using Co-60 to induce charg-Sun Seeds Orwon Flowers via Co-es in cell nuclei.
60 trradiation 553 P. Bottomley Microbiology. OSU Rhizobium Ecology soil sterihzation via irradiation en Co-60.
Merobiology 554 B. Robesen Oregon Department of Instrument Cahbration Instrument cabbraton of survey meters for PUC truck Oregon Dept. of D. Smith Energy for Oregon Dept. of inspectors.
Energy Energy 5
- Protects which utihzed the OSTR.
Om
-.. ~
g_____
___g Table VI.C.3 (Continued)
Project Deraftment and Number User (s) Name Instituten Project Title Description Fund.ng Agency
- 555 C. Bennett Intel Corporation Quantifcation of Quantify trace amounts of P in the presence of As in Intel Corporaten Trace Amounts of pure salscon semiconductors.
Phosphorus in Silicon Sensconductor Mate-rials 556
- 8. Wilson Southern Oregon State Neutron Survey Use of BF aeutron survey meter to determ.ne sur-Radiation Center a
College. Physics instrumentation for face dose rates on shipping contairer containing a Surveying Radioactive 500 mci AmBe neutron source.
Material Shepments
- S57 R. Walker Radiation Center.
ASTM Task Group's Standardization of peach and apple leaves for use as Radiation Center D. Becker National Institute of Biological Material standard reference materials.
Standards and Technolo-Quality Assurance gy Intercomparison
- 559 W. Loveland Chem.stry, OSU Vial Certification Test screwtop vials for use in the OSU TRIGA reac-Radiation Center tor.
- S59 J. Schmitt Battelle Norttmest Lab.
INAA of Katmai Elemental analysis of granetrie rock samples via Battette NW Lab.
J.Laul Fumuruul Surte INAA.
- 560 D. Pyle Oceanography. OSU Trace Dement Cfem-firadiation of basalt samples to determine trace ele-Oceanography istry of Basaltic Glass-ment chemistry.
es from the Southeast Indian Redge
- 561 W. Sandane Microbeology, OSU Patent infringement INAA of a powdered chemmal for Mg.
Mcrotnology Investigation
- 562 H. Brager Westinghouse Hanford Tantalum Content of Determination of Ta content of Y metal or Y hybrid.
Westinghouse Yttrium Hanford
- S63 D. Miller Rensselaer Polytechnic Thermal History of Analysis of U content of apatite and zircon for use in USDOE (Reactor Institute Sedimentary Basins fission track age determinations.
Use Share)
- Projects wluch utilized the OSTR.
3 (D
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-u. 4 g
o
- Teble VI.C.3 (Contmued)
Project Department and Number User (s) Name institution Project Title '
Description Fundmg Agency
- S64 C. Hull Geologscal Sciences.
Petrochemestry of Determmation of feeder ddtes for tte P6cture Gorge USDOE (Reactor University of Oregon Feeder Dikes fer the basalt by use of trace element characterization.
Use Share)
Picture Gorge Basalts, Oregon
- 565 G. Goles Geological Sciences, Gen :.wiL5try of '
Geochemical characterization of granitic rocks to USDOE (Reactor M. Patino-Douce Urvversity of Oregon Granites from tte estatAsh their petrogenesis and the tectonic impfsca-Use Share)
Achala Batholeth,.
tions of their formatiort.
Southeastern Sierras i
Pampeanas, Argentina
- S66 G. Goles Geological Sciences -
Geochemical Evolu-Irwestigation of the transport of elements by ctdorme USDOE (Reactor A. McBirney Uruversity of Oregon tion of the Skaergaard and sulfur-rich fluids af ter the mag natic stage of tte Use Steel E. Sonnenthat intrusion, East Green-witrusion has culminated.
land i
'567 G. Goles Geological Sciences, Geocherrucal Charac-Pett.Aiacid determenation of basalts and trachytes USDOE (Reactor R. Page Urwversity of Oregon terization of a Basalt-from the Talagapa Volcarwc Field to compare them Use Share)
S.Poma Trachyte Suite from with basalt-trachyte suites from other tectonic set-the Talagapa Volcarwc tings.
Field, Argentina
- 568 G. Goles Geological Sciences, Geochemical Charac-Petrochemical determination of igneous rocks from USDOE (Reactor University of Oregon terization of Igneous ite archaeologn at site of Pohnper.
Use Share)
Rocks from Pohnpei, Federated States of Micronessa
- 569 C. Stern Geological Sciences.
Pliocene and Quater-Interpretation of temporal changes in magmagmesis USDOE (Reactor R. Harrington Uruversity of Colorado nary Volcarwcs of tte processes and thest relation with tectonics along tte Use Share)
Southem Andes in Southern Chdemi oceanic-continental corwergent Central Ctwee plate boundary.
- 570 W. t.eeman Geology and Geophys-Geochemical Studies Evaluation of a primitnre intracceanic arc setting to USDOE (Reactor ics, Rice Uruversity of a Primitive Oceanic determine the subduction component of the magmas Use Share) island Arc-South without the interference of a sialic contammant.
Sandwich Islands
- Projects which utilized tte OSTR.
4 7
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Table VI.C.3 (Continued)
Project Department and tiumber User (s) Name Institution Project Title Description Fordeng Agency
- 571 C. Skirwer Anttropology, Urwversity Geochemical Charac-Use of abundances of trace elements in obsid:an arts-USDOE (Reactor of Oregon terization and Correla-facts as fa.vaus4s to determine the source loca-Use Share) tion of Geologic and t!ons and identify trading routes.
Archaeological Obside-an from Western Oregon
- S72 B. Nelson Geologeal Scsences, Geodonkist Charac-klentifcation of the African and European continental USDOE (Reactor University of WasNog-teristics of tre Varis-margin origins by comparing tfe Carborwferous to Use Sharel ton can Grarmtes Devonian age Variscan grarwtes.
- S73 J. Sctweber Geology, Uruversity of Geochmistry of Determine source terranes, fractionation of elements USDOE (Reactor Texas-Arkngton Shales from the West-during transport, and variations in weathenng intensi-Use Sharel em and Central Belt ty of the Proterozoc Belt Supergroup, Montana.
Basin. Montana
- f74 J. EcNeber Geology, University of A Geochemcal Sur-Determine tectonic setting Nd igneous environment USDOE (Reactor R. Schmerold Texas-Arhngton vey of Proterozoic of volcarwc rocks ard the source areas of ite sedi-Use Sharel Metasediments ard mentary rocks. TNs should elucMate early crustal Metavolcanics from tistory of East African craton.
Central EtNopia
- 575 P. Mueller Geology, University of Madison Range investigation of Archean rocks from the Madison USDOE (Reactor J. Murphy Florida Archean Rocks from Range to determine if they are en ancient analog of a Use Sharel E. Weyand Southem Montana enodern convergent plate margin.
- S76 K. Hoernte Geology, Uriversity of Geoctemistry of Development of petrogenetic models for the Gran USDOE (Reactor G. Tilton Cahforrua, Santa Barbara Basa6ts on Gran Canaria picrite-tholeiite through mehhtite suite, parte-Use Share)
H. Schmincke Canaria, Canary Is-utarfy if batch or fractional melting models are more lands appropriate.
- 577 J. Steiner Earth and Plaretary Geoctemistry of the Trace element characterization of various phases of Radetoon Center R. Walker Science, City Col!ege of Palisades Silt in tte the Palasades Sill to determine the origin of the mag-(Unfunded Research)
City Uruversity of New Area of Nyack. New ma and constrain the crystafleratier Nstory of the York: Radiation Center, York S II.
OSU
- Projects which utshzed the OSTR.
hn s
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Project Department and Number User (s) Name Institution Project Title Description Fundug Agency
- 578 C. Bames Geosciences. Texas Trace Element Geo-Trace element investgation to determme the geo-USDOE (Reactor Tech University cfemistry of Basalts chernmal characteristics of the sources of basaltic Use Sharet from the High Cas-Iavas and constrain the composition of parental cade Range. Southern magmas of the andesite lavas found in the southern Oregon High Cascades.
- 579 P. Verplanck C!RES, University of Comparison of the Both zones consist of suturing island arc terranes USDOE (Reactor G. Davidson.
Colorado; USGS, Den-Salmon Rever Suture, with contenental terranes, the geode. c ; character-Use Share) ver; Geosciences, OSU idate with the Indus iration of the two suture zones wn!I allow comparison Suture, northern Paki-of sumlanties and differences between the processes.
stan
- 580 G. Farmer Geological Sciences and A Nd isotopic Study To constram models for the genesis of Proterozoic USDOE (Reacts t l
T. Ball CtRES, Uneversity of of Early Proterozoc continental crust and for tre accretion of ttese crust-Use Sterel l
Colorado Crustal Growth in al segments to the margins of prei:xisting Archean g
Southern Wyommg contirental cratons.
- 581 W. Elston Geology, University of Geochemistry and To constrain the chemical histories of early versus USDOE (Reactor C. Bryan New Mexico Petrogeneisis of M4 latecupted volcanse rocks and to develop petro-Use Sha c)
Tertiary Volcanic genetic models involving partial melting of lower Rocks, Southwestern crustal rocks.
New Mexico and Southeastern Arizona
- 582 J. Longshore Humboldt State Univer-Redefinition of Early Reexamination of the volcanc units in the Klamath USDOE (Reactor S. Cashman sity Mesozoic Terranes.
Mountains to establish inter-terrane correlations arx1 Use Sharel D. Elder Central Klamath determine tectonic setting of volcanic rocks.
Mountains. Califomia
- 583 R. Walker Radsation Center Petrochemical Com-An investigation using trace element contents of the Radiati.. % er t
parison of the Sonya 20 my old Sonya Creek eruptrve center and the 0.8 (Unfunded Research)
Creek and Sanford my old Sanford volcano to characterize the volcanism Duptive Centers, of the Wrangell area of southeast Alaska.
Alaska
- Projects which utilsted the OSTR.
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- 4 7-
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Tat /e VI.C.3 (Contmuedi Project Department and Number User (s) Name Institution Protect Title Description Funding Agency
- 584 A. Johnson Radiation Center Radiation Center Tours of 1:e Radiation Center and TRIGA reactor for USDOE (Reactor Tours various nonOSU academic groups on an as<equest-Use Sharel ed basis.
