ML023120071

Letter Regards Oregon State University Triga Reactor

ML023120071
Person / Time
Site:	Oregon State University
Issue date:	10/28/2002
From:	Klein A Oregon State University
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
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Download: ML023120071 (174)

Text

RADIATION CENTER October 28, 2002 U.S. Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555

Reference:

Oregon State University TRIGA Reactor (OSTR),

Docket No. 50-243, License No. R-106 In accordance with section 6.7.e of the OSTR Technical Specifications, we are hereby OREGON submitting the Oregon State University Radiation Center and TRIGA Reactor Annual Report for the period July 1, 2001 through June 30, 2002.

STATE UNIVERSITY The 2001-2002 Annual Report continues the pattern established over the past few years by including information about the entire Radiation Center rather than concentrat ing primarily on the reactor. Because the report addresses a number of different 100 Radiation Center Corvallis, Oregon interests, it is rather lengthy, but we have incorporated a short executive summary 97331-5903 which highlights the Center's activities and accomplishments over the past year.

The executive summary indicates that the Radiation Center has maintained its high degree of productivity this past year. We hope that you will find the current report to be informative and interesting. Should there be any questions, please let me know.

Sincerely, Andrew C. Klein Director Enclosure Telephone 541.737 2341 Fax 541.737.0480 A

Ato/)oo

USNRC October 28, 2000 cc w/enclosure:

Mr. Al Adams, Jr., Senior Project Manager, USNRC, MS O11 B20, Washington, DC 20555-0001 Mr. Craig Bassett, USNRC, 61 Forsyth St. SW, Ste. 23T85, Atlanta, GA 30303 Mr. Pat Madden, USNRC, One White Flint North, MS 12 D1, Rockville, MD 20852 cc w/out enclosure:

D. Stewart-Smith, Oregon Office of Energy J. C. Ringle, Chairman, OSTR Reactor Operations Committee G. M. Wachs, OSTR Reactor Supervisor, OSU S. R. Reese, OSTR Reactor Administrator, OSU S. A. Menn, Senior Health Physicist, OSU

Oregon State University Radiation Center and TRIGA Reactor Annual Report July 1, 2001 - June 30, 2002

Anfnual Report of the Oregon State University Radiation Center and TRIGA Reactor July 1, 2001 - June 30, 2002 To satisfy the requirements of:

A. U.S. Nuclear Regulatory Commission, License No. R-106 (Docket No. 50-243), Technical Specification 6.7(e).

B. Task OrderNo. 3, under SubcontractNo. C84-110499 (DE-AC07-76ER01953) for UniversityReactor Fuel Assistance-AR-67-88, issued by EG&G Idaho, Inc.

C. Oregon Office of Energy, OOE Rule No. 345-030-010.

Edited by:

A. C. Klein, Director With contributions from:

A. C. Klein, Director K. M. Brock, Senior Health Physicist S. C. Campbell, Business Manager M. R. Conrady, Analytical Support Manager J. E. Darrough, Health Physicist G.M. Wachs, Reactor Supervisor R. A. Keen, Office Coordinator S. A. Menn, Health Physicist S. R. Reese, Reactor Administrator L. J. Robinson, Word Processor S. P. Smith, Scientific Instrument Technician J. M. Stueve, Office Coordinator Submitted by:

A. C. Klein Director, Radiation Center Radiation Center Oregon State University Corvallis, Oregon 97331-5903 Telephone: (541) 737-2341 Fax: (541) 737-0480 October 2002

Annual Report of the Oregon State University Radiation Center and TRIGA Reactor Table of Contents PART I - OVERVIEW I-1 A. Acknowledgem ents .....................................................

I-I B. Executive Summ ary .....................................................

....... 1-2 C. Introduction ...............................................

1-3 D. Overview of the Radiation Center .........................................

1-4 E. Summary of Environmental and Radiation Protection Data .....................

1-4

1. Liquid Effluents Released ............................................

Liquid Waste Generated and Transferred ................................ 1-4 2.

Airborne Effluents Released .......................................... 1-5 3.

Solid W aste Released ............................................... I-5 4.

1-6

5. Radiation Exposure Received by Personnel ..............................

6. Number of Routine Onsite and Offsite Monitoring Measurements and Sam ples ...................................................... 1-7

. -8 F. History ..........................................................

PART II - PEOPLE

....................... 11-1 A. Professional and Research Faculty ..................

11-5 B'. Visiting Scientists and Special Trainees ....................................

11-5 C. OSU Graduate Students ..................................................

11-6 D. Business, Administrative and Clerical Staff..................................

11-6 E. Reactor Operations Staff ..................................................

..................... 11-6 F. Radiation Protection Staff ............................

...................... 11-7 G. Scientific Support Staff ...........................

11-7 H. OSU Radiation Safety Office Staff .........................................

11-7 I. Comm ittees ............................................................

11-7

1. Reactor Operations Committee ........................................

11-8

2. Radiation Safety Committee ..........................................

11-8

3. Radiation Center Safety Committee ....................................

Page PART III - FACILITIES A. Research Reactor .....................................

1. Description .....................................

HI-2

2. Utilization ...................................... .................

HI-2

a. Instruction ................................. S.. . . . .,. . . . . . . . . . .o 11I-3

b. Research .................................. . . ... . . . °°. ..° .. . . .

HI-3 B. Analytical Equipment ..................................

111-3

1. Description .....................................

111-3

2. U tilization ...................................... .................

111-4 C. Radioisotope Irradiation Sources .........................

111-4

1. D escription ..................................... . . .. .. . . . °.. . . . . .

111-4

2. U tilization ...................................... .................

111-4 D. Laboratories and Classrooms ............................

111-4

1. D escription .....................................

111-5

2. U tilization ...................................... .................

111-5 E. Instrument Repair and Calibration Facility .................

111-5

1. D escription .....................................

2. U tilization ...................................... . . .. . . . . . . . . .oo o o . 1H-6 F. Libraries ............................................ .... °............ 11I-6

1. D escription ..................................... ................. 111-6

2. U tilization ...................................... .°............... 111-7 PART IV - REACTOR A. Operating Statistics ..................................... S................ IV -1 B. Experiments Performed ................................. ................ IV-1

1. Approved Experiments ............................. IV -1

2. Inactive Experiments .............................. ................ IV-2 C. Unplanned Shutdowns .................................. ................ IV-3 D. Changes to the OSTR Facility, to Reactor Procedures, and to Reactor Experiments Performed Pursuant to 10 CFR 50.59 ..... ................ IV-3

1. 10 CFR 50.59 Changes to the Reactor Facility ........... ................ IV-3

2. 10 CFR 50.59 Changes to Reactor Procedures ........... ................ IV-6

3. 10 CFR 50.59 Changes to Reactor Experiments ......... ................ IV-7 E. Surveillance and Maintenance ............................ ................ IV -7

1. Non-Routine Maintenance .......................... ................ IV -7

2. Routine Surveillance and Maintenance ................ ................

F. Reportable Occurrences ................................. ................ IV -8

Page PART V - PROTECTION A. Introduction ..................................................... V-1 Environmental Releases ................................................. V-1 B.

1. Liquid Effluents Released ..... .................................. V-2

2. Airborne Effluents Released ......................................... V-2

3. Solid W aste Released .............................................. V-3 Personnel D oses ....................................................... V-3 C.

Facility Survey Data .................................................... V-4 D.

1. Area Radiation Dosimeters .......................................... V-5

2. Routine Radiation and Contamination Surveys .......................... V-5 Environmental Survey Data .............................................. V-6 E.

1. Gamma Radiation Monitoring ....................................... V-6

2. Soil, Water, and Vegetation Surveys ................................ V-7 Radioactive M aterial Shipments .......................................... V-8 F.

References ........................................................... V -9 G.

PART VI - WORK

...... .............. VI-1 A. Summary ........

VI-1 B. Teaching .............................................................

VI-1 C. Research and Service .............................................

1. Neutron Activation Analysis ........................................ VI-2

2. Forensic Studies .................................................. VI-2

3. Irradiations .................... ............................. *V3 Radiological Emergency Response Services ............................. VI-3 4.

5. Training and Instruction ............................................ VI-3

6. Radiation Protection Services ........................................ VI-4

7. Radiological Instrument Repair and Calibration ......................... VI-4

8. Consultation ................................... . VI-5 Public Relations .................................................. VI-5 9.

PART VII - WORDS Publications in Print ................................................... V II-1 A.

VII-12 B. Documents Submitted for Publication ...................................

VII-15 C. Documents in Preparation .............................................

VII-17 D. Theses and Student Project Reports ...................................

V II-19 E. Presentations ........................................................

LIST OF TABLES Table Title.

III.A. 1 OSU Courses Using the OSTR .................................. 111-8 III.A.2 OSTR Teaching Hours ........................................ 111-9 III.A.3 OSTR Research Hours ....................................... 1]1-10 II.B. 1 Radiation Center Spectrometry Systems: Gamma, Low Energy Photon, A lpha .............................................. HI-11 III.B.2 Radiation Center Proportional Counting Systems .................. 1-12 III.B.3 Thermoluminescent Dosimeter Systems .......................... II-13 IlI.C. 1 Gammacell 220 60Co Irradiator Use ............................. 111-14 III.D. 1 Student Enrollment in Nuclear Engineering, Radiation Health Physics and Nuclear Science Courses Which Are Taught or Partially Taught at the Radiation Center ....................................... 111-15 IV.A. 1 OSTR Operating Statistics (Using the FLIP Fuel Core) ............... IV-9 IV.A.2 OSTR Operating Statistics with the Original (20% Enriched)

Standard TRIGA Fuel Core .................................... IV-12 IV.A.3 Present OSTR Operating Statistics .............................. IV-13 IV.A.4 OSTR Use Time in Terms of Specific Use Categories ............... IV-14 IV.A.5 OSTR Multiple Use Time ..................................... IV-15 IV.B. 1 Use of OSTR Reactor Experiments ............................. IV-16 IV.C. 1 Unplanned Reactor Shutdowns and Scrams ....................... IV-17 V.A. I Radiation Protection Program Requirements and Frequencies ......... V-10

LIST OF TABLES (Continued)

Table Title Page V.B.1.a Monthly Summary of Liquid Effluent Releases to the Sanitary Sewer ............................... ................... V-1I V.B. 1.b Annual Summary of Liquid Waste Generated and Transferred ......... V-12 V.B.2 Monthly Summary of Gaseous Effluent Releases ................... V-13 V.B.3 Annual Summary of Solid Waste Generated and Transferred ......................... ........... ........... V-14, V.C. I Annual Summary of Personnel Radiation Doses Received ............ V-15 V.D. 1 Total Dose Equivalent Recorded on Area Dosimeters Located Within the TRIGA Reactor Facility .............................. V-16 V.D.2 Total Dose Equivalent Recorded on Area Dosimeters Located W ithin the Radiation Center .................................... V-17 V.D.3 Annual Summary of Radiation Levels and Contamination Levels Observed Within the Reactor Facility and Radiation Center During Routine Radiation Surveys ............................... V-19 V.E. 1 Total Dose Equivalent at the TRIGA Reactor Facility Fence ........... V-20 Radiation V.E.2 Total Dose Equivalent at the Off-Site Gamma Monitoring Stations ......................................... V-21 V.E.3 Annual Average Concentration of the Total Net Beta Radioactivity (Minus 3H) for Environmental Soil, Water, and Vegetation Sam ples .................................................... V -22 V.E.4 Average LLD Concentration and Range of LLD Values for Soil, W ater and Vegetation Samples .................................. V-23 V.F.1 Annual Summary of Radioactive Material Shipments Originating From the TRIGA Reactor Facility's NRC License R-106 .............. V-24

I LIST OF TABLES (Continued)

Table Title Page V.F.2 Annual Summary of Radioactive Material Shipments Originating From the Radiation Center's State of Oregon License ORE 90005 ................................................. V-26 V.F.3 Annual Summary of Radioactive Material Shipments Exported Under NRC General License 10 CFR 110.23 ....................... V-28 VI.C. 1 Institutions and Agencies Which Utilized the Radiation C enter ...................................................... V I-6 VI.C.2 Graduate Student Research Which Utilized the Radiation Center ............................................. VI-12 VI.C.3 Listing of Major Research and Service Projects Performed or in Progress at the Radiation Center and Their Funding Agencies .......... VI- 18 VI.C.4 Summary of the Types of Radiological Instrumentation Calibrated to Support the OSU TRIGA Reactor and the Radiation Center ............................................. IV-39 VI.C.5 Summary of Radiological Instrumentation Calibrated to Support Other OSU Departments and Other Agencies ....................... VI-40 VI.F. 1 Summary of Visitors to the Radiation Center ....................... VI-41

LIST OF FIGURES Figur Title Page IV.E.1 Monthly Surveillance and Maintenance (Sample Form) ............. IV-18 IV.E.2 Quarterly Surveillance and Maintenance (Sample Form) ............. IV-19 IV.E.3 Semi-Annual Surveillance and Maintenance (Sample Form) .......... IV-21 IV.E.4 Annual Surveillance and Maintenance (Sample Form) .............. IV-23 L V.E.l Monitoring Stations for the OSU TRIGA Reactor .................. V-29 L

Part I Overview

Part I OVERVIEW A. Acknowledgments Many individuals and organizations help the Radiation Center succeed, and in recognition of this, the staffofthe Oregon State University (OSU) Radiation Centerand TRIGA Reactor (OSTR) would like to extend its appreciation to all of those who contributed to the information and events contained in this report: to the University administration; to those who provided our funding, particularly the U. S.Department of Energy (USDOE) and the State of Oregon; to ourregulators; to the researchers, the students, and others who uised the Radiation Center facilities; to OSU Facilities Services; and to OSU Department'ofPublic Safe-ty and the Oregon State Police. We most earnestly sa ,, "Thank you."'

The Center would not be able to accomplish all that is shown in this report without the diligent efforts ofall of its staff who have all worked hard. It is to their'credit that we have managed to improve our level and quality of service. To each one,"Thank you."

Putting this report together each year is a major effort for several people. Only those who have been involved can fully understanal what a greatjob Joan Stueve and Eralee Jordan have done in the data-gathering, organization, and keybo'a-ding of this Annual Report.IThanks, Joan and Eralee!

In addition, Erin Cimbri provided significant help in converting Access database information into word processor documents. Thanks, Erin!

B. Executive Summary In October 2002, A. C. Klein assumed the position of Dir6ctor of the Radiation Center and is officially authorizing this edition of the annual report following the retirement of S.E. Binney. A.

D. Hall resigned the Reactor Supervisor position shortly after the reportingperiod began and G.

M. Wachs assumed the Reactor Supervisor Position for the duration ofthe time covered by this report.

The data from"this reporting year shtbow that the use of the Radiation Ceinter and OSTR has continued to grow in many areas.

Overview I - 1

The Radiation Center supported 94 different courses this year, mostly in the Department ofNuclear Engineering. About one-quarter of these courses involved the OSTR. The number of OSTR hours used for academic courses and training was 724, while 2145 hours0.0248 days <br />0.596 hours <br />0.00355 weeks <br />8.161725e-4 months <br /> were used for research projects.

Eighty-one percent ofthe OSTR research hours were in support of off-campus research projects, which reflects the increasing wider use of the OSTR nationally and internationally. Radiation Center users published 96 articles this year, with 22 more submitted for publication. There were also 15 theses completed and 34 presentations made by Radiation Center users. The number of samples irradiated in the reactor during this reporting period was 6660. Funded OSTR use hours comprised 100 % ofthe research use. This is consistent with the move to a more full cost recovery basis for services provided by the Center. The OSTR continues to be the facility of choice for many of the 39

" Ar/40Ar and fission track geochronology laboratories around the world.

Personnel at the Radiation Center conducted 111 tours of the facility, accommodating 1,425 visitors. The visitors included elementary, middle school, high school, and college students; relatives and friends; faculty-, current and prospective clients; national laboratory and industrial scientists and engineers; and state, federal and international officials. The Radiation Center is a significant positive attraction on campus because visitors leave with a good impression of the facility and of Oregon State University.

Research projects ofpersonnel housed in the Radiation Center totaled approximately $2.5 million for this year.

The Radiation Center projects database continues to provide a useful way of tracking the many different aspects of work at the facility. The number of projects supported this year was 134.

Reactor projects comprised 63% of all projects. The total research supported by the Radiation Center, based on 40 user responses, was $3,894,218. The actual total is likely considerably higher.

This year the Radiation Center provided service to research faculty and students from 96 different institutions, 54% ofwhich were from other states and 15% of which were from outside the U. S.

and Canada. So while the Center's primary mission is local, it is also a facility with a national and international clientele.

The Radiation Center web site provides an easy way for potential users to evaluate the Center's facilities and capabilities as well as to apply for a project and check use charges. The address is:

http://www.ne.orst.edu/facilities/radiationcenter.

C. Introduction The current annual report of the Or'egon State University Radiation Center and TRIGA Reactor follows the usual format by including information relating to the entire Radiation Center rather than just the reactor. However, the information is still presented in such a manner that data on the reactor maybe examined separately, ifdesired. It should be noted that all annual data given in this report cover the period from July 1,2001 through June 30, 2002. Cumulative reactor operating data in this report relate only to the FLIP-fueled core. This covers the period from August 1, 1976 through Overview I - 2

June30, 2002* For a summary of data on the reactor's original 20% enriched core, the reader is referred to Table IV.A.2 in Part IV of this report or to the 1976-77 'Annual Report if a more comprehensive review is needed.

In addition to providing general information Center, this report about the activities ofthe RadiationCommission, is designed to meet the reporting requirements of the U. S. Nuclear Regulatory the U.

S. Department of Energy, and the Oregon Office of Energy. -Because of this, the report is divided into several distinct parts so that the reader may easily find the sections of interest.

D. Overview of the Radiation Center The Radiation Center is a unique facility which serves the entire OSU campus, all other institutions within the Oregon University System, and many other universities and organizations throughout the nation and the world. 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 Office, the OSU Institute ofNuclear Science and Engineering and Radiation Health Physics, and for the OSU nuclear chemistry, radiation chemistry, geochemistry and cosmochemistry programs. There is no other universityfacility with the combined capabilitiesof 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 6teaching and research facilities. They include a TRIGA Mark II research nuclear reactor; a 'Co gamma irradiator; a large number of state-of-the art computer-based gamma radiation spectrometers and associated germanium detectors; and a variety of instruments for radiation measurements and monitoring. Specialized facilities for radiation work inclide teaching and research laboratories with instrumentation and related equipment for performing neutron activation analysis and radiotracer studies; laboratories for plant experinents involving iadioactivity;, a facility for repair and calibration of radiation protection instarmentation; and facilities for iackaging radioactive materials for shipment to national and international destinations.

A major non-nuclear facility housed in the Radiation C6nter is~the one-quarter scale thermal hydraulic advanced plant experimental (APEX) test facility for the Westinghouse AP600 reactor passive design. The AP,600 is a next-generation nuclear reactor design which incorporates many at safety features as well as considerably simplified plafit systems and equipment. APEX operates pressures up to 400 psia and temperatures up to 450°F rising electrical heaters instead of nuclear fuel. All maj or components of the AP600 are included in APEX and all systems are appropriately of scaled to enable the experimental measurements to be used for safety eValuhations and licensing to provide the full scale plant. This world-class facility meets exacting quality assurance criteria assurance of safety as well as validity of the test results.

Overview I - 3

Also housed in the Radiation Center is the Advanced Thermal Hydraulics Research Laboratory, which is used for state-of-the-art two-phase flow experiments, and the Nuclear Engineering Scientific Computing Laboratory.

The Radiation Center staff regularly provides direct support and assistance to OSU teaching and research programs. Areas of expertise commonly involved in such efforts include nuclear engineering, nuclear and radiation chemistry, neutron activation analysis, radiation effects on biological systems, radiation dosimetry, environmental radioactivity, 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.

In addition to formal academic and research support, the Center's staff provides a wide variety of other services including public tours and instructional programs, and professional consultation associated with the feasibility, design, safety, and execution of experiments using radiation and radioactive materials.

E. Summary of Environmental and Radiation Protection Data

1. Liquid Effluents Released (See Table V.B. 1.a)

a. Total estimated quantity of radioactivity none released (to the sanitary sewer)0) (2)

b. Detectable radionuclides in the liquid waste none

c. Estimated average concentration of released none radioactive material at the point of release

d. Percent of applicable monthly average none concentration for released liquid radioactive material at the point of release

e. Total volume of liquid effluent released, 4.308 gallons 3

including diluent( )

2. Liquid Waste Generated and Transferred (See Table V.B. Lb)

a. Volume of liquid waste packaged(4) 30 gallons

b. Detectable radionuclides in the waste 3 H, 32 P, 59Fe 65 Zn, 86 Rb Overview I - 4

c. Total quantity of radioactivity in the waste 5.52 x 10.' Ci (1) OSU has implemented apolicyto reduce radioactive wastes disposed to the sanitary sewer to the absolute minimum.

(2) The OSU operational policy is to subtract only detector background from the water analysis data and not background radioactivity in the Corvallis city water.

(3) Total volume of effluent plus diluent does not take into consideration the additional mixing with the over 250,000 gallons per year of liquids and sewage normally discharged by the Radiation Center complex into the same sanitary sewer system.

(4) TRIGA and Radiation Center liquid waste is picked up by the Radiation Safety Office for transfer to its waste processing facility for solidification and final packaging

3. Airborne Effluents Released (See Table V.B.2)

a. Total estimated quantity of radioactivity 2.71 Ci released 41Ar (t, 1.83 hr)

b. Detectable radionuclides in the gaseous =

wasteo)

c. Estimated average atmospheric diluted 1.84 x 10s ý.Ci ml-'

concentration of 4 tAr at the point of release

d. Percent of applicable monthly average 0.46%

concentration for diluted concentration of 41Ar at the point of release

e. Total estimated release of radioactivity None in particulate form with half lives' greater than 8 days(2)

4. Solid Waste Released (See Table V.B.3)

a. Total amount of solid waste packaged and 44.5 ft3 disposed of 3H, 14C, 46Sc, 47Sc,

b. Detectable radionuclides in the solid waste 54Mn, 58 60 Co, Co, 22 Na, 5 9Fe, 90Sr, 18 1I, 137Cs, 238 U, 75 Se, 89Rb, Overview I- 5

I

c. Total radioactivity in the solid waste 5.2 x 10.2 Ci (1) Routine gamma spectroscopy analysis of the gaseous radioactivity in the stack discharge indicated that it was all 41Ar.

(2) Evaluation ofthe detectable particulate radioactivity in the stack discharge confirmed its origin as naturally occurring radon daughter products, predominantly 214Pb and 214Bi, which are not associated with reactor operations.

5. Radiation Exposure Received by Personnel (See Table V.C. 1)

a. Facility Operating Personnel (mrem)

(1) Average whole body 8 (2) Average extremities 17 (3) Maximum whole body 63 (4) Maximum extremities 549

b. Key Facility Research Personnel (1) Average whole body 0 (2) Average extremities <1 (3) Maximum whole body 0 (4) Maximum extremities 24

c. Facilities Services Maintenance Personnel (1) Average whole body <1 (2) Maximum whole body 10

d. Class Students (1) Average whole body <1 (2) Average extremities <1 (3) Maximum whole body 23 (4) Maximum extremities 107

e. Campus Police and Security Personnel (1) Average whole body <1 Overview I - 6

(2) Maximum whole body 12

f. Visitors (1) Average whole body <1 (2) Maximum whole body 8

6. Number of Routine Onsite and Offsite Monitoring Measurements and Samples

a. Facility Survey Data (1) Area Radiation Dosimeters (See Table V.D.1)

(a) Beta-gamma dosimeter measurements 68 (b) Neutron dosimeter measurements 68 (2) Radiation and Contamination Survey ~-5000 measurements (See Table V.D.3)

b. Environmental Survey Data (1) Gamma Radiation Monitoring (See Tables V.E.1 and V.E.2)

(a) Onsite monitoring

-- OSU TLD monitors 108

-- ICN TLD monitors , 108

-- Monthly pIrem h-' measurements 108 (b) Offsite monitoring

-- OSU TLD monitors 240

-- ICN TLD monitors 144

-- Monthly L.rem h-' measurements 240 (2) Soil, Water and Vegetation Surveys (See Table V.E.3)

(a) Soil samples 16 (b) Water samples 13 (c) Vegetation samples 56 Overview I- 7

F. History A brief chronology of the key dates and events in the history of the OSU Radiation Center and the TRIGA reactor is given below:

June 1964 Completion of the first phase of the Radiation Center, consisting of 32,397 square feet of office and laboratory space, under the direction of founding Director, C. H. Wang.

July 1964 Transfer of the 0.1 W AGN 201 reactor to the Radiation Center. This reactor was initially housed in the Department of Mechanical Engineering and first went critical in January, 1959.

October 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.

October 1967 Formal dedication of the Radiation Center.

August 1969 OSTR licensed to operate at a maximum steady state power of 1 MW, but could do so only for short periods of time due to lack of cooling capacity.