- 585 S. Lewis Geology, Montana Col-Correlation of Precam-To establish geochemical criteria for the comparison USDOE (Reactor M. Bartholomew lege of Mineral Scie ee brian Crystalline Mas-of Precambrian crystalline massifs that underle meta-Use Sharel and Technology sifs in the Appala-morphic and plutonic rocks of tte Appalachian chian Mountains.
orogen.
Eastern Uruted States
- 586 S. Hughes Chemistry, Montana Petrology and Geo-To evaluate the petrogenesis of magma types associ-USDOE (Reactor College of Mineral Sci-chemistry of Colum-ated with CRB feeder dekes, to study the tectonic Use Sharei ence and Technology bia River Basalt Feed-relations of early CRB eruptions in eastem Oregon, er Dikes in Eastem and to gain knowledge of feeder deke interaction with Oregon the country rock through which ttey erupted.
- 587 J. Davidson Earth and Space Scienc-Tertiary Magmatism To evaluate the dafferentiation hrstories and degree of USDOE (Reactor J. Nelson es, Univ. of Cahlornia, of the Colorado Pla-crustal interaction of volcanic rocks from the Herwy Use Sharel Los Angeles teau and La Sal Mountains Utah.
- 588 J. Steiner Dept. of Earth and Plan-REE Charactenstics of To map tre various magmatic pulses of tte Pahsades USDOE (Reactor etary Sciences, City Col-the Pahsades Magma Sdl using REE content, to identify the irutial chemical Use Sharel lege of City University of Pulses. New York and signature of the pulses, and to establish chermcal New York New Jersey variations resulting from internal differentiation fol-lowing emplacement.
- S89 G. Goles Geological Sciences.
Relationstwps Be-Geochemical characterization of ceramic artifacts USDOE (Reactor R. Bryson Anthropology, University tween Ceramics and from Nan Madol archaeological complex to trace Use Sharel of Oregon Pohtical Organization trading routes and estabhsh pohtical boundanes and in Prehistoric Pohrwei, interactions.
Micronesia
- 590 G. Goles Geological Sciences, Late Cretaceous Gran-Geochemical characterization of accreted terranes USDOE (Reactor A. Brandon University of Oregon ites of Southeastem and the petrogeveses of plutons that mark tie suture Use Sharel British Columbia boundaries.
h
- Projects which utas. red the OSTR.
tJ G3
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- ~ - - - -
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,u y-Table VLC 3 (Coronuedi Project Departrrent and -
Number
~ User (s) Name -
Institution.
~ Project Title Description Ftm&ng Agency
- 591 A. Basu Geological Sciences.'
Nd-Sr and Pb4sotope To evahjate crust <nantie geochemical interactens.
USDOE (fleactor B. Faggart. Jr.
University of floctester Geocher wstry in Use Sharel Crust-Mantle Evolu-tion! Selected Stud-ies from the Kings Mountain Belt of the Carohnas and from the Adirondacks in New York
- 592 AL Glarner -
Geology, Ureversity of Geochemistry. Isoto-Trace elenent data to constrain models for the Me-USDOE (Heactor J. M Her North Carohna -
pic Composition, and -
sozoic tecto wc evoluten and possible source rocks Use Sharel Age of Mesozoic for Cenozoic magmatism of the sourtwvestem Uruted Plutonic Rocks in the States.
Western and Central Mosave Desert 593 N. Kerkvliet Veterinary Me&certij, Benavior of Finer Cens lera&ation of fdler cets in
- Co facety.
Vetennary Med. cme OSU for T-Enzymes 594 B. Grappi Society of American Use of Ra&ation:a lecture to SAME on the apphcations of NAA in the Ra6ation Center C. Kelly Mditary Engmeers. OSU Geology geological soences.
(Unfunded Researchl
- 595 C. Barres Geosoences, Texas Onge of Gabbro and.
Trace element investigation to model the efferentia-USDOE G4eactor M. Bames
~t;h Unrversity Peralummous Gran-tion history of the Vesa Blufts pluton tdtimately to Use Sharel K. Johnson ites. Klamath Moun-provice informaten concemmg the orige of peratumi-tains. Califomia nous granates (e.g. crystal fractenation vs. crustal mettegi.
596 G. Davies Oregon Health Soences Gamma Ray irra&a-CoRagen irrasated to a gamma dose of 2.5 Mrads.
Oregon Health Sci-J. Bentley Uruversity tion of Dned Proten ences University (Coltageni
'597 J. Laul Battatie Northwest Lab.
Rare Earth Tracer Aa waters of housd tracer samples to assess rare USDOE. Battene J. Schmitt Study-eaah content and stwpment to BNW for countmg.
I
- Projects which utdized the OSTR.
$3 b
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_y Table VLC.3 (Continued)
Protect Department ard Number User (si Name Institution Project Title Dwiption Fundmg Agency 598 R. Knaus Louisiana State Uruversi-Gamma Spectroscopy Count two barnacle samples to assess radionucIwe Radiation Center tv of Bamacle Sarrples uptake from environment.
(Unfunded Research)
- 599 A. Robinson Nuclear Engineenng, Study of Instrumenta-Famsfearia 4tson with reactor operation and concepts.
International Atorruc R. Abdur OSU; international tion and Control Re-Energy Agency Atomic Energy Agency lated to a Research Reactor
- 600 B. Patrick Geoscience, New Mexi-Fission Track Dating Irradiation of rircons and apatites in ttermal column New Mexco Tech co Tech of Geological Samples for age dating of geologic sas.iples.
- 601 M. Samuelson OreMet Titarwum Radrography Training Research reactor orientation and introduction to Radiation Center capabilities of neutron radKgraphy.
602 M. Bloomfield Text review, advice, A review of the radioicgical portions of tte text for Radiation Center consultation by Dr.
the fif th edition of " Chemistry and the Living Organ-Dodd esm" by Bloomfeeld.
- 603 G. Goles Geological Sciences, Elemental Composi-Chemmal characterization of prehistoric potshards USDOE (Reactor R. Wden Anthropology, University tion of Ceramic from northeast Thailand to determine if distinctive Use Share) of Oregon Pastes from the Huay ceramsc traditions were executed using specahc clay Sai Khao Basin, sources.
Northeast Thaifard
- 604 G. Goles Geological Sciences.
Elemental Composi-Chemical characteization of prefustoric buildog USDOE (Reactor W. Ayres Anthropology, Urwversity tion of Stone Budding material from Nan Madol archaeological sste Pohnpes Use Sharel R. Mauricio of Oregon Material from Nan Island to determine the provenance of the stone.
Madol, Pohnpei Is-land, Meronesia
- 605 A. Mathis Geosciences OSU Age, Stratigraphy, Using geochemical data, especially trace elements, to Radiation Center and Petrogenesis of determire the age, stratigraphy, and plausible petro-(Unfunded Research)
Volcanic Rocks from genetic models for Basin and Range volcaruc rocks Hart Mountain, South-from Hart Mountam, southeastern Oregon.
eastern Oregon Projects which utilized the OSTR.
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Table VI.C 3 (Continued)
Project Department and Number User (s) Name institution Protect Title Description Funding Agency
'606 F. Sutterland Australian Museum Trace Element Char-Determine the range of trace element contents of the Radiation Center acterization of Austra-various groups of zircons from Australia. This infor-(Unfunded Research) lian Gem Quahty mation could provide important information concern-
~Zercons ing zircon crystallization and sources.
- 607 A. Babb Nuclear Engineering, TRIGA Reactor Opera-Operation of the OSU TRIGA reactor for training USDOE (R actor University of Washing-tor Training purposes.
Use Stere) ton
'608 R. Knaus Nuclear Science Center, Wetland Accretion Determination of soil movement using stable REE USDOE (Heactor D. Van Gent Louisiana State Universi-and Erosional Pro-tracers during the enlargement of
- holes
- in brackish Use Share)
K. Sweeney ty cesses water wetlands in south Louisiana.
- 609 R. Fodor Marine, Earth and Atmo-Petrology of Tertiary Trace element contents of xenoliths and megacrysts USDOE (Reactor A. Sial spheric Sciences, North Basalt and Ultramfaic to determine mantle heterogenesty beneath northern Use Share)
G. Gandhok Carohna State Univ.
Xenohths and Mega-Brazil and of basalts to distinguish between continen-crysts: Mantle Char-tal and oceanic magmatism.
acteristics Beneath Northem Brazil
'610 P. DeCelles Geological Scaences, Middle Tertiary Sedi-Trace element contents of sandstones and conglom-USDOE (Reactor K. Ridgway University of Rochester mentation in Stnke-erates ttut fill small basins along the Denati fault in Use Share)
Slip Basins Along the Yukon Territory to correlate with nearby : source areas Denali Fault, Yukon and estabhsh provenance.
Territory, Canada
- 611 D. Smith Geology, Trinity Univer-Petrologic and Geo-The determination of trace element contents to con-USDOE (Reactor P. Pearce sity chemical Characteris-strain possible petrogenetic processes such as crystal Use Share) tics of Cretaceous fractionation or magma mixing.
Hypabyssalintrusions in Central Montana and Precambrian Grarutoids from Cen-tral Texas
- Projects which utinzed the OSTR.
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y,-
Table VI.C.3 (Continued)
Project Department and Number User (s) Name Institution Project Title Description Funding Agency
- 612 F. Beardsley Anthropology, University Easter Island Obsidian The determination of trace element contents of USDOE (Reactor of Oregon Studies: Research on obsidians from Easter island to establish source areas Use Sharel Source Variabelity and and trading routes of artifacts.