June 1971 OSTR cooling capacity upgraded to allow continuous operation at 1 MW.

April 1972 OSTR Site Certificate issued by the Oregon Energy Facility Siting Council.

September 1972 OSTR area fence installed.

December 1974 AGN-201 reactor permanently shut down.

March 1976 Completion of 1600 square feet of additional space to accommodate the rapidly expanding nuclear engineering program.

July 1976 OSTR refueled with 70% enriched FLIP fuel.

Overview I - 8

July 1977 Completion of a second -1600 square feet of space to bring the Radiation Center complex to a total of 45,553 square feet.

January 1980 Major upgrade of the electronics in the OSTR control console.

July 1980 AGN-201 reactor decommissioned and space released for unrestricted use.

June 1982 Shipment of the original 20% enriched OSTR fuel to Westinghouse Hanford Company.

December 1984 C. H. Wang retired as director. C. V. Smith became new director.

August 1986 Director C. V. Smith left to become Chancellor of the University of Wisconsin-Milwaukee. A. G. Johnson became new Director.

December 1988 AGN-201 components transferred to Idaho State University for use in their AGN-201 reactor program.

December 1989 OSTR licensed power increased to 1.1 MW.

June 1990 Installation of a 7000 Ci 6"Co Gammacell irradiator.

March 1992 25th anniversary of the OSTR initial criticality.

November 1992 Start of APEX plant construction.

June 1994 Retirement of Director A. G. Johnson. B. Dodd became new Director.

August 1994 APEX inauguration ceremony.

August 1995 Major external refurbishment: new roof, complete repaint, rebuilt parking lot, addition of landscaping and lighting.

September 1998 B. Dodd left on a leave of absence to the International Atomic Energy Agency. S. E. Binney became new Director.

January 1999 Installation of the Argon Production Facility in the OSTR.

April 1999 Completion of ATHRL facility brings the Radiation Center complex to a total of 47,198 square feet.

Overview I- 9

July 2002 S. E. Binney retired. J. F. Higginbotham became interim director.

October 2002 A. C. Klein became new director.

Overview I - 10

Part II PEOPLE This part contains a listing of all people who were residents ofthe Radiation Center or who worked a significant amount of time at the Center during this reporting period. Sections A, B, and C list the academic staff, trainees, and students, while sections D through G list the Radiation Center's operating staff. Section H shows the OSU Radiation Safety Office staff, and section I provides the composition ofcommittees 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 in this part. Summary information on the number of people involved is given in Table VI.C.1, while individual names and projects are listed in Tables VI.C.2 and VI.C.3.

A. Professional and Research Faculty

• Binney, Stephen E.

Director, Radiation Center Director, Institute of Nuclear Science and Engineering Professor Nuclear Engineering and Radiation Health Physics

• Brock, Kathryn M.

Faculty Research Assistant Health Physicist

• Conrady, Michael R.

Faculty Research Assistant Analytical Support Manager Craig, A. Morrie Professor College of Veterinary Medicine Daniels, Malcolm Professor Emeritus Chemistry

• OSTR users for research and/or teaching.

People 11- 1

Groome, John T.

Faculty Research Assistant ATHRL Facility Operations Manager Nuclear Engineering Gunderson, Chris E.

Faculty Research Assistant ATHRL Facility Operator/Test Engineer Nuclear Engineering Haggerty, Roy Assistant Professor Geosciences Hamby, David Associate Professor Nuclear Engineering Hart, Lucas P.

Faculty Research Associate Chemistry Harvey, Richard Faculty Research Assistant Nuclear Engineering

• Higginbotham, Jack F.

Chairman, Reactor Operations Committee Professor Nuclear Engineering and Radiation Health Physics

• Higley, Kathryn A.

Associate Professor Nuclear Engineering and Radiation Health Physics Johnson, Arthur G.

Director Emeritus, Radiation Center Professor Emeritus Nuclear Engineering and Radiation Health Physics

• OSTR users for research and/or teaching.

People1- 2

Klein, Andrew C.

Department Head, Department of Nuclear Engineering Director, Oregon Space Grant Program Professor Nuclear Engineering

• Krane, Kenneth S.

Professor Physics Krebs, Rolf Faculty Research Associate Crop and Soil Science Lafi, Abd Y.

Assistant Professor Senior Research ATHRL Research Analyst Nuclear Engineering

• Loveland, Walter D.

Professor Chemistry

• Meredith, Charlotte C.

Faculty Research Assistant College of Oceanic and Atmospheric Sciences Mommer, Niels K.

Faculty Research Associate Physics

• Palmer, Todd S.

Associate Professor Nuclear Engineering

• Pastorek, Christine Senior Instructor Chemistry Popovich, Milosh Vice President Emeritus

• OSTR users for research and/or teaching.

People 1I - 3

• Prahl, Frederick G.

Professor College of Oceanic and Atmospheric Sciences Reyes, Jr., Jos6 N.

ATHRL Principal Investigator Professor Nuclear Engineering Ringle, John C.

Professor Emeritus Nuclear Engineering Robinson, Alan H.

Department Head Emeritus Nuclear Engineering

• Schmitt, Roman A.

Professor Emeritus Chemistry

• Schtitfort, Erwin G.

Faculty Research Assistant Project Manager

• Sullivan, Barbara E.

Faculty Research Assistant College of Oceanic and Atmospheric Sciences Wang, Chih H.

Director Emeritus, Radiation Center Professor Emeritus Nuclear Engineering Young, Roy A.

Professor Emeritus Botany and Plant Pathology

• OSTR users for research and/or teaching.

People 11- 4

B. Visiting Scientists and Special Trainees Advisor or Research Name Field (Affiliation) ProgramDirector Cloughsey, Michael ASE Summer Student,, W. D. Loveland Gallant, Aaron Saturday Academy Mentorship Program W. D. Loveland Crescent Valley High School Corvallis, Oregon Nicholas Myers ASE Summer Student W. D. Loveland Rouki, Chariklia Visiting Scientist, Chemistry "W.D. Loveland Peterson, Don Postdoctoral Assistant, Chemistry W. D., Loveland C. OSU Graduate Students Degree Name Program Field " Advisor Abel, Kent MS Nuclear Engineering J. N. Reyes Antoine, Stephanie MS Nuclear Engineering R. N. Reyes Bak, Michael MS Radiation Health Physics K. A. Higley

• Bergman, Joshua J. MS Radiation Health Physics S. E. Binney Bittle, Whitney MS Nuclear Engineering T. S. Palmer Buchholz, Matthew MS Radiation Hefalth Physics J. F: Higginbotham Coleman, Joseph MS Radiation Health Physics D. M. Hamby Duffy, William MS Radiation Health Physics K. A. Higley Hart, Kevin MS Radiation Health Physics K. A. Higley Haugh, Brandon MS Nuclear Engineering" *J. N. Reyes Huang, Zhongliang PhD Nuclear Chemistry W. D. Loveland Kim, Kang Seog PhD Nuclear Engineering T. S. Palmer Kincaid, Kevin MS Nuclear Engineering J. N. Reyes Kriss, Aaron PhD Radiation Health Physics' D M.MHamby Moss, Stephen C. MS Radiation Health Physics K. A. Higley Napier, Bruce PhD Radiation Health Physics D. M. Hamby Nes, Elena MS Radiation Health Physics K. A. Higley Nes, Razvan MS Nuclear Engineering I - * 'T. S. Palmer Mallory, Stacy MS Radiation Health Physics D. M. Hamby Rains, Bruce MS Nuclear Engineering - T: S. Palmer Ralph, Benjamin MS Nuclear Engineering IJ. N. Reyes

• OSTR users for research and/or teaching.

PeopleII- 5

Rock, Mollie MS Radiation Health Physics D. M. Hamby Saiyut, Kittiphong PhD Nuclear Engineering J. F. Higginbotham Stringham, Michael MS Nuclear Engineering T. S. Palmer Tang, Hong PhD Nuclear Engineering Q. Wu Villamar, Glenda MS Radiation Health Physics K. A. Higley Welter, Kent B. PhD Nuclear Engineering T. S. Palmer Wiltman, Timothy MS Nuclear Engineering T. S. Palmer Yao, You PhD Nuclear Engineering Q. Wu Yoo, Yeon-Jong PhD Nuclear Engineering J. N. Reyes Young, Eric MS Nuclear Engineering J. N. Reyes D. Business, Administrative and Clerical Staff Director, Radiation Center ....................................... S. E. Binney Business Manager ........................................... S. C. Campbell Office Coordinator ............................................. J. M . Stueve Office Specialists ............................................... E. D. Jordan Custodian ....................................................... E. Cim bri Office Coordinator (Nuclear Engineering) ............................ R. A. Keen Word Processing Technician (Nuclear Engineering) .................. L. J. Robinson Word Processing Technician (ATHRL - Nuclear Engineering) ........... T. L. Culver E. Reactor Operations Staff Principal Security Officer ............... ........ S. E. Binney Reactor Administrator .................. .......... S.R. Reese Reactor Supervisor, Senior Reactor Operator ......... G. M. Wachs Senior Reactor Operator ................. .......... S.P. Smith S. T. Keller J. F. Higginbotham Reactor Operator ...................... ........ N. A. Carstens J. A. Ammon M. A. Minton F. Radiation Protection Staff Senior Health Physicist ......................................... K. M . Brock Health Physicist ................................................ S. A. M enn Health Physicist .............................................. J. E. Darrough Health Physicist ............................................... J. J. Bergm an People1I - 6

Health Physics Monitors (Students) .................................. M. Cheyne K. Fenton M. Hackett

• M. Helie C. Hepler J. Wallace G. Scientific Support Staff Analytical Support Manager .............. ...................... M. R. Conrady Projects M anager ............................................ E. G. Schfitfort Neutron Activation Analysis Technicians (Students) .................... S. Antoine E. Nes R. Nes A. Saptura Scientific Instrument Technician ................................... S. P. Smith Nuclear Instrumentation Support .................................... Z. Kenney H. OSU Radiation Safety Office Staff

'Radiation Safety Officer ......................................... R. H. Farmer Assistant Radiation Safety Officers ................................ D. L. Harlan M. E. Bartlett Offi ce M anager ................................................. K. L. M iller Lab Technician ............................................ P. A. Schoonover Student Technicians .............................................. W . Duffy A. Maple M. Rock B. Brumm I. Committees

1. Reactor Operations Committee Name Affiliation J. F. Higginbotham, Chair ........................... Nuclear Engineering S. E. Binney .................... Radiation Center and Nuclear Engineering G. M . W achs ........................................ Radiation Center A. C. Klein ...................................... Nuclear Engineering People II- 7

K. M . Brock ......................................... Radiation Center W. J. Richards ....................... McClellan Nuclear Radiation Center J. C. Ringle ...................................... Nuclear Engineering S. R. Reese ...................... Radiation Center and Nuclear Engineering M . H. Schuyler ............................................ Chemistry W . H. W arnes .................................. Mechanical Engineering

2. Radiation Safety Committee (OSU)

Name Affiliation T. Dreher, Chair .......... ..................... M icrobiology J. Higginbotham, Vice Chair . ............... Nuclear Engineering R. Farmer, Secretary and RSO ............. Radiation Safety Office R. Collier ................ .... Oceanic and Atmospheric Science B. Francis ................ ..... Environmental Health and Safety M . Leid ................. ........................ Pharm acy C. Snow ................. .......... Exercise and Sport Science J. Steiner ................. .. USDA-ARS/Crop and Soil Science K. Ahem ................ ........... Biochemistry/Biophysics T. W olpert ............... ......... Botany and Plant Pathology

3. Radiation Center Safety Committee Name Affiliation W . D. Loveland, Chair ............................. ........ Chemistry K . M . Brock ..................................... ... Radiation Center M . R. Conrady ................................... ...Radiation Center J. T. G room e .................................... Nuclear Engineering J. F. Higginbotham ................................ Nuclear Engineering K . L. M iller ..................................... ... Radiation Safety People 1I- 8

Part III FACILITIES A. Research Reactor

1. Description 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 serves to reflect neutrons back into the core.

The core is situated near the bottom ofa 22-foot deep water-filled tank, and the tank is surrounded by a concrete bioshield which acts as a radiation shield and structural support.

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 2500 MW.

The OSTR has a number of different irradiation facilities including a pneumatic transfer tube, a rotating rack, a thermal column, fourbeam ports, five sample holding (dummy) fuel elements for special in-core irradiations, an in-core irradiation tube, and a cadmium-lined in-core irradiation tube for experiments requiring a high energy neutron flux. The OSTR also has an Argon Irradiation

-Facility for the production of 41Ar.

The pneumatic transfer facility enables samples to be inserted and removed from the core in four to five 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 ofwhich can hold two sample tubes. Rotation of the rack ensures that each sample will receive an identical irradiation.

The reactor's thermal column consists of a large stack of graphite blocks which slows down neutrons from the reactor core in order to increase thermal neutron activation of samples. Over 99% ofthe neutrons in the thermal column are thermal neutrons. Graphite blocks are removed from the thermal column to 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. One 4

ofthe beam ports contains the Argon Production Facility forproduction of curie levels of" Ar.

The other beam ports are available for a variety of experiments.

Facilities111-1

ffsamples which are to be irradiated require a large neutron fluence, especially from higher energy neutrons, they maybe inserted into a dummy fuel element. This device will then be placed into one of the core's inner grid positions which would normally be occupied by a fuel element.

Similarly samples can be placed in the in-core irradiation tube (ICIT) which can be inserted in the same core location.

The cadmium-lined in-core irradiation tube (CLICIT) 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 higher energy 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 normallybe occupied by a fuel element. It is the same as the ICIT except for the presence of the cadmium lining.

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 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> during a typical work week.

a. Instruction Instructional use of the reactor is twofold. First, it is used significantly for classes in Nuclear Engineering, Radiation Health Physics, 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 demonstrations 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 O STR involves education ofreactor operators, operations managers, and health physicists. The OSTR is in a unique position to provide such education since curricula must include hands-on experience at an operating reactor and in associated laboratories. The many types of educational programs that the Radiation Center provides are more fully described in Part VI (Section VI.C.5) of this report.

During this reporting period the OSTR accommodated 24 different OSU academic classes and other academic programs. In addition, portions of classes from other Oregon universities were also supported by the OSTR. The OSU teaching and training programs utilized 724 hours0.00838 days <br />0.201 hours <br />0.0012 weeks <br />2.75482e-4 months <br /> of reactor time. Tables III.A. 1 and III.A.2, as well as Table III.D. 1,provide detailed information on the use of the OSTR for instruction and training.

Facilities111-2

b. Research The OSTR is a unique and valuable tool for a wide variety ofresearch applications and serves as an excellent source of neutrons and/or gamma radiation. The most commonly used experimental technique requiring reactor use is instrumental neutron activation analysis (INAA).

This is a particularly sensitive method of elemental analysis which is described in more detail in Part VI (Section VI.C. 1). Part llI.B provides a listing of equipment used in INAA at the Radiation Center.

The OSTR's irradiation facilities provide a wide range of neutron flux levels and neutron flux qualities which are sufficient to meet the needs of most researchers..This is true not only for INAA, but also for other experimental purposes such as the "Ar/4Ar ratio and fission track methods of age dating samples.

During this reporting period, the OSTR accommodated 50 funded and 8 unfunded research projects. Details of the reactor's use specifically for research are given in Table III.A.3.

Additional information regarding reactor use for research, thesis, and service can be found in Tables VI.C. 1 through VI.C.3. In Table VI.C. 1 OSTR use is indicated with an asterisk.

B. Analytical Equipment

1. Description The Radiation Center has a large variety ofradiation detection instrumentation. This equipment is upgraded as necessary, especially the gamma ray spectrometers with their associated computers and germanium detectors. During the previous year four new germanium detectors and six digital multichannel analyzers were purchased. Tables II.B. 1 through II.B.3 provide a brief listing of laboratory counting devices present at the Center. Additional equipment for classroom use and an extensive inventory of portable radiation detection instrumentation are also available.

2. Utilization Radiation Center nuclear instrumentation receives intensive use in both teaching arnd research applications. In addition, service projects also use these systems and the combined use often results in 24-hour per day schedules for many of the analytical instruments. Use of Radiation Center equipment extends beyond that located at the Center and instrumentation maybe made available on a loan basis to OSU researchers in other departments.

Facilities111-3

I C. Radioisotope Irradiation Sources

1. Description The Radiation Center is equipped with a 1,644 curie (as of 7/27/01) Gammacell 220 6°Co irradiator which is capable of delivering high doses of gamma radiation over a range of dose rates to a variety of materials.

Typically, the irradiator is used by researchers wishing to perform mutation and other biological effects studies; studies in the area ofradiation chemistry;, dosimeter testing; sterilization offood materials, soils, sediments, biological specimen, and other media; gamma radiation damage studies; and other such applications. In addition to the 6"Co irradiator, the Center is also equipped with a variety of smaller 'Co, 3 T 7 Cs, 226Ra, plutonium-beryllium, and other isotopic sealed sources of various radioactivity levels which are available for use as irradiation sources.

2. Utilization During this reporting period there was a diverse group of projects using the 'Co irradiator. These projects included the irradiation of a variety of biological materials including different types of seeds. In addition, the irradiator was used for sterilization of several media and the evaluation of the radiation effects on different materials. Table III.C. 1provides use data for the Gammacell 220 irradiator.

D. Laboratories and Classrooms

1. Description The Radiation Center is equipped with a number of different radioactive material laboratories designed to accommodate research projects and classes offered by various OSU academic departments or off-campus groups.

Instructional facilities available at the Center include a laboratory especially equipped for teaching radiochemistry and a nuclear instrumentation teaching laboratory equipped with modular sets of counting equipment which can be configured to accommodate a variety of experiments involving the measurement ofmany types of radiation. The Center also has four student computer rooms equipped with a large number of personal computers and UNIX workstations.

In addition to these dedicated instructional facilities, many other research laboratories and pieces of specialized equipment are regularlyused for teaching. In particular, classes are routinely given Facilities111-4

access to gamma spectrometry equipment located in Center laboratories. A number ofclasses also regularly use the OSTR and the Reactor Bay as an integral part oftheir instructional coursework.

There are two classrooms in the Radiation Center which are capable of holding about 35 and 18 students, respectively. In addition, there are two smaller conference rooms and a library that are suitable for graduate classes and thesis examinations. .As a service to the student body, the Radiation Center also provides an office area for the student chapters of the American Nuclear Society and the Health Physics Society.

This reporting period saw continued high utilization of the Radiation Center's thermal hydraulics laboratory. This laboratory is being used byNuclear Engineering faculty member to accommodate a one-quarter scale model of the Palisades Nuclear Power reactor. The multi-million dollar advanced plant experimental (APEX) facility was fully utilized by the U. S. Nuclear Regulatory Commission to provide licensing data and to test safety systems in "beyond design basis" accidents.

The fully scaled, integral model APEX facility uses electrical heating elements to simulate the fuel elements, operates at 450'F and 400 psia, and responds at twice real time. It is the only facility of its type in the world and is owned by the U. S. Department of Energy and operated by OSU.

In addition, a new building, the Air-water Test Loop for Advanced Thermal-hydraulics Studies (ATLATS), was constructed next to the Reactor Building in 1998. Two-phase flow experiments are conducted in the ATLATS. Together APEX and ATLATS comprise the Advanced Thermal Hydraulics Research Laboratory (ATHRL).

2. Utilization All of the laboratories and classrooms are used extensively during the academic year. For example, a listing of 119 courses accommodated at the Radiation Center during this reporting period along with their enrollments is given in Table IH.D. 1.

E. Instrument Repair and Calibration Facility

1. Description The Radiation Center has a facility for the repair and calibration of essentially all types of radiation monitoring instrumentation. This includes instruments for the detection and measurement ofalpha, beta, gamma, and neutron radiation.It encompasses both high range instruments for measuring intense radiation fields and low range instruments used to measure environmental levels of radioactivity. The Center's instrument calibration capability is described more completely in Section VI.C.7 of this report.

Facilities111-5

2. Utilization The Center's instrument repair and calibration facility is used regularly throughout the year and is absolutely essential to the continued operation of the many different programs carried out at the Center. In addition, the absence of any comparable facility in the state has led to a greatly expanded instrument calibration program for the Center, including calibrationofessentiallyall radiationdetection instruments used by state andfederal agencies in the state of Oregon.

This includes instruments used on the OSU campus and all other institutions in the Oregon University System, plus instruments from the Oregon Health Division's Radiation Protection Services, the Oregon Office of Energy, the Oregon Public Utilities Commission, the Oregon Health Sciences University, the Army Corps of Engineers, and the U. S. Environmental Protection Agency. Additional information regarding instrument repair and calibration efforts is given in Tables VI.C.4, VI.C.5, and VI.C.6.

F. Library

1. Description The Radiation Center has a library containing significant collections oftexts, research reports, and videotapes relating to nuclear science, nuclear engineering, and radiation protection.

The Radiation Center is also a regular recipient of a great variety of publications from 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, the Center library maintains a current collection of leading nuclear research and regulatory documentation. In addition, the Center has a collection over 50 sets of nuclear power reactor SafetyAnalysis Reports and Environmental Reports specificallyprepared byutilities for their facilities.

The Center maintains an up-to-date set of reports from such organizations as the International Commission on Radiological Protection, the National Council on Radiation Protection and Measurements, and the International Commission on Radiological Units. Sets of the current U.S.

Code of Federal Regulations for the U.S. Nuclear Regulatory Commission, the U.S. Department of Transportation, and other appropriate federal agencies, plus regulations of various state regulatory 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 topics. 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 Facilities111-6

Radiation Center staff, using the Center's videotape equipment and the facilities of the OSU Communication Media Center.

2. Utilization The Radiation Center library is used mainly to provide reference material on an as-needed basis.

It receives extensive use during the academic'year. In addition, the orientation videotapes are used intensively during the beginning of each term and periodically thereafter.

Facilities111 -7

Table III.A.1 OSU Courses Using the OSTR Course Number Course Name NE 482 Applied Radiation Safety GEO 330 Environmental Conservation Chem 462 Experimental Chemistry II Chem 222 General Chemistry Chem 225H Honors General Chemistry NE 114 Introduction to Nuclear Engineering and Radiation Health Physics NE 451 Neutronic Analysis and Lab I NE 452/552 Neutronic Analysis and Lab II NE 453/553 Neutronic Analysis and Lab III NE 116 Nuclear Engineering NE 236 Nuclear Radiation Detection and Instrumentation Chem 419/519 Radioactive Tracer Methods NE 122 Reactor Kinetics Advanced Physics Class REU Physics students SMILE Science and Math Investigative Learning Experiences Adventures in Learning Visiting Students Facilities111-8

Table III.A.2 OSTR TeachingHours Cumulative Values for FLIP Core (hours)

Departmental Adventures in Learning 2.1 Chemistry 23.8 Engineering Science 05 Geosciencest1 ) 1.2 Nuclear Engineering 19.4 Physics 1.5 SMILE 1.3 Departmental Total 49.8 7,658 Special Classes and Projects(2 _

Crescent Valley High School - AP Physics 6.0 Department of Science 3.2 Groups or Organizations from Educational 0.2 Institutions Liberty Christian High School 0.7 Reactor Staff 0.6 Reactor Staff Use 30.1 Operator License Training 633.0 Student Recruitment Tours 0.0 University of California at Berkeley Nuclear 0.2 Engineering Special Classes and Projects Total 674 5,848 3 4 13,506 TOTAL TEACHING HOURS( ' 'S) 724 (1) Some use hours bythese departments are not shown under "Teaching Hours," but are reflected under Thesis Research, both funded and unfunded.

(2) A variety of educational classes were conducted which involved one-time meetings for orientation or support purposes.

These included: high school science classes, new student programs support, community college classes, and classes from other universities. In addition, this category includes 633 hours0.00733 days <br />0.176 hours <br />0.00105 weeks <br />2.408565e-4 months <br /> of reactor operator training (3) See Table III.D.1 for classes and student enrollment.

(4) See Table IV.A.5 for a summary of all multiple reactor use.

(5) Total teaching hours reflect all the 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 Facilities111-9

Table III.A.3 OSTR Research Hours Annual Values Cumulative Values Types of Research (hours) for FLIP Core (hours)

OSU Research 420 9,109 Off-Campus Research 1,726 17,384 TOTAL RESEARCH HOURSO) 2,145 26,493 (1) Total research hours statistics:

(a) 100% (2145 hours0.0248 days <br />0.596 hours <br />0.00355 weeks <br />8.161725e-4 months <br />) of the total research hours were user-funded by federal, state, or other organizations.

(b) 0% 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.

Facilities11I -10

Table III.B.1 Radiation Center Spectrometry Systems:

Gamma, Low Energy Photon, Alpha Rel. Effie.