Artifact Distribution
'613 V. Sisson Geology and Geophys-Trace Element Model-The determination of trace element contents of dif-USDOE (Reactor ics, Rice Uruversety kng of Open and ferent types of migmatite to establish characteristics Use Share)
Oosed System M g-of movement for various elements during formation.
matites
- 6t4 G. Goles Geological Sciences, Tectoruc implications Geochemscal characterization of the latterally exten-USDOE (Reactor J. Stimac University of Oregon of Structural and sive &sh-flow tuff uruts of the Owyhee Uplands of Use Sharel Paleomagnetic Fea-eastern Oregon.
tures of Late Miocene AstrFlow Tuffs of Eastem Oregon
- 615 S. DeBari Geology, Stanford Uni-Petrogenesis and Tie ctemscal evolution of a mantle-derived mafic USDOE (Reactor versity Physical Evolution of intrusion from its earhest crysta:fization through ex-Use Share) the Fiambala Gab-tensive fractionation and assimilation of country bronorite, Northwest-rock.
ern Argentina
- 616 J. Gardner Physics OSU H.gh Pressure Per-Irradiation of ZrO, to assess properties under tugh Physics L Dundon turbed Angular Corre-pressure using PAC.
lation (PAC)
- 617 J.Laul Battelle Northwest Lab.
INAA of Katrnas Fu-Irradiation of geologic and meteoritic samples for Battelle NW Lab.
J. Schmitt marole and flowardite INAA determination of trace elements and rare Meteorites earths.
- 618 K. Mcdonald Applied Chemistry, MB Feasibihty Study-Develop a fast and cost-effective INAA procedure for Radiation Center Research INAA Measurement of measurement of iodene on wood samples.
lodine-containing Wood Preservative
- Projects which utihzed the OSTR.
hm 4
y.
__,- - - - _g Table VI.C.3 (Continued)
Project Department and.
' Number User (s) flame Institution Protect Title Description Fundmg Agency 619 G. Little Radiation Safety Office, Gamma Screenmg of Screen samples for possible gamma radiation.
Radiation Center R. Farmer OSU Swipes
- 620 R. Schmitt Chemistry, OSU INAA of Standard kradiation of (nor>-glassi standard lunar samples for NASA, University of L Taylor University of Tennessee Lunar Samples subsequent INAA.
Tennessee 621 B. Stevenson Reed College Chemical Dosimetry kradiation of a chemical dosimeter to 500-1000 Gy Reed Co88ege usmg the "Co irradsator.
622 W.Ctism "Co kradiation of krediate wood samples to be used in veohn bridges in Radiation Center Wood Samples
- Co irradetor.
fUnfunded Research) 623 S. Gutenberger Microtuology, OSU Gamma krad>ation of kradiation of bactenal cutttre to 4.5 x 10' rads.
Merobiology Bacteria 624 R. Eastborn Corvasis Clinic Thyroid Bioassay by Morntor thyroids of 6-8 people from the Corvaths Radiatm Center Counting Chnic on 2/6/90.
- 625 A. Klein Nuclear Engmeeting, Cold Fusion CeII Resi-Chermcal identifcation of metalhc residues found in Radiation Center OSU does cold fusion cells foGowing experimental rur (Unfunded Resewchl
- 626 G. Goles Geologecal Sciences, Geochemcal Charac-Petrochermcal determmation of basalts and trachytes Get%gcal Sciences.
R. Page University of Oregon terization of a Basa!t.
from the Talagapa Volcanic Field to compare them University of Oregon Trachyte Suite from with basalt-trachyte suites from other tectonic set-the Talagapa Volcanic tings.
Field Argentina 627 G. Little Radiation Safety Offece, Radiation Protection Gamma analysis of one oceanic chemrey sample to Radiation Center R. Farmer OSU of OSU Research determme level of naturallyeccurring radioactive Personnel and Re-material in the sample.
search Laboratory I
- Projects wtuch utilized tte OSTR.
6 c) 4,.J. _ ;..,..
,J..._,
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Table VI C.3 (Contoued)
Project
_ Department and Number User (s) Name lastitutKm Project Title Description Funding Agency
- 628 G. Harper Geological Sciences, Oceanic Faulting and Tte chemical evolution of the Josephme ophohte.
USDOE (Reactor State University of New Hydrothermal Meta-Klamath Mtns., Cahfomia appears to be related to Use Share)
York morphism of the Jo-freezing" of magma chambers extensional faulting, sephine Ophsohte, and and periodec eruption of lava. Trace element geo-its Relation to Frac-chemistry may defoe the roles of these processes in tionation in Dtkes and the formation of oceanic crust.
Lavas
'629 C. Shearer Inst. for the Study of Petrogenetic Relations investigation of the role of spatially associated igne-USDOE (Reactor C. Patterson Mrneral Deposits, South Between Gold Miner-ous intrusions with sedementary hosted epethermal Use Share)
E. Fritch Dakota School of Mines afization and Igneous gold mineralization in the Black Hills, South Dakota.
and Technology intrusions in the Black is there a specific geochemistry of mineraliz ng Hills. South Dak ota magmas?
'630 D. Parsons Evaluaton of Radsation irradiation of one topar sample in a cadmium box for D. Parsons Levels for Irradiation approximately 20 MW hours in the TRIGA reactor.
Gemstones.
Quantitative gamma analysis of tfe irradiated gem-stone and one previously irradiated gemstone.
631 M. Mok Horticulture. OSU Induction of soma-Attempts are made to obtain mutants of quince with Horticulture clona! variation in enhanced tolerance to low Fe (leaf discs are irradiat-quince.
ed and plants are regenerated).
632 R. Thompson Oregon State Police Radiation Survey Cahbration services for portable radiation survey Oregon State Pohce, instrument Cahbration instruments.
Crime Laboratory for Oregon State Police Crime Labora-tory a ttelle Northwest Lab.
Flood Basalts /Geo-Activation of samples for INAA.
Battelle NW Lab.
- 633 J.Laul a
J. Schmitt chemical Megration
'634 S. Binney Nuclear Engineering Production of Medical Determmation of production rates and ur*nown or Nuclear Ergineerirg Radioisotopes poorly known cross sections for radioisotopes of medical interest.
I
- Projects which utilized the OSTR.
6 to
.o,.
y 7,.
y y - --- -
y,-
7 Table VI.C.3 (Continued)
Project Department and Number User (s) Name institution Project Title Description Funding Agency
- 035 J. Dilies -
Geoscences OSU Ore Genesis, Exam-Determination of trace element contents of altered Geosciences, OSU pies from Pakistan and unaltered geologic material from various ore deposits in Pakistan. -
- 636 A. Mathis Geosc ences, OSU Age, Stratigraphy, Use of geochemcal data, especadly trace elenwnts, Radiation Center and Petrogenesis of to determine the age, stratigraphy, and plausd>le (Unfunded Research)
Volcanic Rocks from petrogenetic models for Basin and Range volcariic Hart Mourstain, South-rocks from Hart Mountain, southeastern Oregon.
eastern Oregon -
- 637 M. Strecir Geosoences, OSU Petrology and Geo-Use of geochemscal data, especially trace elements, Radiation Center chemistry of the Rat-to determine the age, stratigraphy, and plausible (Unfunded Research) tiesnake Tuf f, West petrogenetic models for. the Rattlesnake Tuff.
Central Nevada
- 638 E. Schuetfort Geosciences. OSU Petroiogy and Geo -
Use of geochemical data, especially trace elements, Radiation Center chemistry of the to determine plausible oetrogenetic models for the (Unformed Research)
Cherry Creek Pluton, Cherry Creek plot on.
Whitepine County, Nevada
- 639 R. Collier Oceanography, OSU Trace Elements in.
INAA of oceanographic sediment samples to deter-Marine Geology B. Conard Sediment Cores and rntne trace eh composition.
Sediment Traps from Southarn Oregon Coast 640 J. Higginbotham Radiation Center, OSU -
Investigation of the Dose response of glass personnel radiation dosime-Radiation Center Ress,anse of Glass ters.
Calibration Capsules to High Energy Gam-ma Ray irradiation 641 J. Higginbotham Nuclear Engineering,,
Boy Scout Atomac -
Radiation Center equipment and personnel support Radiation Center J. Reyes OSU; American Nuclear Energy Merit Badge for 6 hour Merit Badge class.
Society
'
- Projects which utilized the OSTR.
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__ __________ ____,__________- _ - ~
. =.
Table VI.C.3 (Continuedi Project Department and Number User (s) Name Institution Project Title Description Fundmg Agency 642 J. Bentley Oregon Health Sciences Collagen irradiation Research and development of collagen for burn treat-Oregon Health Sci-G. Davies University ment.
ences University
- 643 W. Sandine Microbiology, OSU Patent infringement INAA of one powdered chemecal sample ~ Biogen
- for Mecrobsology T. Whitehead Irwestigation Al, Ca, and Mg.
644 J. Ayres Pharmacy. OSU in vivo behavior of Radsotracer study using S and 32sl injected into Pharmacy E. Piepmeier detergent-solubihzed laboratory rats.
purified thrombomod-ulin on intravenous injection into rats 645 C. Davis Springfield Utahty Board-Radon Measurements Assist Springfield Utikty Board (Water Departnwnt)
Radiation Center
-Water Dept.
in Water with radon measurements in water.
646 U. Farber International Educatiort Radiological Rasks of Evaluation of the radsological risk of Isvmg in Kiev, Radiation Center C. Gildersleeve OSU Living in Kiev USSR. Write up two page letter. Present informa-tion and answer questions.
647 J. Gardner Physics OSU Radioactive Material Shipment of approximately 1 mci of '"In to the Physics Shipment University of Maryland.
- 649 R. Seymour EG&G Ortec Software Beta Testing instrumental Neutron Activation Analysis (INAA) of Radiation Center 16 standards.
650 J. Ayres Pharmacy, OSU in vivo behavior of Provide Radiation Center general onentation, supple-Pharmacy detergent-so!ubdized mental radioactive material user orientation, and purified thrombomod-training in laboratory techniques (one week duration) ulin on mtravenous for one gradute student.
iriection into rats
- Projects which utdized the OSTR.
$b a
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VI-32 L
i 1.
Neutron Activation Analysis 1
o' Neutron activation analysis (NAA) stands at the forefront of techniques for the quantitative multi-element analysis of major, minor, trace and rare elements. The f
principle involved in NAA consists of first irradiating a sample with neutrons in a nuclear reactor such as the OSTR to produce specific radionuclides. After the irradiation, the characteristic gamma rays emitted by the decaying radionuclides are quantitatively measured by suitable semiconductor radiation detectors, and the I
gamma rays detected at a particular energy are usually indicative of a specific radionuclide's presence. Data reduction of gamma ray spectra by means of a computer then yields the concentrations of various elements in samples being studied. With sequentialinstrumental NAA it is possible to measure quantitatively about 35 elements in small samples (5 to 100 mg), and for activatable elements, the lower limit of detection is on the order of parts per million, or parts per billion depending on the element.
The Radiation Center's NAA laboratory has analyzed for the major, minor, and trace element content in many thousands of samples covering essentially the
. complete spectrum of material types and involving virtually every scientific and 0
technical field.
i While some researchers perform their own sample counting on their own or on Radiation Center equipment, the Radiation Center provides a complete, NAA service for researchers and others who may require it. This includes sample preparation, sequentialirradiation and counting, and data reduction and analysis.
Data on NAA research and service performed during this reporting period are included in Table VI.C.3.
3 i
o 1
1 VI33 i
2.
Forensic Studies Neutron activation analysis can also be advantageously used in criminal investigations. The principle underlying such application usually involves matching h
trace elemer.t profiles in objects or substances by NAA. This in turn can help identify materials or products (e.g., identify the manufacturer of a given object),
and in some cases can match bullets and other materials recovered from a victim to similar materials obtained from suspects. Materials which have been analyzed by the Radiation Center f or forensic purposes include bullets, metals, paint, fuses, coats, glass, meat, and salts, i
Foronsic studies performed in this reporting period are included in the listings in Tables VI.C.1 and VI.C.3.
3.
Irradiations As described throughout this report, a major capability of the Radiation Center involves the irradiation of a large variety of substances with X rays, gamma rays o.
and neutrons. Detailed data on these irradiations and their use during this reporting period are included in Part 111 as well as in section C of this part.
o 3
4.
Radioloaical Emeroency Resoonse Services The Radiation Center has an emergency response team capable of responding to.
all types of radiological accidents. This team directly supports the City of Corvallis 1
and Benton County emergency response organizations and medical facilities, in addition, most members of the team have been certified as Regional Radiological Technical Assistants (RRTAs). As a result, these individuals are authorized to provide assistance at the scene of any radiologicalincident anywhere in the state l
of Oregon on behalf of the Oregon Radiation Control Section and the Oregon I
Department of Energy.
i e
The Radiation Center maintains dedicated stocks of radiological emergency
~
response equipment and instrumentation. These items are located at the Radiation Center, at the Good Samaritan hospital, and in the regional hazmat vehicle operated by the city of Corvallis, d
-L E
VI34 i
i
~
During the current reporting period, the Radiation Center emergency response team conducted several training sessions and exercises, but was act required to respond
{
to any incidents, in conjunction with the OSU Department of Nuclear Engineering, Radiation Center staff provide on going support to the state of Oregon's emergency response plan for the Trojan Nuclear Power Plant. About seven persons residing in the Radiation
?
Center hold either primary, second shift or alternate positions in the Trojan Emergency Plan, and would work in the Emergency Operations Center in Salem, or in the Emergency Operations Facility at Trojan in the event of an incident.
y h-During the past year, Radiation Center Personnel attended training sessions, participated in drills and exercises, and provided advice relating to emergency i
response to a Trojan incident, but no one was required to respond to a real emergency,
-?
5.
Trainino and Instruction In addition to the academic laboratory classes and courses discussed in Parts Ill.A.2,' lit.E and VI.B. and in addition to the routine training needed to meet the requirements of the OSTR emergency response p;an, physical security plan and operator requalification program, the Radiation Center is also used for special training programs, Radiation Center staff are well experienced in conducting these special programs, and regularly offer training in areas such as research reactor operations, research reactor management, research reactor radiation protection, I
radiological emergency response, 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: visiting faculty and research scientists: Internationai Atomic Energy Agency (IAEA) 5 fellows; special short term courses; or individual reactor operator or health physics training programs. During this reporting period there were four visiting scientists E
VI 35 and special trainees. One IAEA fellow underwent trainir.g in instrumentation and 1
control for research reactors. This training was performed at the Radiation Center 1
under the auspices of the Nuclear Engineering Department. The fellow was from Bangladesh and the total period of his fellowship was six months, in addition, two visiting scientists, one from Japan and one from Sweden, worked in the field of nuclear chemistry under the direction of Dr. Loveland. Finally, the last special
{
trainee came from the Oregon Episcopal School and was trained to perform dose calculations arising from routine releases of airborne radioactive material.
6.
Radiation Protection Services The primary purpose of the radiation protection program at the Radiation Center 1
is to support the instruction and research conducted at the Center. However, due to the high quality of the program and the level of expertise and equipment available, the Radiation Center is also able to provide health physics services in support of the OSU Radiation Safety Office and to assist other state and federal agencies. The Radiation Center does not compete with private industry, but supplies health physics services which are not readily available elsewhere. In the case of support provided to state agencies, this definitely helps to optimize the utilization of stata resources.
The Radiation Center is capable of providing health physics services in any of the areas which are discussed in Part V. These include personnel monitoring, radiation
= surveys, sealed source leak testing, packaging and shipment of radioactive materials, calibration and repair of radiation monitoring instruments (discussed in detailin Section VI.C.7), radioactive waste disposal, radioactive material hood flow surveys and radiation safety analysis and audits.
a-l in the current reporting period the Radiation Center health physics program
['
supported the OSU Radiation Safety Office by performing gamma spectroscopy on a number of charcoal filters and paper smears to identify possible airborne or surface contamination, by assisting the of fice with equipment and instrumentation needs, and by performing instrument calibrations for a number of organizations.
l l
FM
r VI36 7.
RadioloaicalInstrument Renair and Calibration 4
While repair of nuclear instrumentation is a practical necessity, routine calibration C
of these instruments is a licensing and regulatory requirement which must be met.
As a result, the Radiation Center operates a radiation instrument repair and calibration facility which can accommodate a wide variety of equipment, b
The Center's scientific instrument repair facility performs maintenance and repair on all types of radiation detection and other nuclear instrumentation. Since the Radiation Center's own programs regularly utilize a wide range of nuclear instruments, components for most common repairs are often on hand and repair time is therefore minimized.
g In addition to the instrument repair capability, the Radiation Center has a facility for calibrating essentially all types of radiation monitoring instruments. This includes typical portable monitoring instrumentation for the detection and measurement of alpha, beta, gamma and neutron radiation, as well as instruments designed for low level environmental monitoring. Higher range instruments for use
-in radiation accident situations can also be calibrated in most cases, instrument calibrations are perf ormed using radiation sources certified by the Nationallnstitute of Standards and Technology (NIST) or traceable to NIST.
Table 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, while _ Table VI.C 5 shows instruments calibrated for other OSU departments and non OSU agencies.
8.
Consultation
['
Radiation Center staff are able to provide consultation services in any of the areas discussed in this annual report, but in particular: research reactor operations and 0
use, radiation protection, neutron activation analysis, neutron radiography, radiological emergency response and radiotracer methods.
J
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c Records are not normally kept of such consultations as they often take the form of telephone conversations with researchers encountering problems or planning the.
t
' design of experiments. Many faculty members housed in the Radiation Center-
~
W
..have on going consulting functions with various agencies,in addition to sitting on numerous committees in advisory capacities, t
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i VI38 b
Table VI.C,4 b
Summary of the Types of RadiologicalInstrumentation Calibrated
'to Support the OSU TRIGA Reactor and the Radiation Center Type of Instrument Number of Calibrations Radiation Center instruments GM Detectors 87 lon Chambers 31 Alpha Detectors 4
Neutron Detectors 6
Micro R Meters 6
Mini Detectors 30 J
Civil Defense Detectors 28 Personnel lon Chambers 113 i
Support Agency Instruments Corvallis Fire Department 4
Good Samaritan Hospital 3
(Corvallis, OR) q
-TOTAL 312 o:
c o
u
~
VI39 e
a-Table VI.C.5 g,
Summary of RadiologicalInstrumentation Calibrated to Support Other Agencies Number of Calibrations OSU Departments Agricultural Chemistry 1
. Animal Sciences 1
Biological Chemistry 3
Botany 5
Crop Science 1
Fisheries and Wildlife 2
Food Science 1
Horticulture 1
Microbiology 1
Radiation Safety Office 7
Veterinary Medicine 2
b f':5 Non OSU Agencies U.S. Bureau of Mines-1 1U.S. Environmental Protection Agency 5-
"~
U.S. Forest Service
'2 Oregon Health Sciences University:
16 Oregon State Health Division 3
Oregon Public= Utilities Commission 5
= Oregon Department of Energy '
6 Oregon State Police Crime Lab 1
- Vollum Institute, OHSU 3
- TOTAL 67
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- t i
m ,,,,.g 4 g L i PART Vil 6 WORDS e 1 A. Publications in Print
- 'g,.
implications for Andean ensialic orogenesis," Earth and Planetary Science Letters, in press. Binney, S.E., B. Azim and C.D. Peterson (1989), " Elemental composition of the Very Heavy Non magnetic Fraction of Pacific Northwest Beach Sands," Oreaon Geoloav, 51(6), p.130.
- Basu, A.R., M. Sharma and P.G. DeCelles (1990), "Nd Sr isotopic provenance and trace element geochemistry of Amazonian foreland basin sands from Peru and Bolivia:
Binney, S.E. and. A.G. Johnson (1989), " Qualitative Assessment of the Value of the OSU TRIGA Reactor," Trans. American Nuclear Society,60, p. 255. Binney, S.E., L.L. Zahm, A.C. Klein, J.N. Reyes, Jr.. J.F. Higginbotham, A.H. Robinson i g-and M. Daniels,(1990), " Experimental Investigations of the Electrolysis of D 0 2 .Using Palladium and Platinum Electrodes," Journal of Electroanalvtical Chemistry, 281, pp. 313 321. b
- Binney, S.E. and A.J.M. Bakir (1989), " Design-and Development of a PC based Reactivity Meter for a Research Reactor," Nuclear Technoloav,85, p.12.