Room System (%)

B100 EG&G Ortec D-Spec MCA, HPGe 26.8' B100 EG&G Ortec D-Spec MCA, HPGe 38.2 B100 EG&G Ortec D-Spec MCA, HPGe 33.6 B100 EG&G Ortec D-Spec MCA, HPGe 28.6 B125 EG&G Ortec D-Spec MCA, HPGe 24.2%

D102 EG&G Ortec D-Spec MCA, HPGe 28.5%

B100 EG&G Ortec Adcam 8k-MCA, PGT LEP N/A B100 EG&G Ortec Adcam 8k-MCA, EG&G Ortec LEP N/A B100 EG&G Ortec Adcam 8K-MCA, HPGE 29.0 D102 EG&G Ortec Adcam 8K-MCA, HPGE 27.6%

C120 EG&G Ortec Ace 4k-MCA, NaI(T1) 3x3 N/A A146 EG&G Ortec Ace 4k-MCA, 576A Alpha Spectrometer N/A FacilitiesIII- 11

Table III.B.2 Radiation Center Proportional Counting Systems Room System A124 NMC AC5 84 A138 Protean MPC 9400 A138 Tennelec LB 5100 Auto Counting System w/IBM PC FacilitiesIII -12

f .

Table III.B.3 Thermoluminescent Dosimeter Systems Room System A132 Harshaw Model 2000 FacilitiesIII -13

Table III.C.1 Gammacell 220 6°Co Irradiator Use (1893 Ci: 7/1/00)

Purpose of Dose Range Number of Use Time Irradiation Samples (rads) Irradiations (hours) albumin, medical devices, chambers, bioflex strips, hamster 1.6 x 106 Sterilization cells, nutrients, to 37 1,074 patches syringes, 3.0 x 106 wood, soil, tissue, plastic tubes, 5.0 x 104 Material to 2 166 Evaluation gems, minerals, 9x 106 5.0 x 103 Botanical Studies bean seeds to 10 3 8.0 x 104 TOTALS 49 1243 FacilitiesIII- 14

Table III.D.1 Student Enrollment in Nuclear Engineering, Radiation Health Physics and Nuclear Science Courses Which Are Taught or Partially' Taught at the Radiafion Center Number of Students Course -Credit Course Title Fall Winter Spring Summer

.. . 2001 2002-- -2002 2002 Nuclear Engineering Department Courses NEIRHP 114* 2 Introduction to Nuclear Engineering and 15 - -

Radiation Health Physics NE/RHP 115 2 Introduction to Nuclear Engineering and 17 ---

Radiation Health Physics NE/RHP 116 2 Introdu ction to Nuclear Engineering'and -- 15 Radiation Health Physics NE/RHP234 4 Nuclear and Radiation Physics 1 20 --..

NEJRHP235 4 Nuclear and Radiation Physics II -- 21 --

NE/RHP236* 4 Nuclear Radiation Detection and - -- 18 Instrumentation NE319 3 Societal Aspects of Nuclear Technology -- -- 53 NE/RHP401 1-16 Research -- 1 I NE405H 1-16 R&CfUsed Nuclear Fuel: Garbage or Gold -- - 4 NE405 1-16 Reading and Conference RHP405 1-16 Reading irid Conference .......

NE/RHP406 1-16 Projects -- -- 4 -

NE/RHP407"" 1 Nuclear Engineering Seminar- 11 13 -17 -

NE/RHP410 1-12 Internihip 2 .-- -1 NE415 2 Nuclear Rules and Regulations -- - -- -

RHP415 2 Nuclear Rules and Regulati6iis - .....

NE450 3 ST/ Nuclear Mdicine -- - --

NE451 4 Neutr6nic Analysis and Lab I 4 ....

NE452 4 Neutronic Analysis and Lab II -- 5 -

NE453 4 Neutronic Analysis and Lab III -- - 5 --

ST = Special Topics

• = OSTR used occasionally for demonstration and/or experiments.

• • = OSTR used heavily. Facilities111-15

Table III.D.1 (continued)

Student Enrollment in Nuclear Engineering, Radiation Health Physics and Nuclear Science Courses Which Are Taught or Partially Taught at the Radiation Center NE457** 3 Nuclear Reactor Laboratory NE467 4 Nuclear Reactor Thermal Hydraulics 6 .....

NE474 4 Nuclear Systems Design I -- 5 ....

NE475 4 Nuclear Systems Design II . 5 NE479 1-4 Individual Design Project .......

RHP479 1-4 Individual Design Project .......

RHP480 1-3 Field Practice in Radiation Protection 1 .....

NERHP481 4 Radiation Protection 12 ......

NE/RHP482* 4 Applied Radiation Safety - 23 --

RHP483 4 Radiation Biology 8 ....

RHP487 3 Radiation Biology .....

RHP488 3 Radioecology .......

NE/RHP490 4 Radiation Dosimetry .... 14 -

RHP493 3 Non-reactor Radiation Protection ........

NE499 1-16 St/Environmental Aspects Nuclear Systems .......

RHP499 1-16 St/Envrionmental Aspects Nuclear Systems ......

NESO 1-16 Research -- 1 - -

RHP501 1-16 Research 1 -- I -

NE503 1 Thesis 7 6 6 -

RHP503 1 Thesis 6 3 2 2 NE/RHP505 1-16 Reading and Conference .- 2 NE/RHP506 1-16 Projects I -....

NE/RHP507/ 1 Nuclear Engineenng Seminar 9 6 7 -

607 NE507 1 Sem/Management of Mixed Waste ........

NE/RHP510 1-12 Internship  ! ......

ST = Special Topics

• = OSTR used occasionally for demonstration and/or experiments.

• • = OSTR used heavily. FacilitiesIII -16 I4

Table III.D.I (continued)

Student Enrollment in Nuclear Engineering, Radiation Health Physics and Nuclear Science Courses Which Are Taught or Partially Taught at the Radiation Center NE515 2 Nuclear Rules and Regulations . - I - -

RHP515 2 Nuclear Rules and Regulationjs _ - - -.

NE526 3 Computational Methods for Nuclear -- 1 -- -

Reactors NE/RHP535 3 Nuclear Radiation Shielding -- -- -

NE/RHP539 3 ST/Nuclear Physics for Engineers and -- -- -- -

Scientists NE/RHP543 3 Hi-Level Radioactive Waste Management .... 6 -

NE549 3 Low Level Waste .. -..

RHP549 3 Low Level Waste " -- --

NE550 3 Nuclear Medicine - -- --

NE551 4 Neutronic Analysis and Lab I 4 - - -

NE552 4 Neutronic Analysis and Lab i1 -- A -

NE553 4 Neutronic Analysis and L -- -L 2 -

NE557** 3 Nuclear Reactor Laboratory _ - -

NE559 1 ST/Nuclear Reactor Analysis: Criticality - -- -- -

-- Safety .

NE567 4' -Advanced Nuclear Reactor Thermal 3 . . -

Hydraulics NE568 3 Nuclear Reactor Safety - 7"7 7 -

NE569 1 ST/Thermal Hydraulic Instumentation 8 NE574 '4 Nuclear Systems Design I -- -2 - -

NE575 4 Nuclear Systems Design II 2 RHP580 1-3 Field Practice in Radiation Protection 2 .....

NE/RHP581 4 Radiation Protection 9 -....

NE 4 -Applied Radiation Safety -- 6 - -- ..

/RHP582*

RH1P583 4 Radiation Biology -- 5 -

ST = Special Topics

• = OSTR used occasionally for demonstration and/or experiments.

• • = OSTR used heavily. Facilities111-17

Table III.D.1 (continued)

Student Enrollment in Nuclear Engineering, Radiation Health Physics and Nuclear Science Courses Which Are Taught or Partially Taught at the Radiation Center NE585 3 Environmental Aspects Nuclear Systems ........

RHP585 3 Environmental Aspects Nuclear Systems ........

NE586 3 Advanced Radiation Dosimetry ......

RHP586 3 Advanced Radiation Dosimetry ......

RHP588 3 Radioecology ......

RHP589 1-3 ST/Radiation Protection and Risk .... 5 -

Assessment NE/RHP590 4 Radiation Dosimetry -- - 7 i__'

RHP593 3 Non-Reactor Radiation Protection -- - 4 NE599 I ST/Principles of Nuclear Medicine ....

NE601 1-16 Research RHP601 1-16 Research ...

NE603 1-16 Thesis 5 7 6 RHP603 1-163 Thesis 2 2 4 -

NE605 1-16 Reading and Conference ........

RHP605 1-16 Reading and Conference RHP610 1-12 Internship ........

NE654 3 Neutron Transport Theory -- 9 ....

NE667 3 Advanced Thermal Hydraulics ........

Courses from Other Departments CH222* 5 General Chemistry (Science Majors) -- 426 ....

CH225H 5 Honors General Chemistry -- 20 ....

CH462* 3 Experimental Chemistry II Laboratory -- 27 ....

ENGR331 4 Momentum, Energy and Mass Transfer -- 47 ....

GEO300 3 Environmental Conservation 10 ......

PH202 5 General Physics 12 .....

Courses from Other Institutions ENGRIlI I COCC Engineering 22 - -

GS 105 LBCC General Science 29 23 27 NOTE:

This table does not include the thesis courses from other OSU departments (see Table VI.C 2)

ST = Special Topics

• = OSTR used occasionally for demonstration and/or experiments.

• • = OSTR used heavily. Facilities111-18

Part IV Reactor

Part IV REACTOR A. Operating Statistics Operating 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.

Thermal energy generated in the reactor during this reporting period was 38.2 megawatt days (MWD). The cumulative thermal energy generated by the FLIP core now totals 985.9MWD from August 1, 1976 through June 30, 2002. Reactor use timeý') averaged 88.0% of the normal nine-hour, five-day per week schedule. Tables IV.A.3 through IV.A.5 detail the operating

.statistics applicable to this reporting period.

A single fuel element was removed from the core to increase calculated Shutdown Margin which was approaching the TS limit of $0.57 while in a Dummy/ICIT core configuration. 10CFR50.59 safety evaluation 01-09 analyzes the decrease in core reactivity of $0.22 by the removal of fuel element #8414 from core position F28.

(1) Reactor use time includes hours the reactor was critical or unavailable to irradiate samples due to startup/shutdown checks and operating maintenance.

B. Experiments Performed

1. Approved Experiments During the current reporting period there were seven approved reactor experiments, listed below, available for use in reactor-related programs.

A-1 Normal TRIGA Operation (No Sample Irradiation).

B-3 Irradiation of Materials in the Standard OSTR Irradiation Facilities.

B-1 I Irradiation ofMaterials Involving Specific Quantities of Uranium and Thorium in the Standard OSTR Irradiation Facilities.

B-12 Exploratory Experiments.

B-23 Studies Using TRIGA Thermal Column.

B-29 Reactivity Worth of Fuel.

B-30 NAA of Jet, Diesel, and Furnace Fuels.

B-31 TRIGA Flux Mapping.

B-32 Argon Production Facility Of the approved experiments on the active list, six were used during the reporting period.

A tabulation of information relating to reactor experiment use is given in Table 1V.B. 1 and includes a listing of the experiments which were used, how often each was used, and the general purpose of the use.

2. Inactive Experiments Presently 32 experiments are in the inactive file. This consists of experiments which have been performed in the past and maybe reactivated. Many ofthese experiments are now performed under the more general experiments listed in the previous section. The following list identifies these 32 inactive experiments.

A-2 Measurement of Reactor Power Level via Mn Activation.

A-3 Measurement of Cd Ratios for Mn, In, and Au in Rotating Rack.

A-4 Neutron Flux Measurements in TRIGA.

A-5 Copper Wire Irradiation.

A-6 In-core Irradiation of LiF Crystals.

A-7 Investigation ofTRIGA's Reactor Bath Water Temperature Coefficient and High Power Level Power Fluctuation.

B-1 Activation Analysis of Stone Meteorites, Other Meteorites, and Terrestrial Rocks.

B-2 Measurements of Cd Ratios of Mn, In, and Au in Thermal Column.

B-4 Flux Mapping.

B-5 In-core Irradiation of Foils for Neutron Spectral Measurements.

B-6 Measurements of Neutron Spectra in External Irradiation Facilities.

B-7 Measurements of Gamma Doses in External Irradiation Facilities.

B-8 Isotope Production.

B-9 Neutron Radiography.

B-10 Neutron Diffraction.

B-13 This experiment number was changed to A-7.

B- 14 Detection of Chemically Bound Neutrons.

B-15 This experiment number was changed to C- 1.

B-16 Production and Preparation of "8 F.

ReactorIV - 2

B-17 Fission Fragment Gamma Ray Angular Correlations.

B-18 A Study of Delayed Status (n, y) Produced Nuclei.

B-19 Instrument Timing via Light Triggering.

B-20 Sinusoidal Pile Oscillator.

B-21 Beam Port #3 Neutron Radiography'Facility.

B-22 Water Flow Measurements Through TRIGA Core.

B-24 General Neutron Radiography.

B-25 Neutron Flux Monitors.

B-26 Fast Neutron Spectrum Generator.

B-27 Neutron Flux Determination Adjacent to the OSTR Core.

B-28 Gamma Scan of Sodium (TED) Capsule.

C-1 PuO 2 Transient Experiment.

C. Unplanned Shutdowns There were thirteen unplanned reactor shutdowns during the current reporting period. A scram occurs when the control rods drop in'as a resiult of an automatic trip or as a result of the operator pushing the manual trip button. Dugti6 uriisual conditions or operational anomalies ofa less critical nature, the reactor may also be secured by manual rod insertion. Table IV.C. 1contains a summary of the unplanned scrams, including a brief description of the cause of each.

D. Changes to the OSTR Facility, to Reactor Procedures, and to Reactor Experiments Performed Pursuant to 10 CFR 50.59 The information contained in this section of the report piovides a summary of the changes performed during the reporting period under the provisions of 10 CFR 50.59. For each item listed, there is a brief description of the action taken and a summary of the applicable safety evaluation.

1. 10 CFR 50.59 Changes to the Reactor Facility There were 3 changes to the reactor facility during the reporting period.

For additional information r6garding these changes, or copies of the changes, contact the 0STR Operations staff.

(1) 01-04, Reactor Bay Ventilation System Upgrade Reactor IVX- 3

a. Description The reactor building ventilation system was upgraded by the installation of a pressure and temperature control master unit manufactured by Johnson Controls, INC., and its associated analog/digital input and output ports.

This upgrade modified the bay pressure control scheme to modulate air supply damper position to maintain bay negative pressure. In addition, reactor bay temperature is controlled based on inlet supply air temperature, local bay temperature detection, and direct steam supply control air modulation. This modification follows earlier repairs to the supply duct heating coils.

System operating characteristic adjustments and additional minor equipment enhancements were conducted following the conversion to ensure proper and efficient system operation.

(b) Safety Evaluation The consequences of control system failure were evaluated and compared to the current SAR calculations ofdoses based on various failure modes.

All of the failure modes resulted in consequences less than or equal to that previously evaluated in the SAR.

The probability of failure should not be greater than what is already experienced with equipment, such as pneumatic valve diaphragms, already in the system.

The requirement for automatic shutdown upon high stack gas or particulate activity remains in effect.

(2) 01-09, Removal of Fuel Element in GridPosition F28 (a) Description Fuel element #8414 was removed from the core to ensure TS limits of Shutdown Margin were being maintained while in all core configurations.

The reactivity worth of the removed fuel element was previously measured to be $0.22. The element removed from core position F28 was chosen Reactor IV - 4

for its location on the core periphery away from the neutron source and its distant proximity to active beam poits and riuclear instrumentation.

(b) Safety Evaluation This fuel element removal from the core is expected to increase maximum power density by no more than 1 kW per element in the core positions with the highest power densities (B ring). Previous data indicates that operation with higher power densities has been found acceptable. Current power densities will not increase above that which has already been shown to be acceptable.

(3) 02-01, Beam Port #3 Blockhouse (a) Description The shielded blockhouse on the end of Beam Port 3 was reconstructed to evaluate the feasibility ofperforming neutron radiography using industry standard film canisters similar to otheruniversityreactors. Large concrete blocks were used to fabricate a blockhouse encompassing a two-foot wide void and semi-enclosed cavity to form a backscatter shield. A movable side shield block allows access to the film canister holder for shutdown loading while ensuring adequate radiation shielding at full power.

An installed microswitch, connected to the reactor external scram bus relay, provides scram actuation should the rolling block access shield be moved during reactor operation. A local area radiation monitor is positioned directly in front of the access door to provide the control room with remote radiation level indication.

(b) Safety Evaluation The shielded blockhouse is constructed external to the reactor bioshield and will not affect the reactor's operation. Only the external reactor scram circuit is affected by the installation and operation of the beamport facility. The integrity of the blockhouse as a shield will be verified to reduce radiation levels to within tolerable limits. Dual protective features

'in the form of an externally actuated scram and installed ARM will minimize the possibility of creating a High Radiation Area near this facility.

The reduced reactor bay air volume will create higher than normal airborne radioactive material following a SSC malfunction, but the effect will not be significant.

ReactorIV- 5

2. 10 CFR 50.59 Changes to Reactor Procedures There were two changes to reactor procedures which were reviewed, approved and performed under the provisions of 10 CFR 50.59 during the reporting period.

For additional information regarding these changes, or copies ofthe changes, contact the OSTR Operations staff.

(1) 02-02, Revisions to OSTROP 11,17,18 (a) Description This procedure change corrected inconsistencies in language between the OSTROP procedures and Technical Specifications, i.e. shall for must.

Changes corrected typographical errors.

(b) Safety Evaluation The intent of each OSTROP will not be significantly altered. These changes make the language of each OSTROP more consistent with the TS or corrects typographical errors.

(2) 02-05, Revisions to OSTROP 6, 12, 18 (a) Description OSTROP 6 Deleted references to the Assistant Health Physicist. Clarified wording of access authorization form titles.

OSTROP 12 Added procedural step to coincide with the actual physical process of control rod testing preparation.

OSTROP 18 Corrected typographical errors and reworded section to reflect obsolescence of multi-copy forms.

Reactor IV - 6

(b) Safety Evaluation The intent of each OSTROP will not be significantly altered.

These changes will correct typographical errors.

3. 10 CFR 50.59 Changes to Reactor Experiments There were no changes to reactor experiments during this reporting period.

E. Surveillance and Maintenance

1. Non-Routine Maintenance July 7, 2001 Replaced bypass capacitor fin gaseous channel HV power supply.

August 8, 2001 Removed previously installed shim between shim rod upper and lower housing. Cleaned up binding wear areas inside lower assembly and on draw tube and enlarged foot switch actuating rod pass thru hole.

Replaced two lead acid batteries in inverter rack.

September 1, 2001 SIT evaluated Stack and CAM particulate and gas channel log rate circuits for possible problem causes. Isolated several old an defective printed circuit board solder joints.

Replaced Safe rod foot switch.

October 2001 Replaced ion chamber current monitoring Pico ammeter with new digital model.

November 2001 Scraped excess scale accumulation from Cooling Tower basin screens to increase basin drain flow.

December 2001 Safe rod up and down switches replaced.

January 2002 Replaced Control Room PA selector switch.

February 2002 Replace meteorological instrument bearings and position potentiometer.

Reactor IV- 7

Reconstructed Beam Port 3 to evaluate neutron radiograph facility feasibility.

March 2002 Replaced rabbit system air manifold hoses.

May 2002 Replaced internals on D-106 fan room steam traps.

June 2002 Replaced fire alarm system thermal detectors in Reactor Bay.

2. Routine Surveillance and Maintenance The OSTR has an extensive routine surveillance and maintenance (S&M) program.

Examples of typical S&M checklists are presented in Figures LV.E. 1 through IV.E.4.

Items marked with an asterisk (*) are required by the OSTR Technical Specifications.

F. Reportable Occurrences There were no reportable occurrences during this reporting period.

Reactor IV - 8

F r[-- F- -- F- I r- F F-- .. . . -

Table IV.A.1 OSTR Operating Statistics (Using the FLiP Fuel Core)

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 Through Through Through Through Through Through Through FLIP Core, June 30, 1977 June30, 1978 June30, 1979 June30, 1980 June30, 1981 June30, 1982 June 30,,1983 June 30, 1984 Operating Hours (critical) 875 819 458 875 1255 1192 1095 1205 Megawatt Hours 451 496 '255 571 1005 . 999 931 943 Megawatt Days 19.0 20.6 10.6 23.8 41.9 41.6 38.8 39.3 235U Grams Used 24.0 25.9 13.4 29.8 52.5 52.4 48.6 49.3 Hours at Full Power 401 481 1218 552 998 973 890 929 (I M W ).... . ...... .... .. . ..... ._ __...

Numbers of Fuel Eh6ments Added or '85 0 2 0 0 1 01 0 Removed (-)L _

Number of Irradiation 44 375 329 372 348 408 396 469 Requests _ _ _ _ _ __,

Table IV.A.1 (Continued)

OSTR Operating Statistics (Using the FLIP Fuel Core)

Operational Data July 1, 1984 July 1, 1985 July 1, 1986 July 1, 1987 July 1, 1988 July 1, 1989 July 1, 1990 July 1, 1991 July 1, 1992 for Through Through Through Through Through Through Through Through Through FLIP Core June 30, June 30, June 30, June 30, June 30, June 30, June 30, June 30, June 30, 1985 1986 1987 1988 1989 1990 1991 1992 1993 Operating Hours 1205 1208 1172 1352 1170 1136 1094 1158 1180 (critical)

Megawatt 946 1042 993 1001 1025 1013 928 1002 1026 Q)

Hours Megawatt 39.4 43.4 41.4 41.7 42.7 42.2 38.6 41.8 42.7 Days Grams 235U 49.5 54.4 51.9 52.3 53.6 53.0 48.5 52.4 53.6 Used Hours at Full Power 904 1024 980 987 1021 1009 909 992 1000 (1MW)

Numbers of Fuel Elements 0 0 0 -2 0 -1,+1 -1 0 0 Added or Removed.-)

I I I I I I t I t I I I I I

F"- F - F- [-r- F F- F'. I-- [ .... r -- r--- r F.. - -- I---

Table IV.A.1 (Continued)

, OSTR Operating Statistics (Using the FLIP Fuel Core)

Operational July 1, 1993 July 1, 1994 July 1, 1995 July 1, 1996; July 1, 1997 July 1,1998 July 1, 1999 July 1, 2000 July 1, 2001 Data for Through -. , Through Through Through" Through Through Through Through Through FLIP Core June 30, 1994 June 30, 1995 June30, 1996 June30, 1997 June30, 1998 Juine30, 1999 June30,2000 June30,2001 June 30,

_ _2002 Operating Hours 1248 1262 1226 1124 1029 1241 949 983 1029 (critical ,

Megawatt 1122 1117 1105 985 927 1115 852 896 917 Hours Megawatt 46.7 46.6 46.0 41.0 38.6 46.5 35.5 37.3 38.2 Days __

Grams ... U ..

Urams . ,U58.6 58.4 57.8 51.5 48.5 58.3 44.6 46.8 47.7 0

Hours at Full Power 1109 1110 1101 980 921 1109 843 890 912 (IMW)

Numbers of, Fuel Elements 0 0 -10) 1, +(7) 0 -10) 0 0 _1(5)

Added or Removed (-) _

,Number of .

Irradiation 303.. .268 ....

3 24' 282 249 231ý 234 210 239' Requests V,- .. ., .,

Ine reactor,was snutdown on .July 2o, 1 tio for one montn In order to completely refuel the reactor with a new I'Lt'fuel core.

(2)' No fuel elements were added, but one fueled follower control rod was replaced.'

(3)' Two fuel elements were removed due to cladding defohnation. I (4)" 'One fuel elemfient inioved due to claddingdeformation and ohe 6-ew fuel element added.

(5) One fuel element removed for core excess adjustment.... ....

(6) No fuel elements were added, but the instrumented fuel element wais replaced.

(7) One fuel element removed due to cladding deformation and one used fuel element added.

Table IV.A.2 OSTR Onerating Statistics with the Orig nal (20% Enriched) Standard TRIGA Fuel Core Operational TOTAL:

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 March 67 for 20% Through Through Through Through Through Through Through Through Through Through Through Enriched Jun30,68 Jun30,69 Mar3l,70 Mar31,71 Mar3l,72 Mar31,73 Mar3l,74 Mar31,75 Mar3l,76 Ju126,76 July76 Core Operating Hours 904 610 567 855 598 954 705 563 794 353 6903 (critical)

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 Grams ... 6.1 5.4 7.2 11.7 10.2 26.0 17.6 16.8 21.4 10.7 133.0 Used 1

Hours at Full Power 429 369 58 --- --- --- 856

_ 50kW__) _ _ _ _ __ _._ _ _ _ _ _ _ _

t"J Hours at Full Power --- --- 20 23 100 401 200 291 460 205 1700 (1 M W) .......

Number of 70 Fuel Elements 132 2 0 94 Added to Core (Initial)

Number of Irradiation 429 433 391 528 347 550 452 396 357 217 4100 Requests _ _1 299 102 98 109 1_1 _

Number of 202 236 249 183 43 39 1560 Pulses I I I I I I I L (1) Reactnr went critzicl on March R 1967 (70 clement core- 25fkW) Note: This neriod lenoth is 133 vears as initial criticalitv occurred in March of 1967.