- Butcher, D.P. and M. McCurry (1990), "Nd Sr Isotope systematics and eruptive
16-17. " Butcher, D.P., M. McCurry and G.L. Farmer (1989), " Evolution of the early Oligocene Organ cauldron, south central New Mexico," (abstract)lnternational Association of volcanoloav and Chemistry of the Earth's Interior Continental Maamatism Abstracts. New Mexico Bureau of M:ngLand Mineral Resources, Bulletin 131, p. - 35. ' Cole, R.B. and P.G. DeCelles (1990), " Tectonic implications of Early Miocene volcanic rocks, San Joaquin basin," American Association of Petroleum Geoloaists Abstracts,in press, f ' Cole, R.B. and P.G. DeCelles (1990), "Subaerial to submarine transitions in 'Early b Miocene pyroclastic flow deposits, southern San Joaquin basin, California,. Geoloical Society of America Bulletin, v.102, in press. l* I. Daniels, M. and L.P. Hart (1989). " Lifetime Evidence for a Weak Lowest-Lying Electronic I State of Adenosine," Biochem. Biochvs. Res. Comm.152, p. 781-787. l I
- characteristics of the Organ Cauldron, south central New Mexico,*' New Mexico Geoloav (New Mexico Bureau of Mines and Mineral Resources), v.12, no.1, p.
3 Vll 2 Daniels, M., L.P Hart, P.H. Ho, J. P. Ballini and P. Vigny (1990), " Time Resolved Spectroscopy of the intrinsic Fluorescence of Nucleic Acid Species," SPIE 1204,
- Indicates OSTR use.
y "Delano, J.W., Y.-G. Liu and R.A. Schmitt (1990), " Geochemistry of Apollo 11 impact glasses: regolith compositions." Lunar and Planetary Science XXI, p. 280 281. 'Desonie, D.L., R.A. Duncan and W.M. White (1989), " Resolution of Time Space Geochemical Variability at the Marquesas Hotspot," (abstract) EOS Trans AGU, v.70,p.1385i Dodd, B. and L.L. Humphries (1989), "The Risks of Radioactive Material Transportation Accidents in the State of Oregon," Health Physicji, 57,1, p.131 139. l 'Donetick, R.A., M.K. Roden, J.D. Mooers, B.S. Carpenter and D.S. Miller (1990), "Etchable Length Reduction of Induced Fission Tracks in Apatite at Room Temperature (.23 C): Crystallographic Orientation effects and " Initial" Mean Lengths," Nuclear Tracks and Radiation Measurements,in press. - 'Duffield, W.A.; J. Ruiz and R.J. Walker (1990), "The Geochemistry of Taylor Creek Rhyolite: Ignimbrite Style Zoning Tumed Upside Down," Transactions American Geochvsical Union, in press. -i {
- p. 304 313.
o. Reoort.
- Everett, B.H., B.J. Kowallis, E.H. Christiansen and A. Dieno (1989), " Correlation of Jurassic sediemtns of the Carmel and Twin Creek Formations of southern Utah-using bentonite cha'acteristics," Utah Geoloaical and Mineral Survey Ooen File r
GeoohvsJ Union,2Q, p.1420.-
- Farmer, G.L. and A. G'azner (1989),."Isotepic Evidence on the Origin of Miocene-Recent Basalts in SE California and the Nature of the Sub-Mojave Mantle," Trans. Amer.
'Feeley,-T.C. and A.L. Grunder (1990), " Basalt induced crustal melting during mid-Tertiary magmatism: Evidence from the Egan Range, eastern Nevada," Geolooical - Society of America Abstracts with Proaram, v. 22. p. 22. 'Fodor, R.V., A.N.- Sial, S.B. Mukasa and E.H. McKee (1990), " Trace element analyses for basalts from the Maranhao flood basalt province, Brazil," published in " Petrology, isotope characteristics, and K Ar ages of the Maranhao, northern 9' Brazil, Mesozoic basalt province," Mineraloav and Petroloav 104, p. 555 567.
- Feeley, T.C. and A.L. Grunder, " Mantle contribution to the evolution of middle Tertiary magmas during early stages of extension: The Egan Range volcanic complex, east central Nevada, Mineraloav and Petroloav. in press.
sbstracts, v.1, p. 591.
- Grunder, A.L, (1989)," Development of silicic magma chambers during early phases of Tertiary extension, northeastern Great Basin," intemational Geoloaic Conaress.
i } Vll3 ) 'Grunder, A.L. and T.C. Feeley (1989), " Evidence for crustal and mantle sources of o: Tertiaryextension related volcanismin east central Nevada,"(I AVCEI) New Mexico Bureau of Mines and Mineral Resources Bulletin, v.131, p.116. [ 'Higginbotham, J.F. (1990), " Applications of the Oregon State University TRIGA Reactor l In Health Physics," invited, Trans. American Nuclear Societv. 61, p. 94 95. i Higginbotham, J.F. and G.G. Simons (1990), " Spectral Measurements of Gamma ray Induced Secondary Electron Fields, Trans. American Nuclear Society, p. 135-136. Hill, B.E. (1989), " Significance of Distinct Rhyodacitic Provinces Within the Three Sisters Region of the Oregon Central High Cascades," N.M. Bureau Mines Min. j Res. IAVCEI Bulletin 131, p.130. Hill, B.E. and E.M. Taylor (1989), "The Significance of Ouaternary Pyroclastic Volcanism - on the Eastern Flank of the Oregon Central High Cascades," Geol. Soc. Am. Abstr.. 21-5, p. 92, i Hill, B.E. and E.M. Taylor (1989), " Oregon Central High Cascade Pyroclastic Unites in { the Vicinity of-Bend, Oregon," U.S. Geol. Survey Ooen File Reoort,89 645, p. 51-54. 'Hintze, L.F. and _B.J. Kowallis (1989), " Fission track ages from volcanic rocks in and near the Little Drum Mountains, Millard County, Utah," Isochron / West, n. 54, p. 15-16. e. "Hughes, S.S., J.W. Delano and R.A. Schmitt (1990), " Chemistries of individual mare I volcanic glasses: evidence for distinct regions of hybridized mantle and a KREEP component in Apollo 14 magmatic sources, Proc. Lunar and Planet. Sci. Conf. XX, p.127-138, i
- Indicates OSTR use.
volcanic history and mineral potential of the central East Tintic Mountains, Utah," Utah Geolonical and Mineral Survey Ooen File Reoort, i Klein, A.C., S.R. Gedeon and D.C. Morey (1989), " Assessment of Nuclear _ Reactor l Concepts for Low Power Space Applications," Soace Nuclear Power Systems -1988, M.S, El Genk and M.D. Hoover, Eds., Orbit Book Co., Malabar, Florida. ..Klein, A.C.~, et al. (1989), " Energy Conversion Options for ARIES II a Conceptual D 3He Tokamak Reactor," UWFDM 815, University of Wisconsin, Madison, Wisconsin. Klein, A.C., J.A. VanWinkle and M.A. Maguire (1989), " Lithium Hydroxide Accelerated b Oxidation of Zircaloy-4," Trans. American Nuclear Society,60. m Klein, A.C. and H.S. Bloomfield (1989), " Neutron Emissions from a Lunar Based Reactor: 6 Excavation Siting," Trans. American Nuclear Society. 60, pp. 549-550. i
- Keith, J.D., R.D. Dallmeyer, C. S. Kim and B.J. Kowallis (1989), "A re-evaluation of the i
I o Vil-4 l Knaus, R.M. and D.L. VanGent (1989), " Accretion and Canal Impacts in a Rapidly c Subsiding Wetland. Ill. A New Soil Horizon Marker for Measuring Recent . Accretion," Estuaries, v.12, p. 269 283. [
- Indicates OSTR use.
i
- Knaus, R.M.,'"The Application of f Elements in Ecological Research."
of Upper Cretaceous volcanic ash beds from southwestern Utah to central l Colorado," Utah Geoloaical and Mineral Survev Miscellaneous Publication 89 5, 22 p. 3 'Kowallis, B.J., J. Ferguson and G.J. Jorgensen (1990), " Uplift along the Salt Lake segment of the Wasatch Fault from apatite and zircon fission track dating in the Little Cottonwood stock," Nuclear Tracks, in press. l f "Leeman, W.P., H.G. Ave Lallemant, D.C. Gerlach, J.F. Sutter and R.J. Arculus (1990), i " Petrology of the Canyon Mountain Complex, eastern Oregon," U.S. Geol. Surv. l Prof. Pacer 1438, in press. l 4 'Leeman, W.P., D.R. Smith, W. Hildreth, Z.A. Palacz and N.W. Rogers (1990), " Compositional diversity of late' Cenozoic basaltic magmas of the southern l Washington Cascades," J. Geochvs. Res., in press. i 'Liu, Y. G. and R.A. Schmitt (1990), " Cerium anomalies in western Indian Ocean j {i . Cer;ozoic carbonates Leg 115," Proceedinas; Ocean Drillina Project. Res. Results, j l'J., in press. Lovela ad, W., C. Casey, Z. Xu, L. Sihver, K. Aleklett and G.T. Seaborg (1989), Phys, } lev. C 4_Q, p.1244 'Loveland, W., K. Aleklett, M.-Johansson, L. Sihver, H. Groening, P.L. McGaughey and l G.T. Seaborg (1989), Nucl. Phys. A149, p. 591. Loveland, W., C. Casey, Z. Xu, G.T. Seaborg, K. Aleklett and L. Sihver (1989)', "Non-l Equilibrium Fission Processes in Intermediate Energy Nuclear Collisions," 50 Years 1 With Nuclear Fission, J.W. Behrens and A.D. Carlson, Eds., ANS, LaGrange Park,. Illinois, pp. 698 704. Loveland, W. (1989), " Environmental Sciences," Lanthanide Proves in Life. Chemical n-and Environmental Sciences, J. C. G. Bunzli and G.r. Choppin, Eds., Elsevier, Amsterdam. ' Loveland, W., K. Alektett, M. de Saint Simon, L. Sihver, J.O. Liljenzin and G.T. Seaborg j p (1990), " Heavy Residue Linear Momemta in Intermediate Energy Krypton Gold Collisions," Phys. Lett. 8236, p. 404.
- Kowallis, B.J., E.H. Christiansen and A. Dieno (1989), " Multi characteristic correlation i
./ t' Vll5 Loveland, W., K. Aleklett, L. Sihver, Z Xu, C. Casey, D.J. Morrissey, J.O. Liljenzin, M. 6 de Saint Simon and G.T. Seaborg (1990), " Changes in Target Fragmentation Mechanisms with increasing Projectile Energy in intermediate Energy Nuclear Collisions," Phys Rev. C 4.1. p. 973. g o 'McCurry, M., ^. Butcher, D. Fitzpatric and S. Yanicak (1989), "The Organ mountains volcano-plutonic complex, New Mexico," (International Geological Congress guidebook T318 contribution), American Geoohvsical Union, p.1213. ' Miller, D.S. and I.R. Duddy (1989), "Early Cretaceous Uplif t and Erosion of the Northern Appalachian Basin, New York, determined from Apatite Fission-track Analysis," Earth and Planetarv Science Letters,13, p. 35 49. " Miller, D.S., N. EDy, R. McCorkell, P.E. Rosenberg and M. Suzuki (1990), "Results of ~ Interlaboratory Comparison of Fission Track Ages for 1988 Fission Track Workshop," Nuclear Tracks and Radiation Measurements, in press. 'Mogk, D., P. Meuller, W. Weyand and A. Heatherington (1990), " Middle Archean gneisses of the northern Madison Range, SW Montana: Curstal genesis in a magmatic arc,". EQS, v.17, p.655. 'Neal, C.R., L.A. Taylor, A.D. Patchen, S.S. Maghes and R.A. Schmitt (1990), "The significance of fractional crystallizat sn in the petrogenesis of Apollo 17 Type A i and B High-Ti Basalts,".Cigqqtli_rp et Cosmochim. Acta, in press. 1 'Neal, C.R,, L.A. Tay!or, S.S. Hughes and R.A. Schmitt (1990), "The importance of fractional crystallization in the petrogenesis of Apollo 17 type A and-B high-Ti basalts," Lunar and Planetarv Science XXI, p. 857-858. 'Neal, C.R., J.B. Paces, L.A. Taylor, S.S. Hughes and R.A. Schmitt (1990), "Two new type C basalts: petrogenetic implications for source evolution and magma genesis at the Apollo 17 site," Lunar and Planetary Science XXI. p. 857 858. Reyes, J.N. (1989), " Statistically Derived Conservation Equations for Fluid Particle Flows," Trans. American Nuclear Societv, 60, pp. 669-670. l Reyes,- J.N. (1989), " Statistically Derived Conservation Equations for. Fluid Particle - Flows," Fif th Proceedinas of Nuclear Thermal Hvdraulics, pp.1219. Robinson, A.H. and J.O. Heaberlin (1989), "A Knowledge based System Framework for Real time Monitoring Applications," Trans. Americal Nuclear Society. Robinson,L A.H. and K.J. Greek (1989), " Hybrid Expert System ' Implementation *.o 0 Determine Core Reload Patterns," Trans. American Nuclear Society. Robinson, A.H. and K.R. Greene (1990), " Extending an Emergency Classification Expert g: System to the Real Time Environment," Trans. American Nuclear Society. rii. pp. 122 123.
- Indicates OSTR use.
Vll-6 Robinson, A.H., J.O. Heaberlin and K.R. Greene (1990), "EM CLASS, A Knowledge-i Based System for Emergency Classification," Trans. American Nuclear Society. 61, p.126127. [ Robinson, A.H. and K.J. Greek (1990), "PWR Optimal Reload Configuration with an Intelligent Workstation," Trans, American Nuclear Society,61, p.127-128. 'Roden, M.K., " Apatite Fission track Thermochronology of the Southern Appalachian Basin: Maryland, Virginia and West Virginia," Journal of Geoloav, in press, "Roden, M.K. and D.S. Miller (1989), " Apatite fission-track Thermochronology of the Pennsylvania Appalachian Basin" in Gardner, T.W. and W.D. Sevon, eds., Acoalachian Geomoroholoov, Geomoroholoav 2, p,39 51. 'Roden, ~ M.K. and D.S. Miller (1989), " Thermal History of Hartford, Newark and Taylorsville Basins Using Fission track Analysis," Geol. Soc. America Abstracts with Proarams,2L p. A266. 'Schieber, J. (1990), " Distribution of REE in the Eastern Belt Supergroup (Montana, U.S. A.): Implications for stratigraphic correlations and basin evolution," Chemical Geoloov, v. 81, p. 83 98. 'Schieber, J. (1989), " Distribution of rare earth elements in stratigraphic units of the Belt Supergroup," (abstract) EQS, v. 70, October 24, p.1390. 'Schmitt, R.A. (1990), "A general theory of mass extinctions in the Phanerozoic, l. g observations and constraints," Lunar and Planetary Science XXI, p. 1085 1086. 'Schmitt, R.A.'(1990), "A general theory of mass extinctions in the Phanerozoic,11. a brief outline," Lunar and Planetary Science XXI, p. 1087 1088. "Schmitt, R.A. (1990), " Reducing conditions in the Pacific Ocean before, at, and af ter j the Krr (Cretaceousfrertiary) boundary, Ill., Lunar and Planetary Science XXI. p. 1089 1090, t 'Sen, G. and W.P, Leeman (1990), " Iron rich therzolitic xenoliths from Oahu: origin and implications for Hawaiian magma sources," Earth Planet. Sci. Lett.. in press. 'Sharma, M., R.B. Cole, P.G. DeCelles and A.R. Basu (1990), " Basalt-dacite volctnism by MORB continental' crust' interaction: Sr Nd isotopic and trace elemental evidence, Tecuya volcanics, southern California," American Geoohvsical Union, v. 71,no.17,p.665. b 'Sharma, M., A.R. Basu and P.G. DeCelles (1989), "Nd Sr isotopes and trace element geochemistry of Amazonian fluvial. sands from Bolivia and Peru: implications for . magma contamination in the Central Volcanic Zone-(CVZ) and tectonics of the Andes," Geoloaical Society of America Abstracts with Proarams, v. 21, p. A190. g Indicates OSTR use. Vll7 ' Simon, S.B. (1989) " Comparative petrology of lunar regolith breccias and soils, and 6l implications for the howardite parent body regolith," (abstract), Meteoritics,24,
- Indicates OSTR use.
' Simon, S.B. and J.J. Papike (1990), " Comparative petro!ogy of lunar regolith breccias 3 and soils, and implications for the howardite parent body regolith," (abstract), Lunar and Planetary Science XXI. p. 1158 1159. ' Simon, S.B., J.J Papike, D.C. Gosselin, J.C. Laul, S.S. Hughes and R.A. Schmitt (1990) " Petrology and chemistry of Apollo 17 regolith breccias: A history of mixing of highland and mare regolith," Proc. Lunar and Planetary Sci. Conf. 22, p. 219 230. 'Sullivan, K.R., B.J. Kowallis and H.H. Mehnert, " Isotopic ages of igneous intrusions in southeastern Utah: evidence for a mid Cenozoic Reno San Juan magmatic zone," Briaham Youna University Geoloav Studies, v. 37, in press. 'Warnes, W.H; and J.A. Gardner (1989), " Perturbed angular correlation study of impurity interactions in a cubic host metal: Hf in Nb," Phys. Rev. B40. p. 4276-4280.
- p. 325 326.
'Wyld, S.J. (1989), "Paleczoic-Triassic history of the Pine Forest Range, NW Nevada: Implications for the development of arc terranes of the U.S. Cordillera," Geolooical Society of Americal Abstracts with Procrams, v. 21, p.161-162. 'Wyld, S.J. (1990), " Paleozoic and Mesozoic rocks of the Pine Forest Range, northwest ' Nevada, and their relation to volcanic arc assemblages of the western U.S. Cordillera,in Harwood, D.S. and Miller, M.M., eds., " Paleozoic and early Mesozoic paleographic relations: Sierra Nevada, Klamath Mountains, and related terranes," Geoloalcal Society of' America Soecial Pacer 255. in press. 1 e, : Indicates OSTR use. i Vil 8 B. Theses c: " Cole, R.B. (1989), "Early. Miocene volcanism in the southern San Joaquin basin, California:. Origin and tectonic implications based on facies analysis and trace h. element geochemistry," Masters thesis, Department of Geological Sciences, University of Rochester,120 p. "DeBari, S. (1990), " Comparative field and petrogenetic study of arc magmatism in the lower crust: Examples from a continental margin (Argentina) and an intraoceanic (Alaska) setting," Ph.D. thesis, Geology Department, Stanford University.
- Wollenberg, H.A., S. Flexser and L.R. Myer, " Drill Back Studies Examine Fractured, Heated Rock," Tuns. American Nuclear Society.
Masters thesis, Department of Physics, Oregon State University. 'Hoernie, K.A. (1990), "The major element, trace element and Sr Nd Pb isotopic evolution of Gran Canaria (Canary Islands) magma sources over the past 15 m.y.: Inferences on the geochemical and structural evolution of the mantle," Ph.D. dissertation, Department of Geology, University of California, Santa Barbara, 140 p.
- Fuchs, H. (1990), " Perturbed angular correlation investigation of cubic zirconia,"
- temperature," Ph.D. thesis, Department of Physics, Oregon State University. j Walker, R.J. (1989), "Magmatism and Mineralization of the Ash Peak area, Arizona; PetrochemicalInterpretations," Ph.D. thesis, Departmant of Geosciences, Oregon o i State University,189 p. o
- Su, H. T. (1989), " Perturbed angular correlation spectroscopy of oxide ceramics at high
i w f o
- Weidlich, G. (1989), " Structural properties of indium-doped Yba2Cu30(7 x) high Tc superconductors," Masters thesis, Department of Physics, Oregon State University.
Vll 9 C. Reoorts Submitted for Publication c. 'Desonie, D.L. and R.A. Duncan, "The Cobb Eickelberg Seamount Chain: Hotspot Volcanism with Mid Ocean Ridge Basalt Affinity," Jour. Geoohvs. Res.. h. (submitted).
- Indicates OSTR use.
-Basaltic Magma with' Mafic Crust at Amboy and Pisgah Craters, Mojave Desert, California," J. Geochvs. Res., (submitted).