(2) Reactor shutdown August 22, 1969 for one month for upgrading to IMW (did not upgrade cooling system). Note: This period length is only 0.75 years as there was a change in the reporting period from July-June to April-March.

(3) Reactor shutdown June 1, 1971 for one month for cooling system upgrading.

(4) Reactor shutdown July 26, 1976 for one month for refueling reactor with a new full FLIP fuel core. Note: This period length is 0.33 years.

I I f i I I L ( I I I I

Table IV.A.3 Present OSTR Operating Statistics Cumulative Values Operational Data Annual Values for for 2021FLIP Core FLIP Core (2000/2001)

MWH of energy produced - 917 23,661 MWD of energy produced . 38.2 . 985.9 Grams 23 sU used - 47.7 1,237 Number of fuel elements added to (+) -

or removed from (-) the core -1 79 + 3 FFCR(')

Number of pulses 11 1,367 Hours reactor critical 1029 . . .28,805 Hours at full power (1 MW) 912 23,243 Number of startup and shutdown checks 250 6567 Number of irradiation requests processed(2 ) 239 8,553 Number of samples irradiated 6660 109,985 (1) Fuel Follower Control Rod. These numbers represent the core loading at the end of this reporting period.

(2) Each irradiation request could authorize from 0 to 146 samples. The number of samples per irradiation request averaged 17.6 during the current reporting period.

ReactorIV- 13

Table IV.A.4 OSTR Use Time in Terms of Specific Use Categories Cumulative Values OSTR Use Category aValues r(hours) (hours)Core for FLIP Teaching (departmental and others)(') 42 13,148 OSU research(2 ) 178 8,867 Off-campus research(2 ) 1,711 17,369 3 234(3)

Forensic services Reactor preclude time 1,013 20,655 Facility time04 ) 5 7,098 TOTAL REACTOR USE TIME 67,371 (1) See Tables III.A.2 and III.D. 1 for teaching statistics.

(2) See Table III.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 1981-1982 report.

(4) The time OSTR spent operating to meet NRC facility license requirements.

(5) Total reactor use time includes all multiple use hours added separately.

ReactorIV - 14

Table IV.A.5 OSTR Multiple Use Time(')

lAValues Cumulative Values Number of Users afor (hours) (hours)Core FLIP Tv-6 301- 4,454 176 -1,463 Three 78 559 Four 18 133 Five 13 58.5 Six' Seven 1 12 587(2) 6,679.5(3)

TOTAL MULTIPLE USE TIME (1) Multiple use time is that time when two or more irradiation requests are being concurrently fulfilled by operation of the reactor. I .

(2) This represents 57% of the total hours the reactor was critical during this reporting period.

(3) This represents 23.2% of the total hours the reactor was critical since startup with FLIP fuel in August of 1976.

',ReactorIV- 15

I Table IV.B.1 Use of OSTR Reactor Experimentso')

Reactor NRC Experiment License Number 2) Research Teaching Forensic Requirement TOTAL A-1 3 24 0 2 29 B-3 141 31 3 0 172 B-31 9 0 0 0 9 TOTAL 153 55 0 2 210 (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 corresponding title:

A-i Normal TRIGA Operation B-3 Irradiation of Materials in the Standard OSTR Irradiation Facilities B-31 TRIGA Flux Mapping Reactor IV- 16

Table IV.C.1 Unplanned Reactor Shutdowns and Scrams Type of Event" Number of Occurrences Cause of Event Safety Power Operator error. Automatic scram on'higli Safety Power Scamo Channel due to Lazy Susan samples shielding effect on Scram monitored power channel during power increase.

Operator error. IAutomatic scram on high Percent Percent Power Power Channel'due to Lazy Susan samples shielding Scrai 1 effect on monitored piower channel during power increase.

AC spike noise on period channel." Power at <0.1 watt.

Noise occurs when moving rods. Twice occurred Period Scram 3 duringlicensee NRC exam. Scrams received while withdrawing shim rod to 15 watts: Determined to be caused by instrument noise at low power.

High Voltage 1 HV1 annunciated scram occurred at the same time left Scram 1 hand drawer wa's touched by Reactor Supervisor.

Staiic discharge to LHD noted at the same time.

Manual Reactor Seismic activity felt in Control Room. Received later Scram information confiriing earthquake occurrence.

Reactor shutdown prompted by loss of off-site power.

Manual Reactor 1 Cause of loss later determined to mylar balloons hitting a Scram '- substation.

"-Highstack gas alarm required shutdown.. High level Manual Reactor 1determined to be caused by change out of reactor top "Shutdown Lazy Susan filter, increasing system flow and causing slug" effect throutgh detector.

ManuaR o "Manual shutdown prompted by loss of#1 Cooling Manual Reactor 1 Tower Fan. Fuse in disconnect panel blew due to high Shutdown resistance connection.

Reactor IV - 17

Figure IV.E.1 Monthly Surveillance and Maintenance (Sample Form)

OSTROPI13 SURVEILLANCE & MAINTENANCE FOR THE MONTH OF SURVEILLANCE & MAINTENANCE TO BE TARGET DATENOTTOBE DATE REMAPKS, &

PERFORMED LIMITS AS FOUND DATE EXCEEDED" COMPLETED INITIALS I FUNCTIONAL CHECK OF REACTOR WATER MAXIMUM MOVEMENT t._..c LEVEL ALARMS &GREEN LIGHT ALARM A3 INCHES A 2 MEASUREMENT OF THE REACTOR PRIMARY MIN: 5 WATER pH MAX: 8.5 3 MEASUREMENT OF THE BULK SHIELD TANK MIN: 5 WATER pH MAX: 8.5 4 EMERGENCY POWER SYSTEM BATrERY LIQUID: -I!DN CHECKS S.O.: >1.250 FUNCTIONAL CHECK 00 GENERATOR 5.O.: >1.250 VOLTS k 12.6V DC 00 5 EVACUATION HORN & P.A. EMERGENCY LIQUID: FULL SYSTEM BATTERY CHECKS S.O.5>1.250 VOLTS i 12.6V DC CORR., NONE _

6 INSPECTION OF THE BRUSHES ON THE PNEUMATIC CHANGE WHEN TRANSFER SYSTEM BLOWER MOTOR Wj' LEFT 7 REVIEW REACTOR SUPERVISOR'S LOG CURR1NT_

8 CHANGE LAZY SUSAN FILTER FILTERCHANOED 9 LUBRICATE THE TRIOA TUBE LOADING TOOL USE OIL GUN NEED (REEL) OIL?

10 REACTOR TOP CAM OIL LEVEL CHECK OSTROP 13.10 NEED OIL?

II PROPANE TANK LIQUID LEVEL CHECK (%FULL) >30%

,12 BULK WATER TEMPERATURE ALARM CHECK FUNCTIONAL 13 PRIMARY PUMP BEARINGS OIL LEVEL CHECK OSTROP 13.13 NEED

____________ OIL? _____

• Ltcns¢ Rcqulremcnt Dare not to be exceeded Isonly applicable to marked (*)Items. It Isequal to the time completed list month plus Ilxcwks. Rev. 3198 I ( I[ t , [ [ I I I I I I I

I . ' ..- I -. . . I, . .. I- - I' ' " I- -f- '-V [-- - 1'7 - - I ' -- 1 1. [ -1 r- - f ---

Figure IV.E.2 Quarterly Surveillance and Maintenance (Sample Form)

OSTROP 14 9URVEILLANCE & MAJ=t*NANCE FOR TM Q2UARTER OF _ _ 19 QUARTER I QUARTERLY II II 02 i LEVEL~IMEASUREMENTS I QUDARTERLY 2' IN WATER

- I 4 -I . -. _________

0F THE SOLENOID VALVES INTHEE TRANSFER SYSTEM I F NCTIONAL ____ ____

TRANSFER SYSTEM INSEPTION TIME

• Pit *'*'/'N"s*kt f* 0 CHECK a 6 ROTATTNO RACK CHECK FOR UNKNOWN SAMPLES RACK SHOULD 08 EMPTY 7 FUNCTIONAL CHECK OF EMEROENCY LIOHTS (SEE CHECKSHIEDT FUNCTIONAL

- WATER MONITOR ALARM CHECK . . FUNCTIONAL 9 STACK MONITOR CHECKS (OIL DRIVE MOTOMS, HLV.. MOTORS OIL.ED READW.OS) , PARTI IISOV VOLTS 9It OAS: 00V ASO VOLTS 10 74tOT BEING USED) ___________

11 ARM SYSTEM ALARM CHECS.

CHAN

. - . 13 14 1-2. 6 7 9 1'910o11 1x21314

- i i FUNCTONAL

-... P1 -1 Phyiu!si Smcurity Plan Requretment LIoen" RequIrtment M

06 Dote not to W exceeded It only ippllemabl to mnued (1)Items. It IsequAI to thie dite completed I1 quger plus (butrmonn .

Figure IV.E.2 (Continued)

Quarterly Surveillance and Maintenance (Sample Form)

SURVELA1NCE& WMmTNANCE FOR TIM QUARTER OF / /_ 19 osTRop 14 (CONT7NUD) t2 5RA~RE55 IqAvM A 14hour $Ib) QPERATINO EXERCISE 13 CHECK MTER TAPS SPEED ON STACK MONIOR 11$1R A 0.2 _____ ____

14 JINCORIORtATI 50.59 A ROCAS iNTO DOCUMENTATIO N QUARTIIRLY_____

13 (CNOTBEINO USED)______

16 JFUNCTIONAI. CHECK OF OVACUATION ALARMS ALL FUNCTIONAL __________ __ ____

17 I(NOT BEINO USED)__ _________

It STACK MONITOR ALARM CIRCUIT CHECKS ALARM ON CONTACT ______ __________

19 JALARM TESTING OP VITAL ARE DOUBLE DOOR$ FUNCTIONAL ______________ ____

"Ucu les tft FIfrnt Vr 4

to th~ditl tOnv *Cd Ilut quI~tlr Plut toufMr,otls.

(0)ItuMs It IS0.10.1

$4,Det' no r i *xcedVd Isonly OPPltcable to ni&Aied I Il I I I I I. V I I I' I I' I. I

F --

Figure IV.E.3 Semi-Annual Surveillance and Maintenance (Sample Form)

OSTROP.1B SEMI-ANNUAL SURVEILLANCE AND MAINTENANCE FOR S,__ -,, ..-. DATE NOT TO DATE REMARKS &

LIMITS AS FOUND TARGET DATE BE EXCEEDED

• COMPLETED INITIALS SURVEILLANCE & MAINTENANCE TO BE PERFORMED 6 FUNCTIONAL NO"WIThOEIW *1 .....

CHECKS OF a)NEUTRON SOURCE COUNT RATE INTERLOCK 5 CPO _.2 REACTOR NO PULSE b ,_..

INTERLOCKS b) TRANSIENT ROD AIR INTERLOCK c) PULSE PROHIBIT ABOVE I kW ki kW a , _,

I only d .....

d) TWO ROD WITHDRAWAL PROHIBIT a) PULSE MODE ROD MOVEMENT INTERLOCK NOMOVMtNT? 0 .

If MAXIMUM PUMLt M ACTMTY IN$(OTION UMIT  % $2.50 If I) PULSE INTERLOCK ON RANGE SWITCH NO PULSE _

• 2 SAFETY CIRCUIT, PERIOD SCRAM - 3.t3 too TEST 13 CONTROL .. .. TRANS SAFE SHIM REG ROD WITH. S "' . e DRAWAL. SCRAM ,a_ I) e INSERTION & bi WITHDRAWAL 00 sea b SCRAM TIMES! , c) INSERTION "* $0t0 a "4 PULSE COMPARISON (PREVIOUS PULSE): I_________

PULSE I - -20%* *"'"s

_________MW CHANGE _ _ _ _

, " -0.* .- * .. C - ..

05 REACTOR BAY VENTILATION SYSTEM SHUTDOWN TEST AMCtl cett 4m7,toom 06 CALIBRATION OF THE FUEL ELEMENT TEMPERATURE CHANNEL Al2C AtMILI AL.30 "7 MATERIALS BALANCE REPORT/FUEL MANAGEMENT . .

tFiORTos EVI uON ONE

-m ocTostRis OCTOIfR0o 6e CLEANING & LUBRICATION OF TRANSIENT ROD CARRIER INTERNAL 34MN.1 i CTANtO WHOM. oI.toID BARREL 69 LUBRICATION OF BALL-NUT DRIVE ON TRANSIENT ROD CARRIER 34*1 or OUtS0I.

, otywotf0 to LUBRICATION OF THE ROTATING RACK BEARINGS 10 WOIL OILED 11 CONSOLE CHECK UST (OSTROP 15.11) OSIIOPIIM 1 12 CONSTANT AIR MONITOR RECORDER MAINTENANCE 19 S

LIcenle Retzremer ,R Ra v. 11192 Date not to be exceeded isonly opplIeable to merked (1*Items, ItIt equal to the dote lest tIme plus 7% months,

Figure IV.E.3 (Continued)

Semi-Annual Surveillance and Maintenance (Sample Form)

OSTROP IS fcontinwed) EMI.ANNUALB URVEILLANCE AND MAINTENANCE FOR DATE NOT TO DATE REMARKS&

SURVEILLANCE & MAINTENANCE TO BE PERFORMED LIMITS AS FOUND TAROET OATS BE EXCEEDED

• COMPLETED INITIALS 13 Delated 14 BTANDARO CONTROL ROO MOTOR CHECKS OILED 168 Dilated I 18 ION CHAMBER RESISTANCE As SAFETY CHANNEL NONE MEASUREMENTS WITH MEQOAR (Info Only)

INDUCED VOLTAaE 0. %POWER CHANNEL NONE

._ (Info Only) 17 FISSION CHAMBER RESISTANCE @ IOOV. I m_._..AMP8 NONE CALCULATION 0 900 V. I- ___. AMPS (Info Only) 900V Atl- A*__AMPS A-lf 18 FUNCTIONAL CHECK OF HOLDUP TANK WATER LEVEL ALARMS OSTROP I1I.12IO0__'

_UOHT_=

6 Uicense Rsequrmente.

Cot not to be exceeded Is only appfloeble to marked 101 Dae Items. It Is equil to the date last tIme plus 7%1 months. Rev. 11/94 I 1,1 I I I I I I I I. I I I I I I

i

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Co K

1I32 -I t,.

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Ca I E I

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Reactor IV - 23

Figure IV.E.4 (Continued)

Annual Surveillance and Maintenance (Sample Form)

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Part V Protection CA-Ul RADIOACTIVE MATERIALS',

Part V PROTECTION A. Introduction This section ofthereport deals with the radiation protection program at the OSU Radiation Center.

The purpose of this program is to ensure the safe use ofradiation and radioactive material in the Center's teaching,'research, and service activities, and in a similar manner to ensure the fulfillment of all regulatory requirements of the state ofOregon, the U.S. Nucledr Regulatory Commission, and other regulatoryagencies. The comprehensive nature of the program is shown in Table V.A. 1, which lists the program's maj or radiation piotection requirements and the performance frequency for each item.

The radiation protection program is implemented by a staff consisting ofa Senior Health Physicist, two Health Physicists, and several part-time Health Physics Monitors (see Part II.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 Office ofEnergy 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 I.E for quick reference.

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 environment and all exposures to radiation and radioactive materials at levels which are consistently "as low as reasonably achievable" (ALARA).

B. Environmental Releases The annual reporting requirements in the OSTR Technical Specifications state that the licensee (OSU) shall include "a summary ofthe nature and amount ofradioactive effluents released or discharged to the environs beyond the effective control ofthe licensee, as measured at, or prior to, the point of such release or discharge." The liquid and gaseous effluents released, and the solid waste generated and transferred are discussed brieflybelow. Data regarding these effluents are also summarized in detail in the designated tables.

Protection V- 1

1. Liquid Effluents Released

a. Liquid Effluents Released Oregon State University has implemented a policy to reduce the volume of radioactive liquid effluents to an absolute minimum. For example, water used during the ion exchanger resin change is now recycled as reactor makeup water.

Waste water from Radiation Center laboratories and the OSTR is collected at a holdup tank prior to release to the sanitary sewer. Whenever possible, liquid effluent is analyzed for radioactivity content at the time it is released to the collection point. However, liquids are always analyzed for radioactivity before the holdup tank is discharged into the unrestricted area (the sanitary sewer system).

For this reporting period, the Radiation Center and reactor made two liquid effluent releases to the sanitary sewer. All Radiation Center and reactor facility liquid effluent data pertaining to these releases are contained in Table V.B. .a.

b. Liquid Waste Generated and Transferred Liquid waste generated from glassware and laboratory experiments is transferred by the campus Radiation Safety Office to its waste processing facility. The annual summary of liquid waste generated and transferred is contained in Table V.B. 1.b.

2. Airborne Effluents Released Airborne effluents are discussed in terms of the gaseous component and the particulate component.

a. Gaseous Effluents Gaseous effluents from the reactor facility are monitored by the reactor stack effluent monitor. Monitoring is continuous, i.e., priorto, during, and after reactor operations. It is normal for the reactor facility stack effluent monitor to begin operation as one of the first systems in the morning and to cease operation as one of the last systems at the end of the day. All gaseous effluent data for this reporting period are summarized in Table V.B.2.

Protection V - 2

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 confrrmed its origin as naturally-occurring radon daughter products, within a range of approximately 3 x 10-1' ptCi/ml to 1x 10. I-Ci/ml. This particulate radioactivity is predominantly2 4 Pb and 214Bi, which is not associated with reactor operations.

There was no release of particulate effluents with a half life greater than eight 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 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 facility and the Radiation Center. Solid radioactive waste is routinely transferred to Radiation Safety.

Until this'waste is disposed of by Radiation Safety, it is held along with other campus radioactive waste on the University's state of Oregon radioactive materials license.

Solid radioactive waste is disposed ofby Radiation Safetyby transfer to the University's radioactive waste disposal vendor, Thomas Gray Associates, Inc., for burial at its installation located near Richland, Washington.

C. Personnel Doses The OSTR annual reporting requirements specify that the licensee shall present a summary of the radiation exposurý received by facilityipersonnel and visitors. Foi the purposes of this report, the summary includes ail Radiation Ceiiter t ersonnel whomiayhave received exposure to radiation.

These personnel have been categoriied into sixgroups" facility operating personnel; key facility research person-nel, facilities services 'Maintenancepersonnel; students in laboratory classes, police and security personnel, and visitors.

Facility operating personnel include the reactor operations and health physics staff. The dosimeters used to monitor these individuals include quarterly TLD badges, quarterly track-etch/albedo neutron dosimeters, monthly TLD (finger) extremity dosimeters, and pocket ion chambers.

Key facility research personnel consist of Radiation Center staff, faculty, and graduate students who perform research using the reactor, reactor-activated materials, or using other research facilities present at the Center. The individual dosimetry requirements for these personnel will vary Protection V- 3

with the type ofresearch being conducted, but will generally include a quarterlyTLD film badge and TLD (finger) extremity dosimeters. Ifthe possibility of neutron exposure exists, researchers are also monitored with a track-etch/albedo neutron dosimeter.

Facilities Services maintenance personnel are normally issued a gamma sensitive electronic dosimeter as their basic monitoring device. A few Facilities Services personnel who routinely perform maintenance on mechanical or refrigeration equipment are issued a quarterly Xp(y) TLD badge and other dosimeters as appropriate for the work being performed.

Students attending laboratory classes are issued quarterly XP(G) TLD 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 electronic dosimeter. These results are not included with the laboratory class students.

OSU police and security personnel are issued a quarterly XP (y) TLD badge to be used during their patrols of the Radiation Center and reactor facility.

Visitors, depending on the locations visited, maybe issued a gamma sensitive electronic dosimeters.

OSU Radiation Centerpolicy does not normally allow people in the visitor category to become actively involved in the use or handling of radioactive materials.

An annual summary ofthe radiation doses received by each of the above six groups is shown in Table V.C. 1. There were no personnel radiation exposures in excess of the limits in 10 CFR 20 or state of Oregon regulations during the reporting period.

D. Facility Survey Data The OSTR Technical Specifications require an annual summary of the radiation levels and levels of contamination observed during routine surveys performed at the facility. 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.

Protection V - 4

1. Area Radiation Dosimeters 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 or TLD pack. In addition, for key locations in the reactor facility and for certain Radiation Center laboratories a CR-3 9 plastic track-etch neutron detector has also been included in the monitoring package.

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 show the room number or location.

2. Routine Radiation and Contamination Surveys The Center's program for routine radiation and contamination surveys consists ofdaily, weekly, and monthly measurements throughout the TRIGA reactor facility and Radiation Center. The frequency of these surveys is based on the nature of the radiation work being carried out at a particular location or on other factors which indicate that surveillance over a specific area'at a defined frequency is desirable.

The primary purpose ofthe routine radiation and contamination survey program is 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 ori-the-spot personal observations (along with recorded data), 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 objectives, is to gather and document information which will help to ensure that all phases of the operational and radiation protection programs are meeting the goal of keeping radiation doses to personnel and releases of radioactivity to the environment "as low as reasonably achievable" (ALARA).

The annual summary of radiation and contamination levels measured during routine facility surveys'for the applicable re' orfing period is given in Table V.D.3.

Protection V- 5

E. Environmental Survey Data The annual reporting requirements of the OSTR Technical Specifications include "an annual summary of environmental surveys performed outside the facility."

1. Gamma Radiation Monitoring

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 stations. These stations consist ofa polyethylene bottle placed inside a PVC tube attached to the reactor building perimeter fence at a height of four feet.

Each fence environmental station is equipped with an OSU supplied and processed TLD area monitor (normally three Harshaw 7LiF TLD-700 chips per 7Li monitor in a plastic "LEGO" mount). These monitors are exchanged and processed quarterly. The total number of TLD samples for the reporting period was 108 (9 stations x 3 chips per station per quarter x 4 quarters per year). A summary of this TLD data is shown in Table V.E. 1.

During this reporting period, each fence environmental station utilized an LIF TLD monitoring packet supplied and processed by ICN Worldwide Dosimetry Service (ICN), Costa Mesa, California. Each ICN packet contained three LIF TLDs and was exchanged quarterly for a total of 108 samples during the reporting period (9 stations x 3TLDs per station x four quarters). The total number of ICN TLD samples for the reporting period was 90. A summary of the ICN TLD data is also shown in Table V.E. 1.

Monthly measurements of the direct gamma dose rate ([trem h7') were also made at each fence monitoring station. These measurements were made with a Bicron micro-rem per hour survey meter containing a 1" x 1" NaI detector.

A total of 108 ].trem h` measurements were taken (9 stations per month x 12 months per year). The total calculated dose equivalent was determined by averaging the 12 separate jtrem h1 measurements and multiplying this average by 8760 hours0.101 days <br />2.433 hours <br />0.0145 weeks <br />0.00333 months <br /> per year. A summary of this data is shown in Table V.E. 1.

From Table V.E. l it is 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. 1, 2).

Protection V - 6

or the OSU Radiation Center, and also helps indicate the general trend ofthe radioactivity concentration in each of the various substances sampled. See Figure V.E. 1 for the locations of the sampling stations for grass (G), soil (S), water (W) and rainwater (RW) samples. Most locations are within a 1000 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 indicated in Figure V.E.l.

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 ofsamples possible during the reporting period is 88 (16 soil samples, 16 water samples, and 56 vegetation samples).

-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 ofonly the counting system background from the gross beta counting rate, followed by application of an appropriate counting system efficiency.

-Theannual 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 ofLLD 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 of radioactive material (in terms of pCi per unit volume or unit mass) in a representative

• sample,-which has a 95% probability of being detected.

Identification of specific radionuclides is not routinely carried out as part ofthis monitoring program, but would be conducted ifunusual radioactivity levels above natural background were detected. However, from Table V.E.3 it can be seen that the levels ofradioactivity detected were consistent with naturally occurring radioactivity and comparable to values reported in previous years.

F. Radioactive Material Shipments A summary of the radioactive material shipments originating from the TRIGA reactor facility, NRC license R- 106, is shown in Table V.F. 1. A similar summary for shipments originating from the "Radiationi Center's state of Oregon radioactive materials license ORE 90005 is shown in Table V.F.2. A summary of radioactive material shipments exported under Nuclear Regulatory Commission general license 10CFR 110.23 is shown in Table V.F.3.

Protection V- 8

b. Off-site Monitoring The off-site gamma'environmental radiation monitoring program consists oftwenty monitoring stations surrounding the Radiation Center (see Figure V.E.2) and six stations located within a 5 mile radius of the Radiation Center.

Each off-site radiation monitoring station is equipped with an OSU-supplied and processed TLD monitor. Each monitor consists of three Harshaw 7LiF TLD-700 chips in a plastic "LEGO" mount. The mount is placed in a polyethylene bottle inside a PVC tube which is attached to the station's post about four feet above the ground (MRCTE 21 and MRCTE 22 are mounted on the roof of the EPA Laboratory and National Forage Seed Laboratory, respectively). These monitors are exchanged and processed quarterly, and the total number of TLD samples during the current one-year reporting period was 240 (20 stations x 3 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. The total number of ICN TLD samples for the reporting period was 144 (12 station x 3 TLDs per station x 4 quarters). The total number ofICN TLD samples for the reporting period was 128. A summaryof ICN TLD data for the off-site monitoring stations is also given in Table V.E.2.

In a manner similar to that described for the on-site fence stations, monthly measurements of the direct gamma exposure rate in microrem per hour ([.rem h')

are made at each of the twenty off-site radiation monitoring stations. As noted before, these measurements are made with a Bicron micro-rem per hour survey meter containing a 1"x 1"Nal detector. A total of240 .tremh-' measurements were made during the reporting period (21 stations per month x 12 months per year). The total dose equivalent for each station was determined by averaging the 12 separate I.Irem h" measurements and multiplying this average by 8760 hours0.101 days <br />2.433 hours <br />0.0145 weeks <br />0.00333 months <br /> per year. A summary of these data is given in Table V.E.2.

After a review of the data in Table V.E.2, it is concluded that, like the 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).

2. Soil, Water, and Vegetation Surveys The soil, water, and vegetation monitoring program consists of the collection and analysis of a limited number of samples in each category on a quarterly basis. The program monitors highly unlikely radioactive material releases from either the TRIGA reactor facility Protection V- 7

G. References

1. U. S. Environmental Protection Agency, "Estimates ofIonizing Radiation Doses in the United States, 1960-2000," ORP/CSD 72-1, Office ofRadiation Programs, Rockville, Maryland (1972).

2. U. S. Environmental Protection Agency, "Radiological Quality ofthe Environment in the United States, 1977," EPA 520/1-77-009, Office ofRadiation Programs; Washington, D.C. 20460 (1977).'

Protection V - 9

Table V.A.1 Radiation Protection Program Requirements and Frequencies FREQUENCY RADIATION PROTECTION REQUIREMENT Daily/Weekly/Monthly Perform routine area radiation/contamination monitoring.

Perform routine response checks of radiation monitoring instruments.

Monitor radiation levels (I.Lrem h') at the environmental monitoring stations.

Collect and analyze TRIGA primary, secondary, and make-up water.

Exchange personnel dosimeters and inside area monitoring dosimeters, and review exposure Monthly reports.

Inspect laboratories.

Check emergency safety equipment.

Perform neutron generator contamination survey.

Calculate previous month's gaseous effluent discharge.

Process and record solid waste and liquid effluent discharges.

Prepare and record radioactive material shipments.

Survey and record incoming radioactive materials receipts.

As Required Perform and record special radiation surveys.

Perform thyroid and urinalysis bioassays.

Conduct orientations and training.

Issue radiation work permits and provide health physics coverage for maintenance operations Prepare, exchange and process environmental TLD packs Collect and process environmental soil, water, and vegetation samples.

Conduct orientations for classes using radioactive materials.

Collect and analyze sample from reactor stack effluent line.

Exchange personnel dosimeters and inside area monitoring dosimeters, and review exposure reports.

Leak test and inventory sealed sources.

Semi-Annual Conduct floor survey of corridors and reactor bay.

Inventory and inspect Radiation Center equipment located at Good Samaritan Hospital.

Calibrate portable radiation monitoring instruments and personnel pocket ion chambers.

Calibrate reactor stack effluent monitor, continuous air monitors, remote area radiation monitors, water monitor, and air samplers.

Measure face air velocity in laboratory hoods and exchange dust-stop filters and HEPA filters Annual as necessary.

Inventory and inspect Radiation Center emergency equipment.

Conduct facility radiation survey of the 'Co irradiators.

Conduct personnel dosimeter training.

Perform contamination smear survey of Radiation Center ventilation stacks Update decommissioning logbook.

Protection V- 10

r* r r- r V- ... . . r-Table V.B.1.a Monthly Summary of Liquid Effluent Releases to the Sanitary Sewer°'2)

(OSTR Contribution Shown in () and Bold Print) p r T r Specific Activity For Percent of Total Quantity Average Total Volume Each Detectable Applicable Monthly Detectable of Each Concentration of of Liquid Total Quantity Radionuclide in the Average of Radionuclides Detectable Released Effluent Date of Discharge Waste, Where the Concentration for Released Radioactivity in Radionuclide Radioactive Release Released (Month and Year) Released the Waste Released in Material at the Including Concentration Was Radioactive (Curies) the Waste Point of Release Diluent (4)

>1 x 10.i [LCi/cm 3 (Curies) (pCi ml"')

Material (gal)

(l4Ci m"1) 2451 January 2002... . ... 0 .... 0

.1857 May 2002' j, ' 1 0 --- 0 Annual Total for "*0 0, "0 4308 0 Radiation Ceihter OSTR N/A N/A N/A N/A N/A Contribution to Above. _________ j _________ I (1) OSU has implemented a policy to reduce to the absolute minimum radioactive wastes disposed to the sanitary sewer. There were no liquid effluent reieases during months not listed. ,

(2) The OSU operational policy is to subtract, only detector background

, from the water analysis data and not background radioactivity in'the Corvallis city water.

(3) Based on values listed in 10 CFR 20, Appendix B to 20.1001 - 20.2401, Table 3, which are applicable to sewer disp6sal.

(4) The total volume of liquid effluent plus diluent does not take into consideration the additional mixing with the over 250,000 gallons per year of liquids and sewage normally discharged by the Radiation Center complex into the same sanitary sewer system.

(5) Less than the lower limit of detection at the 95% confidence level.

Table V.B.1.b Annual Summary of Liquid Waste Generated and Transferred Dates of Waste Dates of Volume of Liquid Detectable Total Quantity of Pickup for Shipment Origin of Waste Radionuclides in Radioactivity in the Transfer to the from Oregon Liquid Waste Packaged() the Waste Waste (Curies) Waste State (gallons) Processing University Facility TRIGA Reactor None Facility 1

Radiation Center 3 H, 6 5Zn,' 3 1i, 32 p, Laboatories 30 5 Fe, 86Rb 13Rb 5.52 x 10-3 8/21/01, 4/24/02 6/21/02, 2/22/02 Laboratories 59Fe, TOTAL 30 3 H ' 65 5 9Zn, 13 1 I 3 5.52 x 12p Fe, 86 Rb 5.52_ __10._

t\J (1) TRIGA and Radiation Center liquid waste is picked up by the Radiation Safety Office for transfer to its waste processing facility for final packaging.

(2) The short-lived waste was held by the Radiation Safety Office for decay.

I I I I I I I I 1 I I I I

Table V.B.2 Monthly Summary of Gaseous Effluent Releases0M Estimated Average Percent of the Total Estimated Total Estimated Atmospheric Diluted Applicable MPC for Date of Radioactivity Quantity of Concentration of Diluted Concentration Discharge (Month and Released Argon-41 Argon-41 at Point of of Argon-41 at Point of Released(2) Release (Reactor Release (Reactor Year) (Curies) (Curies) Stack) - Stack)

(.-Ci/ml") (%)

July 01 0.32 0.32 2.57E-08 0.64 August 01 0.24 0.24 1.90E-08 0.47 September 01 0.10 0.10 8.52E-09 0.21 October 01 0.24 0.24 1.92E-08 0.48 November 01 0.22 0.22- 1.77E-08 0.44 December 01 0.11 0.11 8.46E-09 0.21 January 02 0.26 0.26 2.06E-08 0.52 February 02 0.16 0.16 1.37E-08 0.34 March 02 0.34 0.34 2.68E-08 0.67 April 02 0.23 0.23 1.87E-08 0.47 May 02 0.23 0.23 2.09E-08 0.52 June 02 0.27 0.27 2.19E-08 0.55 ANNUAL VALUE 2.71 2.71 1.84E-08 0.46 (1) Airborne effluents from the OSTR contained no detectable particulate radioactivity resulting from reactor operations, and there were no releases of any radioisotopes in airborne effluents in concentrations greater than 20% of the applicable effluent concentration. (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.

Protection V- 13

Table V.B.3 Annual Summary of Solid Waste Generated and Transferred "Datesof Waste Volume of - Total Quantity Pickup for Dates of Origin of Solid Waste aDetectable of Radioactivity Transfer to the Shipment from Solid Waste Packaged) Radionnuclides in Solid Waste OSU Waste Oregon State (Cubic Feet) in the Waste (Curies) Processing University(')

Facility 47 8 TRIGA 46Sc, Sc, 5 Co, 54 9 Reactor 17.5(3) 6OCo, Mn, ' Rb, 5.82 x 10. 8/21/01, 11/28/01, 2/22/02,4/24/02, 85 Facility Se 4/24/02 7/17/02 Radiation 3 H, 14C, 46Sc, 47 Center Sc, 22Na, 6CoZn, 5.2 x 10.2 8/21/01, 11/28/01, 2/22/02,4/24/02, Center 27 238 U, 59 Fe, 86 Rb, 4/24/02 7/17/02 Laboratories I_9OSr, 31 7 1 1, 18 Cs I I I TOTAL 44.5 See Above 5.2 x 10-2 1 --- _I___

(1) TRIGA and Radiatior Center laboratory waste is picked up by Radiation Safety for transfer to its waste processing facility for final packaging.

(2) Solid radioactive waste is shipped to Thomas Gray Associates, Inc.

(3) Includes 4 ft3 of dewatered resin beads.

Protection V- 14

Table V.C.1 Annual Summary of Personnel Radiation Doses Received "AverageAnnual Greatest Individual Total Person-mrem Dose(n) Dose") For the Group"t)

Whole Whole Whole Personnel Group Body Extremities Body Extremities Body Extremities (mrem) (mrem) (mrem) .(mrem) (mrem) (mrem)

Facility Operating 8 17 63 549 246 968 Personnel Key Facility Research 0 <1 0 24 0 70

" Personnel Facilities Services Maintenance Personnel Laboratory Class <1 <1 23 107 86 367 Students Campus Police and <1 N/A 12 N/A 23 N/A Security Per~sonnel -- I_ IIII Visitors <1 N/A 8 N/A 81, N/A -

(1) "N/A" indicates that there was no extremity monitoring conducted or required for the group.

Protection V- 15

Table V.D.1 Total Dose Equivalent Recorded'on Area Dosimeters Located Within the TRIGA Reactor Facility Total Recorded TRIGA Reactor Dose Equivalente)(2)

I.D. Facility Location (See Figure V.D.1) x(re) Neutron (mrem) (torero)

MRCTNE D104: North Badge East Wall 101 ND MRCTSE D104: South Badge East Wall 60 ND MRCTSW D104: South Badge West Wall 259 ND MRCTNW D104: North Badge West Wall 50 ND MRCTWN D104: West Badge North Wall 60 ND MRCTEN D104: East Badge North Wall 266 ND MRCTES D104: East Badge South Wall 538 ND MRCTWS D104: West Badge South Wall 253 ND MRCTTOP D104: Reactor Top Badge 276 ND MRCTHXS D104A: South Badge HX Room 282 ND MRCTHXW D104A: West Badge HX Room 94 ND MRCD-302 D302: Reactor Control Room 139 ND MRCD-302A D302A: Reactor Supervisor's Office 24 N/A MRCBP1 D104: Beam Port Number 1 44 ND MRCBP2 D 104: Beam Port Number 2 89 ND MRCBP3 D 104: Beam Port Number 3 678 ND MRCBP4 D104: Beam Port Number 4 348 ND (1) The total recorded dose equivalent values do not include natural background contribution and, reflect the summation of the results of four quarterly beta-gamma dosimeters or four quarterly fast neutron dosimeters for each location. A total dose equivalent of"ND" 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 less than the vendor's threshold of 10 mrem. "N/A" indicates that there was no neutron monitor at that location.

(2) These dose equivalent values do not represent radiation exposure through an exterior wall directly into an unrestricted area.

Protection V- 16

Table V.D.2 Total Dose Equivalent Recorded on Area Dosimeters Located Within the Radiation Center Total Recorded t

Radiation Center Dose Equivalentri Monitor Facility Location xp3(y) Neutron I.D. (See Figure V.D.1) (mrem) (mrem)

MRCAIOO A100: Receptionist's Office 10 N/A MRCBRF A102H: Front Personnel Dosimetry Storage Rack ND N/A MRCA120 A120: Stock Room ND N/A MRCA120A AI20A: NAA Temporary Storage ND N/A MRCA126 A126: Campus RSO's Isotope Receiving Lab 212 N/A MRCCO-60 A128: 'Co Irradiator Room 272 N/A MRCA130 A130: Shielded Exposure Room ND N/A MRCA132 A132: TLD Equipment Room ND N/A MRCA134-2 A134: Graduate Student Office 27(2) N/A MRCA138 A138: Health Physics Laboratory ND N/A MRCA146 A146: Gamma Analyzer Room (Storage Cave) ND N/A MRCB 100 B 100: Gamma Analyzer Room (Storage Cave) 23 N/A MRCB 114 B114: a Lab ( 26Ra Storage Facility) 1,412 83 MRCB119-1 B119: Source Storage Room 182 N/A MRCB 119-2 B 119: Source Storage Room 405 N/A MRCB1 19A BI 19A: Sealed Source Storage Room 4222 ,1908 MRCB120 B120. Instrument Calibration Facility ND N/A MRCB122-2 B122: Radioisotope Storage Hood ND .N/A MRCBI22-3 B122: Radioisotope Research Laboratory ND N/A MRCB124-1 B124: Radioisotope Research Lab (Hood) ND NIA MRCB124-2 B 124: Radioisotope Research Laboratory ND N/A MRCB124-6 B124: Radioisotope Research Laboratory ND N/A MRCB128 B128: Instrument Repair Shop ND N/A MRCC100 CI00: Radiation Center Director's Office ND N/A MRCC106A CI06A: Staff Lunch Room ND N/A MRCC106B C106: Solvent Storage Room ND N/A MRCC106-H C106H: East Loading Dock ND N/A See footnotes following the table. Protection V- 17

Table V.D.2 (continued)

Total Dose Equivalent Recorded on Area Dosimeters Located Within the Radiation Center Total Recorded Radiation Center Dose Equivalente' Monitor Facility Location xp(y) Neutron I.D. (See Figure V.D.1) (mrem) (mrem)

MRCC 118 Cl 18: Radiochemistry Laboratory 18 N/A MRCC120 C120: Student Counting Laboratory ND N/A MRCFI00 FI00: APEX Facility ND N/A MRCF102 F102: APEX Control Room ND N/A MRCBI25N B125: Gamma Analyzer Room (Storage Cave) ND N/A MRCB125S B125: Gamma Analyzer Room ND N/A MRCC124 C124: Student Computer Laboratory ND N/A MRCC130-1 C130: Radioisotope Laboratory (Hood) ND N/A MRCD100 D100: Reactor Support Laboratory 165 N/A MRCDI02 ID102: Pneumatic Transfer Terminal Lab 116 ND MRCD 102-H D102H: Ist Floor Corridor at D102 38 ND MRCD106-H DI06H: Ist Floor Corridor at Dl106 111 N/A MRCD200 D200: Reactor Administrators's Office 157 ND MRCD202 D202: Senior Health Physicist's Office 167 ND MRCBRR D200H: Rear Personnel Dosimetry Storage Rack ND N/A MRCD204 D204 Health Physicist Office 104 ND MRCF104 F104: ATHRL ND ND MRCD300 D300: 3rd Floor Conference Room 94 ND (1) The total recorded dose equivalent values do not include natural background contribution and, except as noted, reflect the summation of the results of 4quarterly beta-gamma dosimeters or four quarterly fast neutron dosimeters for each location. A total dose equivalent of"ND" 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 less than the vendor's threshold of 10 mrem. "N/A" indicates that there was no neutron monitor at that location.

(2) The room was only monitored for one quarter of this report.

Protection V- 18

Table V.D.3 Annual Summary of Radiation Levels and Contamination Levels Observed

-Within the Reactor Facility and Radiation Center During Routine Radiation Surveys "WholeBody Contamination Accessible Location Radiation Levels Levels°i (See Figure V.D.1) (mnrenm h-' (dpmll00 cm 2)

I_ 1 Average -Maximum Average Maximum TRIGA Reactor Facility: _

Reactor Top (D 104) 1 80 <500 <1800 Reactor 2nd Deck Area (D 104) 5 23 <500 <500 Reactor Bay SW (D 104) <1 3 <500 <800 Reactor Bay NW (D 104) <1 4 <500 <1800 Reactor Bay NE (D)104) <1 32 <500 1800 Reactor Bay SE (D 104) <1 5 <500 <600 Class Experimnents (D104, D302) <1 2 <500 <500 Demineralizer Tank-Outside Shielding (D104A) <1 2 <500 <500 Particulate Filter-Outside Shielding (D 104A) <1 3 <500 <500 Radiation Center:

NAA Counting Rooms (A146, B100, C134) <1 <1 <500 <500 Health Physics Laboratory (A138) <1 <1 <500 <500 60 <1 3 <500 <500 Co Irradiator Room and calibration rooms (A128, A130, B120)

Radiation Research Labs <1 <1 <500 <500 (3108, B114, B122, B124, C130, C132A)

Radioactive Source Storage (A120A, B 119, <1 2 <500 <500 B I19A)

Student Chemistry Laboratory (C 118) <1I <5 <500 <500 Student Counting Laboratory (C 120) <1 <1 <500 <500 Operations Counting Room (B 136, C123) <1 <1 <500 <500 Pneumatic Transfer Laboratory (D102) <1 2 <500 <1600 TRIGA Tube Wash Room (D100) <1 <1 <500 <500 (1) <500 dpm/100 cm 2 = Less than the lower limit of detection for the portable survey instrument used.

Protection V,- 19

Table V.E.1 Total Dose Equivalent at the TRIGA Reactor Facility Fence Total Calculated Total Recorded Dose Equivalent Total Recorded Dose Equivalent (Including Background)

Fence Dose Equivalent (Including Based on the Environmental (Including Background) Background) Annual Average Monitoring Based on ICN Based on OSU jirem h-'

Station TLDs0)" TLDs(2X3 ) Dose Rate(3)

(See Figure V.E.1) (mrem) (mrem) (mrem)

MRCFE-l 93 10 65 +/-6 74 +/- 9 MRCFE-2 83 +/-3 61 +/-6 70 +/- 9 MRCFE-3 77 4- 3 62 +/- 6 60 +/- 11 MRCFE-4 85 +/- 4 68 +/- 10 66 +/- 17 MRCFE-5 82 +/- 3 61 +/- 6 66 +/- 8 MRCFE-6 84 +/- 4 64 +/- 7 70 +/- 16 MRCFE-7 81 +/- 3 62 +/- 6 67+/- 11 MRCFE-8 81 +/- 2 61 +/- 6 63 +/- 9 MRCFE-9 80 +/- 3 60 +/- 6 67 +/- 9 (1) Average Corvallis area natural background using ICN TLDs totals 71 +/- 5 mrem for the same period.

(2) OSU fence totals include a measured natural background contribution of 63 +/- 6 mrem.

(3) +/- values represent the standard deviation of the total value at the 95% confidence level.

Protection V- 20

Table V.E.2 Total Dose Equivalent at the Off-Site Gamma Radiation Monitoring Stations Total Calculated Dose Equivalent Total Recorded Total Recorded (Including Background)

Off-Site Dose Equivalent Dose Equivalent Based on the Radiation (Including Background) (Including Background) Annual Average Monitoring Based on ICN Based on OSU p.rem/h Stationo') TLDs(2) TLDs(3X4) Exposure Rate"4 )

(See Figure V.E.2) (mrem) (mrem) (mrem)

MRCTE-2L --- 56 +/- 7 50+/- 11 MRCTE-3 88 +/- 3 57 +/- 6 64 +/- 10 MRCTE-4 79 +/-2 95 +/- 3-7 - 55-8 MRCTE-5L --- 57 +/- 6 70 +/- 16 MRCTE-6 80 +/- 4 .53+/-5 66 +/- 15 MRCTE-7L --- 54 +/- 6 77+/- 11 MRCTE-8 89+/-3 - 59+/-6 74h 10 "

MRCTE-9 76+/- 4 51 +/- 5 64 +/- 6 MRCTE-I0 78 +/- 3 89 +/- 25 58 +/- 7 MRCTE-12 84 +/- 3 63 +/- 9 69 +/- 10 MRCTE-13L -- 56+/- 8 62 +/- 13 MRCTE-14L --- 53 +/- 6 53 +/- 15 MRCTE-15 72 4 53 +/- 4 48 +/- 8 MRCTE-16L -- 65 +/- 6 64 +/- 8 MRCTE-17 81 3 66 +/- 5 58 +/- 8 MRCTE-18L --- 59 +/- 6 60 +/- 8 MRCTE-19 79 +/- 2 64 +/- 5 76 +/-11 MRCTE-20L --- 59 +/- 4 66+/- 11 MRCTE-21 69 +/- 3 55 +/- 7 47 +/- 10 MRCTE-22 74 +/- 5 5+/- 7 53 +/- 10 (1) Monitoring stations coded with an "L" contained one standard OSU TLD pack only. Stations not coded with an 'V" contained, in addition to the OSU TLD pack, one ICN TLD monitoring pack.

(2) Average Corvallis area natural background using ICN TLDs totals 71 +/- 5 mnrem for the saine period.

(3) OSU off-site totals include a measured natural background contribution of 63 +/- 6 mrem.

(4) +/- values represent the standard deviation of the total value at the 95% confidence level.

Protection V- 21

Table V.E.3 Annual Average Concentration of the Total Net Beta Radioactivity (Minus 3H) for Environmental Soil, Water, and Vegetation Samples a Sample Annual Average Concentration (SoeaFigure Smple of the Total Net Beta (Minus 1H) Ung (See Figure Type Rdoci! Units v.E.2) Radioactivity°'

1-W Water 1.02E-07 +/- 9.70E-08( 2) [i.Ci ml' 2) 4-W Water 1.02E-07 +/- 4.16E-09( [LCi mi, 2

I1-W Water 4.01E-07 +/- 1.33E-06( ) l4Ci m.1, 19-RW Water 4.O1E-07+ 1.33E-06(2) [,LCi mi-,

3-S Soil 3.85E-05 +/- 6.65E-05 [iCi g' of dry soil 5-S Soil 2.33E-05 +/- 4.54E-05 [Ci g'l of dry soil 20-S Soil 2.65E-05 +/- 4.15E-05 l, Ci g7' of dry soil 21-S Soil 4.20E-05 :- 2.54E-05 [tCi g.l of dry soil 2-G Grass 3.73E-04 +/- 1.05E-04 0Ci g-' of dry ash 6-G Grass 2.43E-04+/- 2.62E-04 [Ci g-l of dry ash 7-G Grass 3.91E 9.65E-05 [Ci g' of dry ash 8-G Grass 3.41E-04 +/- 1.26E-04 0Ci g-' of dry ash 9-G Grass 3.07E-04 +/- 1.64E-05 [tCi g-' of dry ash 1O-G Grass 1.26E-04 +/-6.83E-05 OCig7' of dry ash 12-G Grass 3.34E-04 +/-- 1.47E-04 tCi g-1 of dry ash 13-G Grass 2.35E-04 +/-2.23E-04 pCi g-' of dry ash 14-G Grass 1.95E-04 +/- 2.84E-04 JLCi g' of dry ash 15-G Grass 1.63E-04 +/- 1.49E-04 oCi g" of dry ash 16-G Grass 1.71E-04 +/- 1.44E-04 pCi g-' of dry ash 17-G Grass 2.58E-04 :h 7.56E-05 OCi g-' of dry ash 18-G Grass 1.98E-04 +/- 1.60E-04 pCi g' of dry ash 22-G Grass 2.91 E-04 +/- 3.22E-04 ltCi g-' of dry ash (1) +/- values represent the standard deviation of the average value at the 95% confidence level.

(2) Less than lower limit of detection value shown.

Protection V- 22

Table V.E.4 Average LLD Concentration and Range of LLD Values for Soil, Water, and Vegetation Samples Sample ,Average, Range of Reporting Type LLD Value. LLD Values Units Soil 1.19E-05 9.60E-06 to 1.47E-05 .tCi g-' of dry soil Water 2.99E-07 6.08E-08 to 1.42E-06 ItCi ml"1 Vegetation 3.50E-05 1.33E-05 to 1.33E-04 1.Ci g-' of dry ash Protection V- 23

Table V.F.1 Annual Summary of Radioactive Material Shipments Originating From the TRIGA Reactor Facility's NRC License R-106 Number of Shipments Total F F Shipped To Activity Limited Yello ello (TBq)IQuantity II III Total Berkeley Geochronology Center Berkeley, CA USA 6 86E-06 9 1 0 10 Brigham Young UniversityI Provo, UT USA 6.95E-07 1 0 0 1 California Institute of Technology Paaea AUA!3.05E-05 2 0 0 2 Pasadena, CA USA Columbia University 5 0 0 Palisades, NY USA 5.98E-06 5 0 0 5 General Dynamics 2 i Scottsdale, AZ USA 2.67E-06 6 0 0 6 Georgia Tech Atlanta, GA USA 1 0 1 Idaho State University I Pocatello, ID USA 402E-05 0 8 0 8 Oregon State University 1 Corvallis, OR USA 1.94E-05 PCC Structurals, Inc.