- Evenson, W.E., A.G. McKale, H.T. Su and J.A. Gardner, " PAC perturbation factor for spin 5/2 nuclei and subject to a rapidly fluctuating EFG," Hvoerfine interactions (submitted).
- Gerlach, D.C., W.P. Leman, M.O. Garcia and H.B. West (1990), " Temporal variations in the geochemistry of lava from Kahoolawe volcano, Hawaii," Mineral. Petrol. (in revision).
- Glazner, A.F., G.L. Farmer, W.T..Hughes, J.L._ Wooden and W. Pickthorn, " Mixing of
climax, and waning in middle Tertiary magmatism in east central Nevada," Geolooy l (submitted). 'Hoernle, K.A. and H.U. Schmincke, "The major and trace element geochemistry of the J: tholeiite melilite'nephelinite basalts on Gran Canaria, Canary Islands: Crystal fractionation, accumulation and melting depth," Mineral. Petrol. (submitted). 1 - 'Hoernle, K.A.' and H.U. Schmincke, "The major and trace element evolution of Gran Canaria magma sources over the past 15 m.y.: An intermittent Canary Island Plume?," Mineral. Petrol. (submitted). 'Jaeger, H., H.T. Su, J.A! Gardner, l.W. Chen, J.C. Haygarth, J.A. Sommers and R.L. Rasera, " Aftereffects following beta decay of 181 Hf,"-Hvoerfine Interactions (submitted). I "Kowallis, B.J. and M.G. Best (1990), " Fission track ages from volcanic rocks in - southwestern Utah and southeastern Nevada," Isochron / West (submitted). Loveland, W., K. Aleklett, P.L. McGaughey, K.J. Moody, R.M. McFarland, R.H. Kraus, Jr.'and G.T. Seaborg, " Au Target Fragmentation in Intermediate Energy Heavy lon ' Reactions," Phys. Rev. C. (submitted). Loveland, W., C.P. Oertel, D.J. Morrissey, P.L. McGaughey, G.T. Seaborg and K. Aleklett, " Heavy Target Fragmentation and the Energy Dependence of Nucleus-P Nucleus Total Reaction Cross Section," Nuclear Phys. A (submitted). Loveland, W., Li Wonxin, P.L. McGaughey and G.T. Seaborg, " Target Fragment Yield Distribution in the Reaction of 245 MeV/A '3'La with La," Nucl. Phys. A. 333 + (submitted).
- Grunder, A.L. and T.C. Feeley, " Textural and petrogenetic changes related to inception, l
T' Vll10 Loveland, W., " Radiochemistry," Encvelooedia of Physics, R.G. Lerner and G.L. Trigg, Eds. (VCH, New York). Loveland, W., M. Hellstrom, L. Sihver and K. Aleklett, " Target Fragment Mass Distributions for the Reaction of 13.3 GeV/N 2eSi with *Au," Phys. Rev. C o. (accepted for publication). Loveland, W,, L. Sihver, K. Aleklett, P.L. McGaughey, D.H.E. Gross and H.R. Jaqaman, " Gold Target Fragmentation by 800 GeV Protons," Phys. Rev. C. (submitted). ' Stern, C.R. and A. Puig, " Chemical Evolution of Pliocene and Quaternary Andean Magmas at 34S.," (abstract) American Geophysical Union Fall Meeting, San Francisco, December 1990 (submitted).
- Indice'es OSTR use.
'Struempler, A.W,, " Element Mobility due to Weathering in the L5 Bayard Chrondrite," Meteoritics. 'Su, H.T., R. Wang, H. Fuchs, J. A. Gardner, W.E. Evenson, J.A. Sommers, " Oxygen vacancy hopping.and trapping in zirconia and ceria," J. Amer. Ceram. Soc. (submitted). k ' Warner, R.D., D.S. Snipes, S.S. Hughes, R.A. Schmitt and J.C. Steiner, " Geochemistry and petrology of Mesozoic dikes in South Carolina," submitted to Geological-Society of America Special Paper " Mesozoic Magmatism in Eastern North America" (J. Puffer and P. Ragland, editors). .o 1' ' Indicates OSTR use. Vll 11 D. . Documents in Precaration 4 1. Publications ' Ayres, W.S., F.R. Beardsley and G.G. Goles, "The Characterizstion of Easter Island Obsidian Sources."
- Stern, C.R. and A. Puig, " Chemical Evolution of Pliocene and Quaternary Andean Magmas at 34S,," Earth and Planetary Science Letters (submitted).
M.K. Roden and D.S.
- Brandon, M.T.,
" Apatite Fission track Thermochronology of the Olympic Subduction Complex, Washington State." " Butcher, D.P., M. McCurry and G.L. Farmer, " Chemical, mineralogical and Nd Sr isotopic zonation of the Organ Needle pluton and its extrusive equivalent."
- Miller,
'Desonie, D.L., R. A. Duncan and J. Natland, " Temporal and Geochemical Variability of Volcanism Over the marquesas Hotspot."
- DeBari, S.M. and J.E. Wright, "Petrogenesis and physical evolution of the Fiambala gabbronorite, northwestern Argentina: Syntectonic magmatism in the deep crust of a continental margin arc," to be submitted to J; Geochvs. Res.
submitted in December 1990 to Kimberlite Conference in Brazil, June 1991). 'Rodon,.M.K. and D.S. Miller, " Apatite Fission-track Thermochronology of the Hartford Basin,' Connecticut." j Skinner, C.E. and S.R. Radosevich, "Maxama " Mimic" Mystery Tephra: A Geochemical Roassessment of Tephra from Vine Rockshelter (35LA304), Central Western-Cascades, Oregon."
- Fodor, R.V., G. Ghondak and A.N. Sial, " Trace element analyses of ultramafic xenoliths and clinopyroxene megacrysts from basalts in Tertiary volcanic centers-in Rio Grande do Norte state of northern Brazil," (abstract to be p
l 'Wyld, S.J., " Development of the early Mesozoic volcanic arc of the western U.S. H-Cordillera: A detailed study from northwest Nevada," in progress.
- Skin'ner, C.E., " Neutron Activation Analysis of Archaeological Obsidian from the Tahkenitch lake Site 135 DO 130), Oregon Central Coast."
- Skinner, C.E., "Geoarchaeological Investigations of an Unexpected ' Geologic Source of Obsidian in the Southwestern Willamette Valley, Oregon."
- Sisson, V.B., " Element mobility during regional amphibolite facies metamorphism in central Maine,"~to be submitted to Geochim. Cosmochim. Acta.
?
- oy
l-1 Vll 12 : 1 i 2. Theses j q 'D'Arcy, K.', " Geochemistry and Geochronology of Precambrian Metamorphic Rocks of '. the Montana Metasedimentary Terrane," Ph.D. thesis, Geology j g., Department, University of Florida, j
- Indicates OSTR use.
megacrysts from basalts in Tertiary volcanic centers in Rio Grande do Norte state of northern Brazil," Masters thesis, North Carolina State University. . Hill, B.E., " Controls on Silicic Magma Evolution in the Central High Cascades of - Oregon," Ph.D. dissertation, Department of Geosciences, Oregon. State -s i University. " Murphy, G.,." Geochemistry of Precambrian Metamorphic Rocks of the Gravelly Range, SW Montana," Masters thesis, Geology Department, University of Florida. 'Desonie, D.L., Ph.D. dissertation, Department of. Oceanography, Oregon State i University.. l [. Y.;
- Ghondak, G., " Trace element analyses of ultramafic xenoliths and clinopyroxene l
i. 14 Indicates OSTR use, l ? 1 Vll13 E. Presentations + o Binney, S.E. and J.F. Higginbotham, " Neutron Detection and Spectrometry in Support of Cold Fusion Experiment," Health Physics Society Annual Meeting, Albuquerque, New Mexico, paper THPM-F01,1989. o 'Dodd, B., "Use of the OSU TRIGA Reactor for Education and Training," American Nuclear Society Annual Meeting, Atlanta, Georgia,1989. 'Dodd, B., "Research Reactor Audit Checklist," TRTR 89, Raleigh, North Carolina,1989. Dodd, B., " Implementation of the IAEA Radiation Protection Optimization Principles at a Research Reactor Facility," 35th Annual Meeting of the Health Physics Society, Anaheim, California, io90. 'Dodd, B. and T.V. Anderson, " Design, Construction, Commissioning and Use of a New Cadmium Lined in Core irradiation Tube for the Oregon State University TRIGA Reactor," 12th TRIGA User's Conference, Austin, Texas,1990. 'Elliott, W.C., J.L.- Aronson, M.K. and D.S. Miller, "The formation of Illite in the Appalachian Basin: A test of the Fluid Expulsion Hypothesis," submitted to Geo. Soc. America Abstracts with Prog.,1990 Annual Meeting. "Evenson, W.E.,' A.G. McKale, H.T. Su and J.A. Gardner, " PAC perturbation factor for spin 5/2 nuclei subject to a rapidly fluctuating EFG," presented at the International l Conference on Hyperfine Interactions, Prague, August 1989. 'Evenson, W.E. and J.A. Gardner, " Defect hopping and trapping investigations by PAC," presented at the March meeting of the American Physical Society, Anaheim, California, March 1990.
- y l+
presented at the annual meeting of the American Ceramics Society, Dallas, Texas, April 1990.
- Evenson, W.E., "The relevance of PAC to studying the properties of ceramics,"'
- Gardner, J.A., " Application of nuclear hyperfine experiments to the study of defects in-
"Gardner, J.A., R. Wang, H. Fuchs, H.T. Su, W.E. Evenson and J.A. Sommers, "Exygen ' vacancy hopping and trapping in ceria, tetragonal zirconia and cubic zirconia," presented at the annual meeting of the American Ceramics Society, Dallas, Texas, April 1990. + O 'Han, W. and J.A. Gardner, "NMR relaxation in high temperature GaAs," presented at the March meeting of the American Physical Society, Anaheim, California, March 1990.
- ceramics," presented at the. annual meeting of the American Ceramics Society, Dallas, Texas, April 1990.
Vil 14
- Indicates OSTR use.