Portland, OR USA 5.64E-07 0 Plattsburgh State University Plattsburgh, NY USA 1.45E-06 3 0 0 3 Stanford University 1. I Stanford, CA USA 1.91E-05 3 I 0 4 Synetix I Houston, TX USA 0.OOE+00 1 0 0 I Syracuse University Syracuse, NY USA 4.07E-06 2 I 0 3 Union College 2 5 Schenectady, NY USA 265 0 0o 5 University of California at Berkeley I7.69E-06 0 Berkeley, CA USA24 Protection V- 24

Table V.F.1 Annual Summary of Radioactive Material Shipments Originating

'From the TRIGA ReactbrFacility's NRC Licen~e R-106 Number of Shipments Total I Shipped To Activity Limited Yellow Yellow]

(TBq) Quantity II III Total University of California at Santa Barbara I I I Santa Barbara, CA USA 2.56E-06 6 0 0 6 University of Nevada Las Vegas 1 0 0 1 Las Vegas, NV USA University of Wisconsin-Madison 2 E Madison, WI USA 2.11E-05 2 2 0 4 University of Wyoming Laramie, WY USA 1.10E-06 2 0 0 '2 Totals I1.67E-04 53 18 0 I 71 ProtectionV.- 25

Table V.F.2 Annual Summary of Radioactive Material Shipments Originating From the Radiation Center's State of Oregon License ORE 90005 Shipped To Total Activity INumber of Shipments (TBq) LSA - 1 Quantity Limited White I

Yellow II Total -2 Argonne National Lab 6.01E-08 1 1 0 0 2 Argonne, IL USA Lawrence Berkeley National Laboratory 1.35E-09 2 1 0 0 3 Berkeley, CA USA Oregon State University 5.75E-04 0 3 1 0 4 Corvallis, OR USA PCC Structurals, Inc.

9.28E-08 0 1 0 0 1 Portland, OR USA Radiation Protection Services 8.43E-07 0 2 0 0 2 Portland, OR USA Protection V- 26

Table V.F.2 Annual Summary of Radioactive Material Shipments Originating From the Radiation Center's State of Oregon License ORE 90005 Total Number of Shipments Shipped To Activity LSA - I Limited White Yellow (TBq) Quantity I II Total Reed College 5.73E-07 0 1 0 0 Portland, OR USA Totals 5.76E-04 3 9 1 0 13 ProtectionV- 27

Table V.F.3 Annual Summary of Radioactive Material Shipments Exported

-Under NRC General License 10 CFR 110.23 Total Number of Shipments Shipped To Activity Limited Yellow Yellow (TBq) Quantity II III Total

-J..

FAPIG Radiation Research Laboratory Ltd. 4 1E - 0 Yokosuka Kanagawa, JAPAN 1 I4.14E-07 0 0 1 Freiburg University 2 I Zurich, Switzerland 2.17E-07 1 0 0 Geological Institute Copenhagen K, Denmark 3

365E07 1 0 0 I

Ruhr-Universitat Bochum Bochum, GERMANY 4.15E-07 1 0 0 1 Scottish Universities Research and Reactor Centre East Kilbride, SCOTLAND 1.75E-06 0 1 0 1 Universita' Degli Studi di Bologna5 0 Bologna, ITALY E Universitat Potsdam Postdam, GERMANY 4.67E-07 4 0 0 4 Universitat Tubingen I0 Tubingen, GERMANY 1.07E-06 2 0 2 Universite Paris-Sud Paris, FRANCE 2.43E-06 0 1 0 1 University of Manchester 11 1 Manchester, UK 10 1 University of Montpellier Montpellier, FRANCE 1.95E-06 2 0 2 University of Queensland Brisbane, Australia 801 5.78E_07 jI 0 2 University of Queensland 1

I 1

I 0 2 Brisbane, Queensland AUSTRALIA 1.36E-06 University of Tuebingen I Tuebingen, GERMANY 1.16E-10 1 0 0 1 Vrije Universiteit 0 Amsterdam, THE NETHERLANDS 1.56E-06 Totals 1.43E-05 17 6 0 23 Protection V- 28

I

[~

I I'7i ~ r ............ I 0

C=33 CD roEwb~ 091's

~ 0

Part VI Work

Part VI WORK, A. Summary

-The Radiation Center offers a wide varietyofresources for teaching, research, and service related to radiationfand radioactive materials.' Some of these are discussed in detail in other parts ofthis report. The purpose of this part is to summarize the teaching, research, and service efforts carried out during the current reporting period.

B. Teaching An important responsibility of the Radiation Center and the reactor is to support OSU's academic programs. Implementation of this support occurs through direct involvement of the Center's staff and facilities in the teaching programs of various departments and through participation in University research programs. For example, during the current reporting period, the Radiation Center accommodated 119 academic classes involving a number ofdifferent academic departments from OSU and other Oregon universities. .The OSU teaching programs (not including research) utilized 724 hours0.00838 days <br />0.201 hours <br />0.0012 weeks <br />2.75482e-4 months <br /> ofreactor time. Tables III.A. 1 and I.D.1 plusSection VI.C.5 provide more detailed information on the use of the Radiation Center and reactor for instruction and training.

C. Research and Service Almost all Radiation Center research and service work is tracked by means ofa project database.

When a request for facility use is received, a project number is assigned and the project is added to the database. The database includes such information as the project number, data about the person and institution requesting the work, information about students involved, a description of the proj ect, Radiation Center resources needed, the Radiation Center project manager, status of individual runs, billing information, and the funding source.

Table VI.C. 1provides a summary of institutions which used the Radiation Center during this

,reporting period. This table also includes additional information about the number of academic personnel involved, the number of students involved, and the number ofuses logged for each organization: Details on graduate student 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 ofthe 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 agency. Projects which used

" Work VI-1

the reactor are indicated by an asterisk. In addition to identifying specific projects carried out during the current reporting period, Part VI also highlights major Radiation Center capabilities in research and service. These unique Center functions are described in Sections VI.C. 1 through VI.C.8.

1. Neutron Activation Analysis Neutron activation analysis (NAA) stands at the forefront oftechniques for the quantitative multi-element analysis of major, minor, trace, and rare elements. The principle involved in NAA consists of first irradiating a sample with neutrons in a nuclear reactor such as the OSTRto 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 gamma rays detected at a particular energy are usually indicative of a specific radionuclide's presence. Computerized data reduction of the gamma ray spectra then yields the concentrations ofthe various elements in samples being studied. With sequential instrumental NAA it is possible to measure quantitatively about 35 elements in small samples (5 to 100 mg), and for activable elements the lower limit ofdetection is on the order ofparts per million or parts per billion, depending on the element.

The Radiation Center's NAA laboratory has analyzed the major, minor, and trace element content oftens ofthousands ofsamples covering essentially the complete spectrum of material types and involving virtually every scientific and technical field.

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, sequential irradiation 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.

2. Forensic Studies Neutron activation analysis can also be advantageously used in criminal investigations. The principleunderlying such application usually involves matching trace element profiles in objects or substances byNAA. 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 for forensic purposes include bullets, metals, paint, fuses, coats, glass, meat, and salts.

Work VI- 2

Forensic 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 capabilityofthe Radiation Center involves the irradiation of a large variety of substances with gamma rays and neutrons. Detailed data on these irradiations and their use during this reporting period are included in Part III as well as in Section C of this part.

4. Radiological Emergency Response Services The Radiation Center has an emergency response team capable ofresponding to all types ofradiological accidents. This team directly supports the City of Corvallis and Benton County emergency response organizations and medical facilities. The team can also provide assistance at the scene ofanyradiological incident anywhere in the state of Oregon on behalf of the Oregon Radiation Protection Services and the Oregon Office ofEnergy.

The Radiation Center maintains dedicated stocks ofradiological emergency response equipment and instrumentation. These items are located at the Radiation Center and at the Good Samaritan Hospital.

During the current reporting period, the Radiation Center emergency response team conducted several training sessions and exercises, but was not required to respond to any actual incidents.

During the past year, Radiation Center personnel participated in drills and exercises, and provided advice relating to emergency response to a radiological incident at the Hanford Site in southwestern Washington; but no one was required toorespond to a real Hanford emergency.

5. Training and Instruction  :

In addition to the academic laboratory classes and courses discussed in Parts III.A.2, UI.D, and VI.B, and in addition to the routine training needed to meet the requirements of the OSTR Emergency Response Plan, Physical SecurityPlan, 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, radiological emergency response, reactor behavior (for nuclear power plant operators), neutron activation analysis, nuclear chemistry, and nuclear safety analysis.

Work VI - 3

Special training programs generally fall into one of several categories: visiting faculty and research scientists; International Atomic Energy Agency fellows; special short-term courses; or individual reactor operator or health physics training programs. During this reporting period there were a large number of such people as shown in Part II.B.

As has been the practice since 1985, Radiation Center personnel annually present a HAZMAT Response Team Radiological Course. This year the course was held at the Oregon State University Radiation Center.

6. Radiation Protection Services The primary purpose ofthe radiation protection program at the Radiation Center is to support the instruction and research conducted at the Center. However, due to the high quality ofthe program and the level of expertise and equipment available, the Radiation Center is also able toprovide health physics services in support of Radiation Safety 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 state resources.

The Radiation Center is capable ofproviding 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 ofradioactive materials, calibration and repair of radiation monitoring instruments (discussed in detail in Section VI.C.7),

radioactive waste disposal, radioactive material hood flow surveys, and radiation safety analysis and audits.

The Radiation Center also provides services and technical support as a radiation laboratory to the Oregon State Health Division (OSHD) in the event of a radiological emergency within the state of Oregon. In this role, the Radiation Center will provide gamma ray spectrometric analysis of water, soil, milk, food products, vegetation, and air samples collected by OSHD radiological response field teams. As part of the ongoing preparation for this emergency support, the Radiation Center participates in inter-institution drills.

7. Radiological Instrument Repair and Calibration While repair ofnuclear instrumentation is a practical necessity, routine calibration 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.

Work VI- 4

-J

The Center's scientific instrument repair facility performs maintenance and repair on all types of radiation detectors and other nuclear instrumentation. Since the Radiation Center's own programs regularly utilize a wide range ofnuclear instruments, components for most common repairs are often on hand and repair time is therefore minimized.

In addition to the instrument repair capability, the Radiation Center has a facility for calibrating essentially all types ofradiation 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 performed using radiation sources certified by the National Institute of Standards and Technology (NIST) or traceable to NIST.

Table VI.C.4 is a summary of the instruments which were calibrated in support ofthe Radiation Center's instructional and research programs and the OSTR EmergencyPlan, while Table VI.C.5 shows instruments calibrated for other OSU departments and non-OSU agencies. Table VI.C.6 shows instruments repaired for non-Radiation Center departments and agencies. It should be noted that the Radiation Center ohlycalibrates and repairs instruments for local, state and federal agencies.

8. Consultation Radiation Center staff are available to provide consultation services in any of the areas discussed in this Annual Report, but in particular on the subjects of research reactor operations and use, radiation protection, neutron activation analysis, radiation shielding, radiological emergency response, and radiotracer methods.

Records are not normally kept of such consultations, as they often take the form of telephone conversations with researchers encountering problems or planning the design of experiments. Many faculty members housed in the Radiation Center have ongoing professional consulting functions with various organizations, in addition to sitting on numerous committees in advisory capacities.

9. Public Relations The continued interest of the general public in the OSTR is evident by the number of people who have toured the facility. In addition to many unscheduled visitors and interested individuals who stopped in without appointments becauseithey were in the vicinity, a total of 128 scheduled tours including 1,499 people were given during this reporting period. See Table VI.F. 1 for statistics on scheduled visitors.

Work VI-, 5

Table VI.C.1 Institutions and Agencies Which Utilized the Radiation Center Number of Number of Number of Number of Uses of Proe Faculty Students Center Institution Projects Involved Involved Center Facilities 11

• Oregon State Universityt 79 38 11 2100)

Corvallis, OR USA

• Crescent Valley High School 2 1 0 1 Corvallis, OR USA

• Linn Benton Community College 1 0 0 3 Albany, OR USA

• Marist High School 1 0 0 Eugene, OR USA

• McKay High School 1 0 0 1 Salem, OR USA Osmotek I 1 0 1 Albany, OR USA

• PCC Structurals, Inc. 1 0 0 5 Portland, OR USA

• Eddyville High School I 1 0 1 Eddyvulle, OR USA

• Fall City High School 1 0 Fall City, OR USA

• Grants Pass High School 1 0 Grants Pass, OR USA

• Jefferson High School 1 0 Jefferson, OR USA

• Phllomath High School I 1 0 Philomath, OR USA Providence St. Vincent Hospital 1 0 0 11 Portland, OR USA

• Reed College 1 0 Portland, OR USA

• Sheridan School District I 1 0_1 Sheridan, OR USA

• Thurston High School I 1 0 1 Springfield, OR USA

• Wheeler County Sheriff's Office 1 0 0 2 Fossil, OR USA

--I

• Project which involves the OSTR. Work VI - 6

Table VI.C.1 (continued)

Institutions and Agencies Which Utilized the Radiation Center Numberofof Number of uses Number of Number of Faculty Students Institution Center Projects Involved Involved Facilities Army Corps of Engineers 1 0 0 2 Portland, OR USA AVI Biopharma 0 Corvallis, OR USA ESCO Corporation 6 Portland, OR USA Evanite Fiber Corp 1 Corvallis, OR USA Federal Aviation Administration 10 5 Portland, OR USA Good Samaritan Hospital 0 0 7 Corvallis, OR USA Hot Cell Services 0 0 4 Kent, WA USA Josephine County Public Works 0 0 Oregon, USA Kirner Consulting 1 0 1 Tacoma, WA USA _ *_

Occupational Health Laboratory 0 0 Portland, OR USA Oregon Office of Energy 0 0 31 Salem, OR USA Oregon Department of Transportation 0 0 Salem, OR USA Oregon Health Sciences University 0 0 22 Portland, OR USA _

Oregon Public Utilities Commission 1 5 Salem, OR USA Oregon State Health Division 1 58 Salem, OR USA Rogue Community College 0 0 Grants Pasi, OR USA USDA Agricultural Research Station 0 Oregon, USA

• Project which involves the OSTR Work V1- 7

Table VI.C.1 (continued)

Institutions and Agencies Which Utilized the Radiation Center Number of Number of Number of Number of Uses of Faculty Students Institution Involved Involved Center Projects Facilities USDA Agricultural Research Station Oregon, USA U.S. Environmental Protection Agency 2 0 0 5 Newport, OR USA Valley Landfills, Inc. 0 0 2 Corvallis, OR USA Veterinary Diagnostic Imaging Cytopathology Clackamas, OR USA

• Double Hat Enterprises 1 Idaho Falls, ID USA

• Idaho State University 1 1 1 4 Pocatello, ID USA

• Liberty Christian High School 1 0 0 Richland, WA USA

• Berkeley Geochronology Center 1 0 4 19 Berkeley, CA USA

• California Institute of Technology I 1 0 3 Pasadena, CA USA M.K. Gems and Minerals 1 0 0 La Habra, CA USA

• Stanford University 2 2 4 Stanford, CA USA

• University of California at Berkeley 3 3 1 2 Berkeley, CA USA

• University of California at Davis 0 0 Davis, CA USA

• University of California at Santa Barbara 2 2 5 8 Santa Barbara, CA USA _

• Umversity of Nevada Las Vegas 1 1 0 Las Vegas, NV USA

• Brigham Young University I I I 1 Provo, UT USA

• University of Wyoming Laramie, WY USA

• Project which involves the OSTR. Work VI - 8

Table VI.C.1 (continued)

Institutions and Agencies Which Utilized the Radiation Center Number of Number of Number of Number of Uses of Institution Projects Faculty Students Center Involved Involved Facilities

• General Dynamics , 0' 7 Scottsdale, AZ USA

• University of California at Los Angeles I I Los Angeles, California

• Brigham Young University 2 2 2 4 Provo, Utah

• University of Wyoming 2 3 Laramie, Wyoming 2 3

• General Dynamics 0 0 7 Scottsdale, AZ USA ____ _

• Geovic Ltd. 0 0 Grand Junction, CO USA . ""

• University of Houston 1 2 Houston, TX USA

• University of Wisconsin 2 2 5 7 Madison, WI USA

• International Titanium Powder 1 0 0 1 0

Lockport, IL USA

• University of Michigan 0, Ann Arbor, MI USA _ 0___1

• Wayne State University 1 0 Detroit, MI USA

• Georgia Institute of Technology 1 1 ,0 2 Atlanta, GA USA Mississippi State University 1 0 01 Mississippi State, MS USA

• Columbia University 3 3 3 5 Palisades, NY USA

• George Washington University 1 1 2 2 Washington, DC USA

• North Carolina State University 2 2 3 3 Raleigh, NC USA

• Plattsburgh State University 2 2 3, 3 Plattsburgh, NY USA

• Project which involves the OSTR 'Work VI1- 9

Table VI.C.1 (continued)

Institutions and Agencies Which Utilized the Radiation Center Numberofof Number of uses Number of Faculty Students Center Institution Projects Involved Involved Center Facilities

• Syracuse University 1 1 3 4 Syracuse, NY USA

• Union College 2 2 0 4 Schenectady, NY USA

• University of Georgia I I I I Aiken, SC USA

• University of Florida 2 2 0 2 Gainesville, FL USA

• FAPIG Radiation Research Laboratory Ltd. 1 0 0 1 Yokosuka Kanagawa, JAPAN

• Scottish Universities Research and Reactor Centre 1 1 15 2 East Kilbride, SCOTLAND

• University of Manchester I 1 1 Manchester, UK

• Universlte Paris-Sud I 1 0 1 Paris, FRANCE

• University of Montpelier 1 0 0 3 Montpelier, FRANCE

-S

• Vnje Universiteit 1 1 4 2 Amsterdam, THE NETHERLANDS

• Albert-Ludwigs-Universitaet 1 0 0 3 Freiburg, GERMANY

• Geological Institute 1 0 0 1 Copenhagen, DENMARK

• Guzzi Dental Services 1 0 0 1 Milano, ITALY

• Ruhr-Unversitat Bochum 1 1 0 2 Bochum, GERMANY

• Universita'Degli Studi di Bologna 1 2 0 1 Bologna, ITALY

• Universitat Potsdam 1 0 0 5 Potsdam, GERMANY

• Umversitat Tubingen 1 1 0 1 Tubingen, GERMANY

• I

• Project which involves the OSTR. Work VI- 10

Table VI.C.1 (continued)

Institutions and Agencies Which Utilized the Radiation Center-Number or Number of userof Number of Projects Faculty Students Center Institution Involved Involved - Fj1 r

ýFacilities

• University of Tuebingen 1 1 3 Tuebingen, GERMANY

• University of Queensland 1 0 2 Brisbane, Queensland AUSTRALIA Total 172 55 93 519

10. Use by Oregon State University does not include any teaching activities or classes accommodated by the Radiation Center.

11. This number does not include ongoing projects being performed by residents of the Radiation Center such as the APEX project, others in the Department of Nuclear Engineering or Department of Chemistry, or projects conducted by Dr. W. D. Loveland, which involve daily use of Radiation Center facilities.

• Project which involves the OSTR. Work VI- 11

Table VI.C.2 Graduate Student Research Which Utilized the Radiation Center Student's Name Degree Academic Department Faculty Advisor Project Thesis Topic Berkeley Geochronology Center Culler, PhD Earth and Planetary Alvarez 920 Lunar Impact History from Timothy Science Analysis of Impact Melt Spherules Knight, MA Earth and Planetary Renne 920 Geochemical and Isotopic Insights Kimberly Science into Continental Flood Basalts Kyoungwon, MA Earth and Planetary Renne 920 Reduction of Systematic Errors in Min Science 40Ar/39Ar Geochronology Zhou, MA Earth and Planetary Renne 920 Rates and Tempo of Permian Zhensheng Science Triassic Boundary Events.

Brigham Young University Hae Hae, MS Geology Kowalhs 335 Subsidence and Uplift History of Kevin the Uinta Basin from Apatite Fission Track Analysis Columbia University Machlus, PhD Earth Sciences Olsen 1267 Milankovitch cyclicity in the Malka Eocene Green River Formation, including dating tuff beds within the formation by Ar-Ar dating.

Young, PhD UCLA Geology Turrmn 1423 Petrology and geochemical Amy evolution of the Damavand trachyandesite volcano in northern Iran.

Zhong, MS Geosciences Hanson 1553 The Grain Size and Provenance of Jian Long Island Loess Idaho State University Scarberry, MS Geology Hughes 1588 Kaleb Work VI- 12

Table VI.C.2 Graduate Student Research Which Utilized the Radiation Center Student's Name - Degree -Academic Department Faculty Advisor Project Thesis Topic North Carolina State University .. . ..

McCarter, MS Departmnt of Marine, Fodor 1559 Crystallization and compositional Earth, and Atmospheric evolution of basaltic reservious, Renee Sci Mauna Loa volcano, Hawaii:

-petrology of gabbroic xenoliths.

Oregon State University Hart, MS Radiation Health Physics Higley 1589 Determination of Scanning Detection Efficiency Kevin Huang, PhD Chemistry Loveland - 1598 Zhongliang Mankowski, PhD Forest Products Morrell 815 Biology of Carpenter Ants in the Pacific Northwest and its Mark Relationship with Fungal Decay in Buildings Sinton, PhD Oceanography Duncan 444 Age and Composition of Two Large Igneous Provinces: The Christopher North Atlantic Volcanic Rifled Margin and the Caribbean Plateau Stone, PhD Chemistry 1580 Jennifer Villamar, MS Nuclear Engineering & Higley 1593 Determination of radiosensitivity Radiation Health Physics of ovarian cells in hamsters.

Glenda Scottish Universities Research and Reactor Centre Barry, PhD Leicester University Pringle 1073 Mongolian Basalts/Tectonics T.

Blecher, PhD Oxford University Pringle 1073 Aden Volcanic Differentiation J.

Cam, PhD Cambridge University Pringle 1073 Indonesian Volcanics S.

Work VI- 13

Table VI.C.2 Graduate Student Research Which Utilized the Radiation Center Student's Name Degree Academic Department Faculty Advisor Project Thesis Topic Chambers, PhD Edinburgh University Pringle 1073 North Atlantic Tertiary Province L.

Dixon, PhD Bristol University Pringle 1073 Subglacial Volcanics H.

Harford, PhD Bristol University Pringle 1073 Montserrat Volcanic Hazards C.

Heath, PhD Lancaster University Pringle 1073 St. Vincent Volcano Hazards E.

May, PhD Aberdeen University Pringle 1073 Chilean Basins G.

McElderry, PhD Liverpool University Pringle 1073 Chilean Tertiary Faulting -..

S.

Najman, PhD Edinburgh University Pringle 1073 Himalayan Foredeep Y.

Purvis, PhD Edinburgh University Pringle 1073 Turkish Basin Tectonics M.

Shelton, PhD Queens University Pringle 1073 North Channel Basin Evolution R.

Sowerbutts, PhD Edinburgh University Pringle 1073 Sardinia Evolution A.

Steele, PhD Aberdeen University Pringle 1073 Cerro Rico Silver ,.._.a G.

White, PhD Leicester University Pringle 1073 Canbean Crustal Growth R.

Work VI- 14

Table VI.C.2 Graduate Student Research Which Utilized the Radiation Center Student's Name Degree Academic Department Faculty Advisor Project Thesis Topic Syracuse University -..

Kline, MS Earth Sciences Fitzgerald 1555 Uplift of the Transantarctic Simon Mountains in the Reedy Glacier area Monteleone, PhD Earth Sciences Fitzgerald 1555 Papua New Guinea Woodlark Brian Basin Project Schwabe, PhD Earth Sciences Fitzgerald 1555 Exhumation in the western Erika Pyrenees University of California at Berkeley Patin, PhD College of Chemistry Hoffman 1468 Study of Production Mechanisms Joshua in Heavy Ion Actinide and Lead Target Reactions University of California at Santa Barbara Calvert, PhD Geological Sciences Gans 1020 Tectonic Studies in Eastern-Most Russia Andy Nauert, MS Geological Sciences Gans 1020 Volcanism in the Eldorado Jon Mountains, Southern Nevada University of Geneva Rapaille, PhD Mineralogy Marzoli 1413 Le Filon de Messejana (Espagne Cedric et Portugal): P6trologie et G~ochronologie University of Georgia Tostowaryk, MS Radiological Health Whicker 1475 The elimination and assimilation Sciences of cesium by freshwater Tracy invertebrates University of Manchester Flude, PhD Earth Sciences Burgess 1592 Rhyolite volcanism in Iceland:

timing and timescales of eruption Stephanie Work VI- 15

Table VI.C.2 Graduate Student Research Which Utilized the Radiation Center Student's Name Degree Academnic Department Faculty Advisor Project Thesis Topic University of Tuebingen Angelmaier, PhD Institut fur Geologie und Dunkl 1519 Exhumation path of different Petra Palaotologie tectonic blocks along the central part of the Transalp-Traverse (Eastern Alps).

Most, PhD Institut fur Geologie und Dunkl 1519 Mesozoic and Tertiary Thomas Palaontologie Tectonometamorphic Evolution of Pelagonian Massif Schwab, PhD Institut fur Geologie und Dunkl 1519 Thermochronology and Structural Martina Palaontologie Evolution of Pamir Mts.

University of Wisconsin Barquero-Molina, PhD Geology and Geophysics Singer 1612 Miriam

-- I Harper, MS Geology and Geophysics Singer 1612 Melissa Jicha, MS Geology and Geophysics Singer 1612 Brian Jicha, MS Geology and Singer 1465 Brian Geosciences Relle, MS Geology and Geophysics Singer 1465 Monica University of Wyoming Beland, MS Geology and Geophysics Murphy 321 Peter McMillan, PhD Geology and Geophysics Murphy 321 Beth Work VI- 16

Table VI.C.2 Graduate Student Research Which Utilized the Radiation Center Student's Name Degree Academic Department Faculty Advisor Project Thesis Topic Vrije Universiteit .

Beintema, PhD Department of Structural White/Wijbrans 1074 The Kinematics and Evolution Kike Geology Major Structural Units of the Archean Pilbara Craton, Western Australia Carrapa, MA' Isotope Geochemistry Wijbrans/Bertotti 1074 The tectonic record of detrital Barbara minerals on sun-orogenics clastic sediments Kuiper, PhD Isotope Geochemistry HilgenlWijbrans 1074 Intercalibration of astronomical Klaudia and radioisotopic timescales Work VI- 17

Table VI.C.3 Listing of Major Research and Service Projects Performed or In Progress at the Radiation Center and their Funding Agencies Project Users Organization Name Project Title Description Funding 321 Murphy University of Fission Track Dating Thermal column irradiations University of Wyoming of apatite and zircon samples Wyoming for fission track production to determine rock age.

335 Kowallis Brigham Young Fission Track Dating Dating of natural rocks and National Science University minerals via fission track Foundation methodology.

444 Duncan Oregon State Ar-40/Ar-39 Dating of Production of Ar-39 from K- OSU University Oceanographic Samples 39 to measure radiometric Oceanography ages on basaltic rocks from Department ocean basins.

481 Le Oregon Health Instrument Calibration Calibration of radiation Oregon Health Sciences University survey instruments. Sciences University

-4 488 Farmer Oregon State Instrument Calibration Calibration of portable OSU Radiation University radiation survey instruments Center for radiation users on OSU campus.

519 Martin US Environmental Instrument Calibration Calibration of portable USEPA-Corvallis Protection Agency radiation survey meters using the standard RC protocol.

521 Vance University of Fission Track Studies Thermal column irradiation University of Washington of zircon and other samples Washington to induce fission tracks in catcher foils for dating.

547 Boese US Environmental Survey Instrument Calibration of GM and other USEPA, Protection Agency Calibration portable survey meters as per Cincinnati, OH standard OSU protocol.

664 Reese Oregon State Good Samaritan Hospital Calibration of radiation OSU Radiation University Instrument Calibration survey instruments. Center 665 Reese Oregon State Corvallis Fire Department Calibration of radiation OSU Radiation University Instrument Calibration survey instruments. Center INAA = Instrumental Neutron Activation Analysis REE = Rare Earth Elements Work VI- 18

Table VI.C.3 Listing of Major Research and Service Projects Performed or In Progress at the Radiation Center and their Funding Agencies Project Users Organization Name Project Title Description. Funding 815 Morrell Oregon State Sterilization of Wood -Sterilization of wood OSU Forest University Samples samples to.2.5 Mrads in Co- Products 60 irradiator for fungal evaluations.

920 Becker Berkeley Ar-39/Ar-40 Age Dating Production of Ar-39 from K- Berkeley Geochronology 39 to determine ages in Geochronology Center various anthropologic and Center geologic materials.

930 McWilliams Stfinford University Ar-40/Ar-39 Dating of Irradiation of mineral grain Stanford Geological Samples samples for specified times University to allow Ar-40/Ar-39 dating. Geological &

Environmental.

Sci 932 Dumitru Stanford University Fission Track Dating Thermal column irradiation Stanford of geological samples for University fission track age-dating. Geology Department 1018 Gashwiler Occupational Calibration of Nuclear Calibrate radiation survey Occupational Health Lab Instruments meters. Health Laboratory 1020 Gans University of Tectonic Studies in Irradiation for Ar-40/Ar-39 National Science California at Santa Eastern-Most Russia dating using the CLICIT or Foundation Barbara dummy fuel element.

1072 Rasmussen Army Corps of Instrument Calibration Calibration of radiation U.S Army Engineers detection instruments. Engineer District, Portland.

1073 Pringle Scottish Argon 40/39 Dating of Age dating of various Scottish Universities Rock Minerals materials using the Ar-40/Ar- Universities Research and 39 ratio method. Research and Reactor Centre Reactor Centre 1074 Wijbrans Vrije Universiteit 40Ar-39 Ar Dating of 40Ar-39Ar dating of rocks Vrije Rocks and Minerals and minerals. Universiteit, Amsterdam INAA = Instrumental Neutron Activation Analysis REE = Rare Earth Elements Work VI- 19

Table VI.C.3 Listing of Major Research and Service Projects Performed or In Progress at the Radiation Center and their Funding Agencies Project Users Organization Name Project Title Description Funding 1075 Lederer University of Activation Analysis Irradiation of small, stainless University of California at Experiment for NE Class steel discs for use in a California at Berkeley nuclear engineering radiation Berkeley measurements laboratory.

1118 Larson Oregon State Primary Phytoplankton Evaluation of the primary US Geological University Production Studies at production of phytoplankton Survey Crater Lake in Crater Lake and lakes in Mount Rainier, Olympic, and North Cascades National Parks.

1127 Numata FAPIG Radiation Kyoto Fission Track Age Irradiation of samples in the FAPIG Radiation Research Dating thermal column for fission Research Laboratory Ltd. track age dating. Laboratory 1188 Salinas Rogue Community Photoplankton Growth in C-14 liquid scintillation Rogue College Southern Oregon Lakes counting of radiotracers Community produced in a photoplankton College study of southern Oregon lakes: Miller Lake, Lake of the Woods, Diamond Lake, ._.,t and Waldo Lake.

1191 Vasconcelos University of Ar-39/Ar-40 Age Dating Production of Ar-39 from K- Earth Sciences, Queensland 39 to determine ages in University of various anthropologic and Queensland geologic materials.

1267 Hemming Columbia Geochronology by Ar/Ar Snake River plain sanidlne Columbia University Methods phenocrysts to evaluate University volcanic stratigraphy; sandine and biotite phenocrysts from a late Miocene ash, Mallorca to more accurately constrain stratigraphic horizon; hornblends and feldspar from the Amazon to assess climatic changes and differences in Amazon drainage basin provenance.

INAA = Instrumental Neutron Activation Analysis REE = Rare Earth Elements Work VI- 20

Table VI.C.3 Listing of Major Research and Service Projects Performed or In Progress at the Radiatiofn'Center and their Funding Agencies Project Users - Organization Name --Project Title -. . Description_ Funding .

1290 Kahn M. K. Gems and 'Mineral Irradiations Irradiations of various M. K. Gems &

-Minerals minerals to evaluate Minerals I colorization effects.

1302 Niles Oregon Office of Calibration of Emergency Routine calibration of Oregon Office of Energy Response Instruments radiological m6nitoring Energy instruments associated with the Oregon Office of Energy's programs supporting HazMat and other emergency response teams.

1352 Niles Oregon Office of General Consultation Radiological and radioactive Oregon Office of Energy material transport consulting Energy services 1354 Wright Radiation Radiological Instrument Routine calibration of Oregon Health Protection Services Calibration radiological monitoring Division instruments.

1359 Niles Oregon Office of State Laboratory Support Maintenance of state Oregon Office of Energy radiological monitoring Energy support capability, including..

QA, counting standards and calibrations of gamma spectrometer systems for measuring low lradioactivities in environmental and foodstuff samples.

1366 Quidelleur Universite Paris- Ar-Ar Geochronology Determination of geological Universite Paris Sud samples via Ar-Ar Sud radiometric dating.

1376 Proebsting Oregon State Genetics of Peas Produce deletion mutants of OSU Horticulture University peas on the SN and NP genes 1390 Bottomley Oregon State Soil Study Soil Study - OSU Crop and University Soil Science INAA = Instrumental Neutron Activation Analysis REE = Rare Earth Elements Work VI- 21

Table VI.C.3 Listing of Major Research and Service Projects Performed or In Progress at the Radiation Center and their Funding Agencies Project Users Organization Name - Project Title Description Funding 1397 Teach Providence St. Sterilization of various Sterilization of various Oregon Medical Vincent Hospital biological materials biological materials for St. Laser Institute Vincents Hospital, Portland 1399 Olander University of Volatilization of uranium Irradiation of vapor from University of California at material depleted uranium loaded on California at Berkeley resin and heated to high Berkeley temperatures in reducing atmosphere. U-235 in vapor deposits fissions; U-238 absorbs neutrons. Gamma ray spectrometry determines amount of uranium volatilized.

1404 Riera-Lizarau Oregon State Evaluation of wheat DNA Gamma irradiation of wheat OSU Crop and University seeds Soil Science 1406 Pate Tracerco Production of Argon-41 Production of Argon-41 for Tracerco -I various field uses 1413 Webb University of Argon Geochronology Ar-39/Ar-40 dating of pure University of Geneva mineral and whole rock Geneva separates.

1415 McGinness ESCO Corporation Calibration of Instruments Instrument calibration ESCO Corporation 1417 Loveland Oregon State Production of Various radionuclides will OSU Chemistry /

University Radionuclides for LBNL be produced for research to Loveland DOE be conducted at LBNL.

1423 Turrin Columbia 40Ar/39Ar Analysis Petrology and geochemical Columbia University evolution of the Damavand University trachyandesite volcano in Northern Iran.

1424 Yasinko Tru-Tec Argon 41 Production Irradiation of argon gas to Tru-Tec produce argon 41.

INAA = Instrumental Neutron Activation Analysis REE = Rare Earth Elements Work VI- 22

Table VI.C.3 Listing of Major Research and Service Projects Performed or In Progress at ihe Radiation Center and their Funding Agencies Project - Users Organization Name Project Title Description Funding 1430 Bottomley Oregon State - Atrazine Remediation in a Characterization of fate of OSU University Wetland Environment atrazine in wetland Microbiology mesocoms and a constructed Department wetland; investigation of presence of atrazine degrading microorganisms in rhizosphere soil.

1431 Stein AVI Bio Pharma Instrument Calibrations Instrument calibration AVI Bio Pharma 1464 Slavens USDOE Albany Instrument Calibration Instrument calibration USDOE Albany Research Center Research Center 1465 Singer University of Ar-40/Ar-39 Dating of' CLICIT irradiation of University of Wisconsin Young'Geologic Materials geological materials such as Wisconsin volcanic rocks from sea floor, etc. for Ar-40/Ar-39 dating.

1467 Kimer Kimer Consulting, Instrument Calibration Instrument calibration Kimer Consulting Inc 1468 Nitsche University of Chemistry 146 Experiment Sample irradiation University of California at California at Berkeley Berkeley 1470 Bolken SIGA Instrument Calibration Instrument calibration Siga Technologies, Inc. Pharmaceuticals 1473 Alarcon Becton Dickenson Gamma Irradiations Gamma Irradiation to 5k, 3k, Becton Technologies & 2k. Dickenson Technologies 1475 Hinton University of Cesium Cycling in a Cesium transfer rates among Savannah River "Georgia Freshwater Ecosystem ecosystem components are Ecology being determined in a Laboratory freshwater ecosystem.

Stable cesium was added to the entire pond and the dynamics are being followed using INAA to assay the cesium.

INAA = Instrumental Neutron Activation Analysis REE = Rare Earth Elements Work VI- 23

Table VI.C.3 Listing of Major Research and Service Projects Performed or In Progress at the Radiation Center and their Funding Agencies Project Users Organization Name Project Title Description Funding 1479 Paul Oregon State Biological Toxin Sensor Multidisciplinary OSU Industrial &

University development of a biological Manufacturing toxin sensor using Engineering arethrophore cells for the Defense Advanced Research Projects Agency.

1486 Hockmuth General Dynamics Irradiation of Electronic Study radiation effects on Motorola Components electronic components for the Nuclear and Space Radiation Effects Group 1488 Gartner Oregon State Determinants of sapwood Sterilization of wood cores OSU Forest University quantity and composition from tree stems to 3 Products Megarads.

1489 Roden-Tice Plattsburgh State Thermochronologic The integration of apatite Plattsburgh State University evidence linking fission-track ages and track University Adirondack and New length based model thermal England regions histories, zircon fission-track Connecticut Valley Regions ages, and U-Th/He analyses to better define the pattern of regional post-Early Cretaceous differential unroofing in northeastern New York's Adirondack region and adjacent western New England.

1492 Stiger Federal Aviation Instrument Calibration Instrument calibration Federal Aviation Administration Administration 1494 Hall Oregon State Flux Measurements in Measurement of the thermal, OSU Radiation University OSTR Irradiation Facilities epithermal, and fast fluxes in Center the various OSTR irradiation facilities INAA = Instrumental Neutron Activation Analysis REE = Rare Earth Elements Work VI- 24

Table VI.C.3 Listing of Major Research and Service Prbjects Performed or In Progress at the Radiition Center and their Fuiiding Agencies Project Users Organization Name . Project Title. Description Funding 1497 Dick Oregon State Tracing C-13 Signatures Using pine litter as a tracer OSU Crop and University from Pine Litter Raised for C into soil pools, looking Soil Science under Elevated C02 into for C sequestered from a set Soil C Storage Pools amount of pine litter. Will put the litter into EPA terracosm chambers. Need to sterilize pine needles.

1502 Teaching and Tours Portland Portland Community Reactor tour and half life USDOE Reactor Community College Tours/Experiments experiment. Sharing College 1503 Teaching and Tours Oregon State Non-class related tours Non-class related tours. OSU Radiation University Center 1504 -Teaching and Tours Oregon State OSU Nuclear Engineering OSU Nuclear Engineering USDOE Reactor University class tours class tours. Sharing 1505 Teaching and Tours Oregon State OSU Chemistry class tours OSU Chemistry class tours. USDOE Reactor University Sharing 1506 Teaching and Tours Oregon State OSU Geosciences class OSU Geosciences class USDOE Reactor University tours tours. Sharing 1507 Teaching and Tours Oregon State OSU Physics class tours OSU Physics class tours. USDOE Reactor University Sharing 1508 Teaching and Tours Oregon State Adventures iAiLearning Adventures in Learning class USDOE Reactor University class tours tours. Sharing 1509 Teaching and Tours Oregon State HAZMAT course tours First responder training tours. Oregon Office of University , Energy 1510 Teaching and Tours Oregon State SMILE Science and Mathematics USDOE Reactor University , Investigative Learning Sharing Experience tours.

1511 Teaching and Tours Oregon State Reactor Staff Use Reactor operation required OSU Radiation University fofrconduct of operations Center testing, operator training, calibration runs,

"- -- " encipsulation tests and other.

INAA = Instrumental Neutron Activation Analysis REE = Rare Earth Elements Work VI- 25

Table VI.C.3 Listing of Major Research and Service Projects Performed or In Progress at the Radiation Center and their Funding Agencies Project Users Organization Name Project Title Description Funding 1512 Teaching and Tours Linn Benton Linn Benton Community Reactor tour and half life USDOE Reactor Community College Tours/Experiments experiment. Sharing College 1513 Ayres Oregon State Absorption of Pharmaceuticals tagged with OSU Pharmacy University Pharmaceuticals in the Sm-153 are used to Colon determine their absorption in the colon.

1514 Sobel Universitat Apatite Fission Track Age determination of Universitat Potsdam Analysis apatites by fission track Potsdam analysis.

1516 McConica Oregon State Analysis of Fouled Residue from severely fouled Chemical University Harvester Engine Pistons harvester engine pistons was Engineering analyzed by INAA to determine silicon and metals content.

1517 Parikh Mississippi State Evaluation of Treated After sterilization of'OSB' Mississippi State University 'OSB' Boards Against Blocks, the blocks will be University Brown Rot Fungi and placed in fungi to determine White Rot Fungi the biocide toxic threshold level.

1519 Dunkl University of Fission Track Analysis of Fission track dating method University of Tuebingen Apatites on apatites: use of fission Tuebingen tracks from decay ofU-238 and U-235 to determine the cooling age of apatites.

1520 Teaching and Tours Western Oregon Reactor tours Reactor tour and half life USDOE Reactor University experiment. Sharing 1522 Control Room Oregon State General Reactor Operation Reactor operation when no OSU Radiation University other project is involved. Center 1523 Zattin Universita' Degli Fission track analysis of Fission track analysis of Universita' Degli Studi di Bologna apatites apatites. Studi di Bologna 1524 Thomson Ruhr-Universitat Fission track analysis of Fission track analysis of Ruhr-Universitat Bochum apatites and zircon apatites and zircon. Bochum INAA = Instrumental Neutron Activation Analysis REE = Rare Earth Elements Work VI- 26

Table VI.C.3 Listing of Major Research and Service Projects Performed or In Progress at the Radiation Center and their Funding Agencies Project Users Organization Name Project Title Description Funding 1525 Teaching and Tours- Life Gate High Productioriof Al for TI/2' Tour of OSTR. USDOE Reactor School lab Sharing 1526 Crawford Hot Cell Services Instrument calibration Calibration of radiation Hot Cell Services detectors.

1527 Teaching and Tours Oregon State Odyssey 'orientation class Introduciion to OSU, USDOE Reactor University including tour of OSU Sharing "RadiationCenter.

1528 Teaching and Tours Oregon State Upward Bound Upward Bound recruitment USDOE Reactor University program for prospective Sharing science and engineering majors.

1529 Teaching and Tours Oregon State OSU Connect Orientation program for new USDOE Reactor University students. Sharing 1530 Teaching and Tours Newport Reactor tour Tour of OSTR. USDOE Reactor Elementary Schools Sharing 1531 Teaching and Tours Central Oregon Reactor tour Tour of OSTR. USDOE Reactor Community Sharing College 1532 Binney Oregon State Development of a Neutron Assistance will be provided University of University Activation Analysis to help the MNRC set up a California Davis Program for the McClellan neutron activation analysis Nuclear Radiation Center program. NAA courses will be taught, software will be developed, and suggestions will be made to implementation of the program.

1533 Teaching and Tours Oregon State Groups or Organizations Tours of OSTR for USDOE Reactor University from Educational individual groups or Sharing Institutions organizations associated with educational institutions other than academic courses.

INAA = Instrumental Neutron Activation Analysis REE = Rare Earth Elements Work VI- 27

Table VI.C.3 Listing of Major Research and Service Projects Performed or In Progress at the Radiation Center and their Funding Agencies Project Users Organization Name - Project Title - Description Funding 1534 Teaching and Tours Oregon State Student Recruitment Tours Reactor tours for the purpose USDOE Reactor University of student recruitment into Sharing OSU academic programs.

1535 Teaching and Tours Corvallis School Center for Alternative Reactor tours. USDOE Reactor District Learning tours Sharing 1536 Nuclear Oregon State Gamma Irradiations for Irradiation of samples for OSU Radiation Engineering Faculty University NEIRHP 114/115/116 Introduction to Nuclear Center Engineering and Radiation Health Physics courses NE/RHP 114/115/116.

1537 Teaching and Tours Oregon State Naval Science tours Tour of OSTR by Naval USDOE Reactor University Science classes. Sharing 1538 Teaching and Tours Oregon State OSTR tours Tour of the OSTR. USDOE Reactor University Sharing 1539 Most Universitat Fission track studies Age dating by the fission Universitat Tubingen track method. Tubingen 1540 Teaching and Tours McKay High Reactor Tours Tour of the OSTR. USDOE Reactor School Sharing 1541 Teaching and Tours Crescent Valley Reactor Tours Tour of OSTR. USDOE Reactor High School Sharing 1542 Teaching and Tours Oregon State OSTR tours for Tours of the OSTR. USDOE Reactor University Engineering Sciences Sharing classes 1543 Bailey Veterinary Instrument Calibration Calibration of radiation Veterinary Diagnostic detection instrumentation. Diagnostic Imaging & Imaging &

Cytopathology Cytopathology 1544 Teaching and Tours West Albany High Reactor tours and Tour of the OSTR and half USDOE Reactor School experiments life experiment. Sharing INAA = Instrumental Neutron Activation Analysis REE = Rare Earth Elements Work VI- 28

Table VI.C.3 Listing of Major Research and Service Projects Performed or In Progress "atthe Radiation Center and their Funding Agencies Project - Users Organization Name Project Title - Description Funding 1545 Teaching and Tours Oregon State OSTR Tours Tours of the OSTR. - USDOE Reactor University - Sharing 1546 Istok Oregon State Elimination of Gamma irradiation to OSU Civil, University microorganism activity in eliminate microorganism Constr., and groundwater activity in groundwater Environmental samples. Engineering 1547 Poklemba U.S. Department' Mutations in lolium Mutations in lolium Agricultural of Agriculture tenulentum tenulentum ( "Ceres") to Research Service flowering affect flowering.

1548 Teaching and Tours Willamette Valley Reactor tours and Tour of the OSTR. USDOE Reactor Community School experiments Sharing 1549 Giovannoni Oregon State Irradiation of Vivaspin Gamma irradiation of OSU University concentrators Vivaspin concentrators to Microbiology destroy any contaminating Department DNA.

1551 Rizo Tru-Tec Production of high-activity Production of Na-24 and Tru-Tec solid radionuclides other solid high activity radionuclides.

1552 Higley Oregon State Radioecology Experiment Measurement of radionuclide USDOE Reactor University for RHP 488/588 transport in an aquatic Sharing environment.

1553 Hemming Columbia Provenance of Long Island Dating of single grain USDOE Reactor University Loess Muscovite and biotite in Sharing Long Island loess by Ar/Ar method and correlating mica "i- ages with possible hinterland.

1554 Fleischer Union College Fission Track Irradiations USDOE Reactor Sharing INAA = Instrumental Neutron Activation Analysis REE = Rare Earth Elements Work VI - 29

Table VI.C.3 Listing of Major Research and Service Projects Performed or In Progress at the Radiation Center and their Funding Agencies Project Users Organization Name Project Title Description Funding 1555 Fitzgerald Syracuse University Fission track Irradiation to induce U-235 Syracuse thermochronology fission for fission track University thermal history dating, especially for hydrocarbon exploration. The main thrust is towards tectonics, in particular the uplift and formation of mountain ranges.

1556 Karchesy Oregon State Determination of chlorine The objective of this study is USDOE Reactor University in wood products to determine the Sharing concentration of chlorine in plywood products.

1557 Garver Union College Fission Track Age Dating Use'of fission tracks from U- USDOE Reactor 235 to determine the location Sharing and concentration of U-238 in zircon crystals to determine the fission track age of unknown samples.

1558 Binney Oregon State Measurement of cross Irradiations to measure USDOE University sections for medical neutron cross sections for radionuclides medically important radionuclides.

1559 Fodor North Carolina Petrochemistry of gabbros Analysis of gabbro and USDOE Reactor State University and basalts from the basalt samples from Mauna Sharing Mauna Loa volcano, Loa volcano in Hawaii.

Hawaii 1560 Enochs Oregon State Assessment of Age Dating Chemical analyses of USDOE Reactor University Potential of Petrified Wood petrified wood samples from Sharing Ashwood Oregon. The objective of this project is to determine potassium and uranium in order to evaluate possible radiometric methods for absolute dating.

INAA = Instrumental Neutron Activation Analysis REE = Rare Earth Elements Work VI- 30

Table VI.C.3 Listing of Major Research and Service Projects Performed or In Progress at the Radiation Center' and'their-Fundinig Agencies Project Users Organization Name . Project Title Description -. Funding 1561 Hertel Georgia Institute Comparison of response Comparison of the response USDOE Reactor of Technology of tissue equivalent ion of a tissue equivalent ion Sharing chambers chamber with a boron-loaded tissue equivalent ion chamber.

1562 Mueller University of Evolution of continental Trace element analyses USDOE Reactor Florida crust in the northern along with internally Sharing Wyoming province generated isotopic and major, element analyses to understanding the evolution of continental crust in the northern Wyoming province.

1563 Jones Xerox Corporation Xerox stainless steel INAA of stainless steel used Xerox

• analysis in Xerox Corporation print Corporation, head manufacturing. Wilsonville 1564 Krane Oregon State Measurement of Tb-160 Measurement of Tb-160 USDOE Reactor University neutron capture cross neutron capture cross section Sharing section by irradiation of Tb-159 to produce Tb-161.

1565 Tollo George Petrology and NAA for petrologic study of USDOE Reactor Washington geochemistry of granitoids and gneisses from Sharing University Mesoproterozoic the basement core of the basement, Blue Ridge Blue Ridge anticlinorium in Province, VA northern VA.