' Due to Routine Ar-41 Gaseous Effluent Releases," Health Physics Society Annual Meeting, Anaheim, California, June 1990. y_ 'Higginbotham, J.F., D.S. Pratt and S.M. Cordell, "Off site Dose Commitment Due to Intentional Releases of Argon-41," 12th TRIGA User's Conference, Austin, Texas, 1990. Higginbotham, J.F. D.S. Pratt and S.M. Cordell, " Certification of a Radioactive Materials Shipping Container Under USDOE Specification 7A, General Packaging, Type A (49 CFR 178.350)," 12th TRIGA User's Conference, Austin, Texas,1990. "Honjo, N. and W.P. Leeman (1990), " Style of silicic volcanism in the Snake River Plain-- Yellowstone hotspot track: a petrologic overview," EQ3 71, p. 964, Western Pacific Geophysics Meeting, Kanazawa, Japan,21-25 August. "Jaeger, H.i H.T. Su, J.A. Gardner, l.W. Chen, J.C. Haygarth, J.A. Sommers and R.L. Rasera, " Aftereffects - following beta-decay of 181 Hf," presented at the international Conference on Hyperfine Interactions, Prague, August 1989. Klein,. A.C., S.R. Gedeon and P.T. Choong, " Nuclear Design Analysis of in core Thermionic Reactor Systems," Sixth Symposium on Space Nuclear Power Summaries, Albuquerque, New Mexico January 1989. I Klein, A.C., K.A. Pauley and B.J. Webb, " Condensation Fluid Dynamics and Heat Transfer on Rotating Spherical Surfaces in a Microgravitational Field," Seventh 1 Symposium on Space Nuclear Power Summaries, Albuquerque, New Mexico,- January 199'). Klein, A.C. and H.S. Bloomfield, " Scattered Neutron Radiation from a Nuclear Power Source Sited in a Lunar Excavation," Sevnoth Symposium on Space Nuclear Power 1 Summaries, Albuquerque, New Mexd January 1990. Klein, A.C.,"Microgravity Thaw Experiment (MITEX)," AIAA/ASME 6th Thermophysics and Heat Transfer Conference Proceedings, Seattle, Washington, June 1990.
- Higginbotham, J.F., D.S. Pratt and S.M. Cordell, " Calculated Offsite Dose Commitment b-
'Leeman, W.P., A.E. Moran and V.B. Sisson - (1990), " Compositional variations accompanying metamorphism of subducted oceanic lithosphere: implications for C genesis of arc magmas and mantle replanishment," (abstract) 7th International Conf. Geochronology, Cosmochronology, and isotope Geology, Canberra, Australia l l; (24 29 September). ? i
- Leeman, W.P. (1990), "The utility of boron as a tracer of subduction processes: slab contributions to arc magmatism and implications for recycling of lithospheric matetialinto the deep mantle," (abstract) Second V.M. Goldschmidt Conference, The Geochemical Society,60 Hunt Valley, MD,2-4 May).
Vll 15 Loveland, W., K. Aleklett, J.O. Liljenzin, M. de Saint Simon, G.T. Seaborg and L. Sihver, " Heavy Residue Spectra -and Linear Momentum Transfer in Intermediate p, l Energy Nucleus-Gold Collisions," 1989 International Nuclear Physics Conference, 1 Sao Paulo, Brazil, August 1989. Loveland, W., K. Aleklett, G.T. Seaborg and L. Sihver, " Heavy Residue Spectra and Linear Momentum Transfer in Intermediate Energy Nuclear Collisions," 1989 International Chemistry Congress of Pacific Basin Societies, Honolulu, Hawaii, December 1989.
- Indicates OSTR use.
effects of burial, metamorphism, and chemical processing," (abstract) Second V.M. Goldschmidt Conference, The Geochemical Society,67 (Hunt Valley, MD,2 4 May). l Reyes, J.N., A.C. Klein, M.A. Maguire, " Thermal Gradient Effects on the Oxidation of Zircaloy Fuel Cladding," IAEA Technical Committee Meeting on Fundamental I Aspects of Corrosion of Zirconium Base Alloys in Water Reactor Environments, Portland, Oregon, September 1989. L
- Moran, A.E., V.B. Sisson and W.P. Leeman (1990), "The fate of boron in subducted oceanic slab:
. the Olympic Subduction Complex, Washington," submitted to Geol. Soc. America - Abstracts with Prog.,1990 Annual Meeting. " Schwenker, R., G. Weidlich, M. Geolz, R. Wang, W.E. Evenson, K. Keszler, J.A. Gardner and J.A. Sommers, " Structural and electronic properties of indium doped
- Roden, M.K., M.T. Brandon and D.S. Miller, " Apatite Fission track thermochronology of R
Anaheim, California, March 1990.- '*Slason,' V.B., " Geochemical and fluid evolution of the southern Chujach Mountains, Alaska," presented at Geol. Soc. Amtr. Penrose Conference. " Skinner, C.T. and S.R. Radosevich, "Mazama "Mimin" Mystery Solved: A Geochemical Reassessment of the Volcanic Tephra from Vine Rockshelter." paper presented at 43rd Annual Northwest Anthropological Conference, Eugene, Oregon, March 22-24,1990. " Skinner, C.T. and S.R. Radosevich, "The Source of the Mazama " Mimic" Mystery i Tephra: Geochemical Studies of Volcanic Tephra from Vine Rockshelter (35LA304), Central Western Cascades, Oregon," presented at 5th Annual Oregon - , Archaeological Conference, Eugene, Oregon, November 4,1989. l: Su, H.T.,' J.A. Gardner, P. Carter and J.A. Sommers, " Oxygen vacancy trapping and A hopping in lightly doped tetragonal zirconia," presented at the International Conference on Science and Technology of Zirconia, Anaheim, California, October l 1989. A " Indicates OSTR use. ,h/ g e v a+ ~ 0' y,ig:fb:r\\l . vil.1 s; = < r i , m. -n >, ' Wang / R W.E.' Evenson and J.A. Gardner, " Oxygen vacancy hopping and trapping by - 7. ~ Q - impurities'in ceriumioxide " presented at the March meeting of the American. j - Physical Society, Anaheim, California, March 1990. ,-.. ~,. 6 i 1 m ..;; I 1 4 .r. 7 1 4m
- YBa2Cu30x," presented at the March meeting og the American Physical Society, 1
i,, l 1 1 v s: .j i q E ait t t n m.: .s. L '~ .p k n e o \\ r ,s. I c: 5 a .-o c .r-
- [
s1 s L:, :m;. f ,64 -r = 's W' { i s j i -Q. E _;q- ) s t 1 a A
- 7,;.
.a y. o ' ' i t. i
- i C
.i m. [,3. s. 5 a t ... I F, 1 1 '.t ;., i. ~i vi. t
- (.;4 / ;
1 ~ y, n' i 'n s c if_ \\ n ': ~v. ,e gn: ,, q : ) m= ? [,j, 'M
- h h
~ ~ ~J. .m. s: _.) l S., ~i i s u Indicates OSTR use.. s t t i y ') / '4 ' /.. 2 ,(., .i ' fj g r, 6 y r. -.g :, a <.s, i 11 f ) $- A s, -3 = s p-e v..E- ,iv-,.i y .y--, ,s ,7 y tt F
- f.,
I d Vll 17 ' F. Public Relations a 4-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 O and interested individuals who stopped in without appointments because they were in the-vicinity, a total of 883 people were given pre planned and scheduled tours during this reporting' period. See Table Vll.F.1 for statistics on scheduled visitors, ?I 1 .j .s. s-' 4 i Vll 18 o Table Vll.F.1 i b Summary of Visitors to the Radiation Center For the Period July 1,.1989 through June 30,1990 c. No. of Date Visitors Name August.4,' 1989 4 Golf group from Portland ~ . August 29,1989 3 Merlin Samuelson & Ormet ',itanium t August 30,1989-33 General Chemistry class (106) l LSeptember 14,1989 1 Bechaida Rivera--OSU Public Health September 28,1989 12 Chemistry 461 'i
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Chemistry 461 October 19;'1989 34 OSU Public Health Class October 24,1989 4 Chemistry 461 November :7,1989 -- 45-North Albany Elementary School,5th grade [ JNovember 9,1989 14 Chemistry 107/207 '. November 20,1989 38. Health and Human Performance--Public Health Class-Personal Health H170 l ' November 21,'1989 4 Chemistry 461 January 3,1990 ~ 7 Cub Scouts -l --Janu'ary 8!.1990 ' 15' North Bend High School Students S January 17,~ 1990~. 5 Reed College Reactor Operating Training [' Course' l. February.1,1990 40 OSU Public Health Class (Man / Health l and Environment H344) l y y February 2,1990 10-Oregon Episcopal School L February 2,1990 2 Dwight Baker & Jay Farr l ' February 3,1990 180 Dad's Weekend Open House-l 1 February 13,1990 52 Chemistry 202 students k February 19,1990 3 Salem Boy Scouts } Febrwry 22,1990 8 .U of O Geology-Paleo, Course
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February 26,1990. 50 Mark Twain School,8th grade honor students Vll 19 7 A Table Vll F.1 (Continued) P{. No. of a Date. Visitors Name February.27,1990-8 . U of O Geology--Paleo Course March 7,1990 14 Oregon Episcopal School Science Students 1 March 29,1990 12 Coquille H.S. Physics Class April 4,,1990 - 20 LBCC Science Students ' April.7,1990 20 Beaver Open House. - April 10,1990 4 Honeywell Corporation April 12,1990. ' 2 Corvallis Fire Dept. April 18,.1990 20 Sweet Home H.S. Physics Class -: April 26; 1990 12 Yamhill Carlton H.S. Physics Seniors May 2, s1990 7 Jefferson H.S. Physics Students t May 5,1990 70 Mom's Weekend Open House ?- .May 10.1990-20-Newport H.S. Advanced Science Class i 4 May 12,-1990. 26 Boy Scouts 'May 15, s1990 3 OSU Students May 5,1990 - 31 Indonesian Group f May 21,1990 41 4 H Extension Program (Summer Week). May 22,1990. '5 General Atomic, Morocco group TOTAL 883 Or u le .}}
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