1566 Dolan Oregon State Irradiation of soil cores to Irradiation of asceptically OSU Civil, University degrade chlorinated acquired soil cores from an Constr., and solvents in situ treatment process site Environmental to degrade chlorinated Engineering solvents.

1567 Johnson University of Compositions of apatites Study of chemical USDOE Reactor Houston from magnetite-rich composition of apatites from Sharing segregation deposits in the magnetite deposits in Cornucopia stock, NE Cornucopia stock to Oregon determine processes responsible for their genesis.

INAA = Instrumental Neutron Activation Analysis REE = Rare Earth Elements Work VI- 31

Table VI.C.3 Listing of Major Research and Service Projects Performed or In Progress at the Radiation Center and their Funding Agencies Project Users Organization Name Project Title Description - Funding 1568 Spell University of Ar/Ar dating of rocks and Irradiation of rocks and University of Nevada Las Vegas minerals minerals for Ar/Ar dating to Nevada Las determine eruption ages, Vegas emplacement histories, and provenances studies.

1569 Barrett PCC Structurals, Investigation of voids in INAA to determine the PCC Structurals, Inc. titanium composition of voids in Inc.

titanium ingots 1570 Jacobsen International Analysis of titanium Analysis of titanium samples International Titanium Powder samples for chlorine and sodium Titanium Powder 1571 Hansen Geological Institute Fission track analysis Study of East Greenland Geological contionental margin to Institute determine thermotectonic evolution as an aid in understanding rifling and opening of a continental volcanic margin with formation of a new ocean.

1572 Wheatcroft Oregon State Uranium Ore Counting on Counting uranium ore OSU COAS University a HPGe samples to determine the activity of different isotopes.

1573 Baxter California Institute Ar partitioning experiments Measurement of the California of Technology partitioning of noble gases Institute of between crystals and grain Technology boundaries.

1574 Lampi Osmotek Stenlization of Nutrients Sterilization of hydration Osmotek bags containing nutrients.

1575 Staton GlaxoSmithKline Production of Sm-153 Production of Sm-153 for GlaxoSmithKline use as a radiopharmaceutical.

1577 Li Wayne State The study of antibacterial To evaluate the anti-infective Wayne State University activity in penile implant efficacy of antibiotic-coated University animal model bioflex strips as a surrogate for the penile prosthesis.

INAA = Instrumental Neutron Activation Analysis REE = Rare Earth Elements Work VI- 32

TableVI.C.3 Listing of Major Research and Service Projects Performed or In Progress at the Radiation Center and their Funding Agencies Project - Users Organization Name -Project Title . . Description . Funding 1578 Monie . University of Fission Track-Analysis of 'Use of fission tracks from U- University of Montpellier U-235 235 to deternri`ie the Montpellier uranium content in minerals.

1579 Leisy Oregon State Evaluation of Bacillus Fish will be immunized with OSU University spores as an immunogen in Bacillus subtilis spores and Microbiology rainbow trout challenged with virulent Department

.. infectious hematopoietic necrosis virus (IHNV) to test for immunization against IHNV. All experiments will be conducted at the OSU Salmon Disease Laboratory.

1580 Keszler Oregon State Analysis of tourmaline INAA of a tourmaline crystal. USDOE Reactor University Sharing 1581 Thompson Philomath High Short Activation Analysis Short activation analysis of USDOE Reactor School of Peat peat samples from Sharing Wils6fiville.

1582 Madson Double Hat Gemstone irradiation Irradiation of gemstones to Stacey Madson Enterprises produce color change.

1583 Teaching and Tours Neahkahnie High Reacior tours Tour of OSTR. USDOE Reactor School Sharing 1584 Teaching and Tours Reed College Tours for Reactor Staff Tours for Reed College USDOE Reactor reactor staff and trainees. Sharing 1585 Krane Oregon State Measurement of Yttrium Measurement of the Y-91 USDOE Reactor University Cross Sections cross section by neutron Sharing activation.

1586 Krane Oregon State Measurement of Sulfur Measurement of S-37 cross USDOE Reactor University -Cross Sections section by neutron activation. Sharing 1587 Poniar Oregon State Trace metals analysis of Determination of trace USDOE Reactor University amber metals in amber for Sharing identification of origin point INAA = Instrumental Neutron Activation Analysis REE = Rare Earth Elements Work VI- 33

Table VI.C.3 Listing of Major Research and Service Projects Performed or In Progress at the Radiation Center and their Funding Agencies Project Users Organization Name Project Title Description Funding 1588 Hughes Idaho State NAA Series 02-03 Thesis research under GEOL USDOE Reactor University 650 for MS degree. Kaleb Sharing Scarberry.

1589 Higley Oregon State Scan Efficiency Production of a Rb-86 USDOE Reactor University Calibration Factor calibration source that is Sharing Determination Using a Rb- used in the determination of 86 Point Source scanning detection efficiency for area sources.

1590 Slavens USDOE Albany Determination of Uranium Determination of natural USDOE Albany Research Center & Thorium Content in uranium, thorium, and Research Center Tech Norm radium in slurry waste from former zirconium metals processing. Purpose is to determine waste characterization.

1591 Guzzi Guzzi Dental Analysis of Dental Alloy The trace element Gianpaolo Guzzi Services concentration of dental amalgam powder is determined by INAA.

1592 Burgess University of Ar-Ar dating of Icelandic Nuclear irradiation of rock University of Manchester rhyolites chips in cadmium-lined Manchester irradiation facility for Ar-Ar dating studies of Icelandic rhyohtes.

1593 Higley Oregon State Irradiation of Hamster Cells Irradiation of hamster OSU Radiation University ovarian cells that have the Center SIP molecule incorporated into them to test for increased radioprotection of the cells.

1594 Teaching and Tours Jefferson High OSTR tours Tour of the OSTR and half USDOE Reactor School life experiment. Sharing 1595 Rahn Albert-Ludwigs- Fission Track Dating of the Dating of the shoulder uplift German Science Universitaet Mid-European Rhine along the Mid-European Foundation Graben Shoulder Rhine graben shoulders by the fission track technique.

INAA = Instrumental Neutron Activation Analysis REE = Rare Earth Elements Work VI- 34

Table VI.C.3 Listing of Major Research and Service Projects Performed or In Progress at the Radiation Center and their' Funding Agencies Project - Users Organization Name .Project Title - Description Funding 1596 Roeske University of Geochemistry of -Determination of the trace USDOE Reactor California at Davis clinopyroxene and whole element composition of Sharing rock samples, Brooks clinopyroxene and whole Range, Alaska rock samples of a high grade metamorphic terrane near the Brooks Range, Alaska.

1597 Reese Oregon State Neutron Radiography Neutron radiography of Precision University airplane components and Castparts Corp.

related material.

1598 Loveland Oregon State QSAR of organically Measurement of OSU Chemistry University bound metals octanol/water partition Department coefficients for a series of chemically related organically bound metals.

1599 Minc University of NAA of Iridium Solution Determination of iridium University of Michigan content in solution through Michigan NAA. Samples also contain Na, Br, and Cu.

1600 Walker Wheeler County Lead Bullet Analysis 1994 Homicide OSP Case Wheeler County, Sheriffs Office No. 94-182466,7 mm Oregon bullets, Bend OSP Officer Rob Ringsage. Original project # 1089. Two new bullets to be compared to 10890 1a, b, c (from spine of victim) OSP 94P-566.

1601 Crutchley Josephine County Instrument Calibrations Calibration of instruments. Josephine County Public Works 1602 Kirsch Crescent Valley Advanced placement This project supports the USDOE Reactor High School physics class support advanced placement physics Sharing class at Cresent Valley High School. It will utilize the reactor for an investigation of arsenic concentrations in soils and bedrock of the Sweet Home area.

INAA = Instrumental Neutron Activation Analysis REE = Rare Earth Elements Work VI- 35

Table VI.C.3 Listing of Major Research and Service Projects Performed or In Progress at the Radiation Center and their Funding Agencies Project Users Organization Name Project Title Description Funding 1603 Teaching and Tours Thurston High Reactor tours Tour of OSTR. USDOE Reactor School Sharing 1604 Buckovic Geovic Ltd. Support of Cobalt-Nickel Analysis of Co/Ni in soil Geovic, Ltd.

Laterite Analyses samples from Africa.

1605 Roden-Tice Plattsburgh State Timing of Movement on Determination if an offset in USDOE Reactor University the Norumbega Fault apatite fission track ages Sharing System in Southern Maine exists along the Norumbega fault in southern Maine.

1606 McGuire Oregon State Sterilization of Nisin Exploration'of effect of OSU Radiation University Coated Medical Devices several commericially Center available sterilization methods on activity of adsorbed nisin, an antimicrobial peptide.

Sterilization by ethylene oxide, high temperature, high pressure, and irradition are being investigated.

1607 Struzik Polish Academy of Timing of uplift and Determination of timing of Polish Academy Sciences exhumation of Polish uplift and exhumation of of Sciences Western Carpathians Polish Western Carpathians (Tatra Mts. and Podhale Flysch) using AFT methods to verify paleotemperature, which are determined by illite-smectite methods.

Reconstruction of thermal history.

1608 Sivaramakrishnan Oregon State Radiation Effects on Determination of neutron USDOE Reactor University Gallium Arsenide irradiation effects on Sharing semiconductors, particularly gallium arsenide.

INAA = Instrumental Neutron Activation Analysis REE = Rare Earth Elements Work VI- 36

Table VI.C.3 Listing of Major Research and Service Projects Performed or In Progress at the Radiation Center and their Funding Agencies Project -Users Organization Name - Project Title Description Funding 1609- Loveland Oregon State Time-Resolved Laser Photophysic determination OSU Chemistry University' 'Spectroscopy of olgomeric components of Department DNA; use of luminescence spectroscopy to investigate

- -the speciation of uranyl ions in aqueous systems.

1610 Gans University of Ar-Ar geochronology Age dating of volcanic and USDOE Reactor California at Santa plutonic rocks from Sonora, Sharing Barbara Mexico to determine the timing and magnitude of crustal extension prior to and during the opening of the Gulf of California.

1611 Teaching and Tours Grants Pass High OSTR tours Tour of OSTR. USDOE Reactor School Sharing 1612 Singer University of Determination of age of Determination of age of USDOE Reactor Wisconsin Eocene and Quaternary Eocene and Quaternary Sharing volcanic rocks volcanic rocks by production of Ar-39 from K-39.

1613 Teaching and Tours Silver Falls School OSTR tour Tour of Radiation Center USDOE Reactor District and OSTR. Sharing 1614 Mosier Marist High School OSTR tours Tour of the OSTR. USDOE Reactor Sharing 1615 Teaching and Tours Liberty Christian OSTR tours Half life experiment and tour. USDOE Reactor High School Sharing 1616 Doyle Evanite Fiber Instrument Calibration Calibration of radiological Evanite Fiber Corporation instruments Corporation 1618 Teaching and Tours Fall City High Tour of OSTR Tour of OSTR and half life USDOE Reactor School experiment. Sharing 1619 Teaching and Tours Sheridan School Tour of OSTR Tour of OSTR and half life USDOE Reactor District experiment. Sharing INAA = Instrumental Neutron Activation Analysis REE = Rare Earth Elements Work VI- 37

Table VI.C.3 Listing of Major Research and Service Projects Performed or In Progress at the Radiation Center and their Funding Agencies Project Users Organization Name Project Title Description Funding 1620 Teaching and Tours Eddyville High Tour of OSTR Tour of OSTR and APEX. USDOE Reactor School Sharing 1621 Foster University of Irradiation for Ar/Ar Ar/Ar analysis of geological University of Florida Analysis samples. Florida 1622 Reese Oregon State Flux Measurements of Measurement of neutron flux OSU Radiation University OSTR in various irradiation Center facilities.

INAA = Instrumental Neutron Activation Analysis REE = Rare Earth Elements Work VI- 38

Table VI.C.4 Summary of the Types of Radiological Instriumentation Calibrated to Support the OSU TRIGA Reactor and the Radiation Center Type of Instrument Number of Calibrations Alpha Detectors 3 GM Detectors 39 Ion Chambers 10 Micro-R Meters 3 Personal Dosimeters 48 TOTAL 103 Work VI- 39

Table VI.C.5 Summary of Radiological Instrumentation Calibrated to Support Other OSU Departments and Other Agencies Department/Agency Number of Calibrations OST Departments Ammal Science 4 Biochemistry/Biophysics 7 Botany and Plant Pathology 6 Center for Gene Research I Civil, Construction and Environmental Engineering 2 Crop Science 2 Electrical and Chemical Engineering I EMT. 6 Exercise and Sport Science I Fisheries and Wildlife I Food Science 2 Forest Science 3 Horticulture 2 Linus Pauling Institute 2 Microbiology 6 Oceanic and Atmospheric Sciences I Pharmacy 4 Physics 5 Radiation Safety 16 R/V Wecoma I Vetennary Medicine 8 Zooloy 2 OSU Departments Total 83 Non-OSU Agencies Army Corps of Engineers 2 AVI Biopharma 1 ESCO Corporation 6 Evanite Fiber Corp I Federal Aviation Administration 5 Good Samaritan Hospital 7 Hot Cell Services 4 Josephine County Public Works I Kimer Consulting I Occupational Health Laboratory 1 Oregon Office of Energy 31 Oregon Department of Transportation 1 Oregon Health Sciences University 22 Oregon Public Utilities Commission 5 Oregon State Health Division 58 Rogue Community College I USDA Agricultural Research Service I U S Environmental Protection Agency 5 Valley Landfills, Inc 2 Veterinary Diagnostic Imaging Cytopathology I Non-OSH Agencies Total 153 Work VI- 40

Table VI.F.1 Summary of Visitors to the Radiation Center Date - No. of Visitors Name of Group 7/6/2001 1 Laura Wendling 7/6/2001 5 Peterson Family 7/12/2001 19 Adventures in Learning 7/17/2001 16 Adventures in Learning 7/17/2001 12 LBCC Science, Technology and Society 7/17/2001 8 Advisory Committee on Reactor Safeguards 7/18/2001 3 Daniel's Family 7/20/2001 10 OSU GEO 300 Environmental Conservation 7/25/2001 3 Melanie Marshall and Hank and Janice Schvette 7/26/2001 1 Geovic Ltd., Dr. Mark Rose 7/27/2001 10 Mike Cloughesy Friends and Family 8/22/2001 4 Research Showcase with Jim Johnson 8/22/2001 12 REU Physics 8/27/2001 3 Don Peterson's Family 8/29/2001 3 Glaxo-Smith Klein Visitors 9/17/2001 1 Alex Plionis 9/18/2001 9 New Graduate Students 9/20/2001 10 OSU Connect Students 10/4/2001 1 Joe Karchesy 10/5/2001 2 Gail Matheson; photographer 10/8/2001 10 NE 451/551 class 10/8/2001 10 OSU Nuclear Engineering 114 10/10/2001 10 OSU Nuclear Engineering 114 Work VI- 41

Table VI.F.1 Summary of Visitors to the Radiation Center Date No. of Visitors Name of Group 10/15/2001 2 Dan Keuter, Dan Denver: NE Advisory Board 10/15/2001 1 Mike Matthews from Varian Technology 10/18/2001 22 COCC Engineering 111 10/25/2001 14 LBCC GS 105 -J 10/25/2001 9 LBCC GS 105 10/26/2001 60 Alumni Tour of ATHRL 11/2/2001 2 George Hedges and Ken Spitzer from WSU 11/7/2001 6 LBCC GS 105 11/15/2001 1 Rachel Engelbrecht from Central Valley High School 11/29/2001 6 Philomath High School students with parents 12/7/2001 4 Jim Barrett-Precision Castparts 1/10/2002 13 OSU CH 462 1/11/2002 30 Reed College Students 1/22/2002 1 Skip Rung 2/12/2002 15 Nuclear Engineering and Radiation Health Physics 482/582 2/14/2002 20 American Water Works Association s

2/15/2002 15 Nuclear Engineering and Radiation Health Physics 482/582 2/15/2002 3 Napier Family 2/26/2002 9 High School students 2/27/2002 23 General Science 152 2/27/2002 47 Engineering Students from ENGR 331 2/27/2002 28 High School students 3/5/2002 23 OSU CH 222 Work VI- 42

Table VI.F.1 Summary of Visitors to the Radiation Center "Date No. of Visitors Name of Group 3/5/2002 20 OSU CH 222 3/5/2002 20 OSU CH 222 3/5/2002 20 OSU CH 222 3/6/2002 25 OSU CH 222 3/6/2002 19 OSU CH 222 3/7/2002 21 OSU CH 222 3/7/2002 22 OSU CH 222 3/7/2002 21 OSU CH 222 3/7/2002 14 OSU CH 222 3/8/2002 4 John Wood, Paul Schmelzenbach, and W. David Kulp, with Ken' Krane 3/11/2002 1 David Snelling 3/12/2002 21 OSU CH 222' 3/12/2002 18 OSU CH 222 3/12/2002 26 OSU CH 222 3/12/2002 18 OSU CH 222 3/13/2002 24 OSU C-I'222 3/13/2002 19 OSU CH 222.

3/13/2002 1 Magan Do 3/14/2002 23 OSU CH 222 3/14/2002 25 `OSU C1H 222 3/14/2002 24 OSU CcH 222 3/14/2002 23 OSU CH 222 Work VI- 43

Table VI.F.1 Summary of Visitors to the Ra'diation Center Date No. of Visitors Name of Group 3/15/2002 23 Nelly Juarez and SMILE students 3/15/2002 23 Nelly Juarez and SMILE students 3/15/2002 2 Joel and Ryan Kreitzberg 3/18/2002 20 Crescent Valley Engineering Club 3/22/2002 2 Teri Palmer and Phil Gunner 3/22/2002 3 Keller Family 4/3/2002 2 Dr. Morrie Craig -vet med- and one guest 4/4/2002 20 Crescent Valley Physics Class 4/5/2002 23 Nelly Juarez and SMILE students 4/5/2002 10 Nelly Juarez and SMILE students 4/5/2002 23 Nelly Juarez and SMILE students 4/5/2002 10 Nelly Juarez and SMILE students

-. 4 4/9/2002 13 Admissions Office Personnel 4/9/2002 12 Admissions Office Personnel 4/11/2002 24 Thurston High School Students 4/17/2002 16 Nuclear Engineering and Radiation Health Physics 116 5/1/2002 7 Neahkahnie High School 5/4/2002 20 Mom's Weekend 5/8/2002 3 Crescent Valley High School 5/8/2002 3 Crescent Valley High School 5/9/2002 5 Crescent Valley High School 5/9/2002 1 Crescent Valley High School 5/9/2002 1 Crescent Valley High School Work VI- 44

-4

Table VI.F.1 Summary of Visitors to the Radiation Center Date No. of Visitors Name of Group 5/10/2002 3 Crescent Valley High School 5/10/2002 2 Crescent Valley High School 5/10/2002 1 Crescent Valley High School 5/14/2002 24 Marist High School 5/14/2002 24 Marist High School 5/14/2002 7 John Garver and Graduate Students from Union College 5/15/2002 24 Mark Twain Middle School 5/15/2002 5 Scott Hughes and group 5/17/2002 15 LBCC Science, Technology and Society 5/21/2002 15 Liberty Christian High School 5/23/2002 15 Grants Pass High School 5/30/2002 11 Fall City High School 5/31/2002 16 Sheridan High School 6/4/2002 9 Eddyville High School 6/4/2002 13 West Albany High School 6/6/2002 1 Mike Quinn from Computer Science 6/14/2002 4 Andrea Stout, her parents and boyfriend 6/20/2002 3 Corvallis Fire Department 6/27/2002 25 4H group 6/27/2002 16 4H group Total Tours: 111 Total Visitors: 1425 Work VI- 45

Part VII Words

Part VII WORDS A. Documents Published or Accepted for Publication Anderson, R.C., E. Hansen, and J.J. Morrell. 2002. Use of anti-stain chemical treatments by the Western U.S. softwood lumber industry, 1999. Forest Products Journal 52(4):69 71.

• Asfaw, B., H. Gilbert, Y. Beyene, W.K. Hart, P.R. Renne, G. WoldeGabriel, E. Yrba, and T.D. White. 2002. Pleistocene Hominids form Bouri Ethiopia integrate Homo erectus:

Nature 416:317-320.

• Balestrieri, M.L., M. Bernet, M.T. Brandon, V. Picotti, P. Reiners,-and M. Zattin.

Pliocene and Pleistocene exhumation and uplift of two key areas of the Northern Apennines.

Quaternary International, in press.

• Batt, G.E., M.T. Brandon, K.A. Farley, and M. Roden-Tice. 2001. Tectonic synthesis of Olympic Mountains segment of the Cascadia Wedge, using 2-D thermal and kinematic

-modeling of thermochronologic ages. Journal of Geophysical Research. V. 106, Part 11, p.

26, 731-26,746.

• Baxter, E.F., D.J. DePaolo, and P.R. Renne. 2002. Spatially correlated anomalous "4°Ar/ 39Ar "age" variations in biotites about a lithologic contact near Simplon Pass, Switzerland: A mechanistic explanation for "excess Ar": Geochimica et Cosmochimica Acta 66(6):1067-1083.

• Behrensmeyer, A.K., A.L. Deino, A. Hill, J.D. Kingston, and J.J. Sanders.- 2002.

Geology and geochronology of the middle Miocene Kipsaramon site complex, Muruyur Beds, Tugen Hills, Kenya: Journal of Human Evolution 42:11-38.

"*Beland et al., 2001. Fission track'evidence of cooling and exumation of the Wind River Basin, Wyoming. Geological Societyof America Meeting,'Boston, Massachusetts.

• Bernet, M., M. Zattin, J.I. Garver, M. Brandon, and J.A. Vance. 2001. Steady-state

,erosiono6f the European Alps: Geology, 29, 35-38.

• Indicates OSTR use.

Worids VII -I

Bistacchi A., G.V. Dal Piaz, M. Massironi, M. Zattin, and M.L. Balestrieri. 2001. The Aosta-Ranzola extensional fault system and Oligocene-Present evolution of the Austroalpine Penninic wedge in the northwestern Alps. International Journal of Earth Sciences, 90, 654 667.

• Blatter, D.L., I.S.E. Carmichael, A.L. Deino, and P.R. Renne. 2001. Neogene volcanism at the front fo the central Mexican volcanic belt: Basaltic andesite to dacite, with contemporaneous shoshonite and high-TiO 2 lava: Geological Society of America Bulletin 113:1324-1342.

• Busby, C.J., G. Yip, L. Blikra, and P.R. Renne. 2002. Coastal landsliding and catastrophic sedimentation triggered by K/T bolide impact: A Pacific margin example?:

Geology 30:687-690.

Cahill, J., D. Parry, J.J. Morrell and C.S. Love. 2001. Feasibility of locating a pole remanufacturing facility in the mid-Willamette Valley of Western Oregon. In: Proceedings, Western Energy Institute Utility Pole Conference, October 25-26, 2001, Reno, Nevada.

Pages 22-45.

Cavazza W., M. Zattin., B. Ventura. and G.G. Zuffa. Apatite fission-track analysis and Neogene low-temperature thermochronology of northern Corsica (France). Terra Nova, 13, 51-57.

• Davis, L.L., S.S. Hughes, and C. Fleisher. 2001. Characterization of an alkali aluminaborosilicate glass considered for storage of radioactive waste: Environmental Geology, v. 40, n. 7, p. 829-846.

• De Min, A., E.M. Piccirillo, A. Marzoli, G. Bellieni, P.R. Renne, M. Ernesto, and L.S.

Marques. The Central Atlantic Magmatic Province in Brazil: Petrogenesis, 40Ar/39Ar Ages, Paleomagnetism and Geodynamic Implications: American Geophysical Union Monograph, in press.

• Deino, A.L. and A. Hill. 2002. 4 Ar/ 39Ar the Chemeron Formation strata encompassing the site of hominid KNM-BC 1, Tugen Hills, Kenya: Journal of Human Evolution. 42:141 151.

• Deino, A.L., J. Gattacceca, R. Rizzo, and A. Montanari. 2002. 40Ar/39Ar dating and paleomagnetism of the Miocene volcanic succession of Monte Furru (western Sardinia):

Implications for rotation history the Corsica-Sardinia microplate: Geophysical Research Letters 28:17:3373-76.

• Indicates OSTR use.

Words VII -2

4 39

• Deino, A.L. and S.-McBrearty. 2002. °Ar/ Ar dating of the Kapthurin Formation, Barifigo, Kenya: Journal of Human Evolution 42:185-235.

• Deino, A.L., L. Tauxe, M. Monaghan, and A. Hill. 2002 .40Ar/39Ar geochlonology and paleomagnetic stratigraphy of the Lukeino and lower Chemeron Formations at Tabarin and Kapcheberek, Tugen Hills, Kenya: Journal of Human Evolution 42:117-140.

Fayon, A.K., D.L., Whitney, C. Teyssier, J.I. Garver, and Y., Dilek. 2001. Differential exhumation of an Alpine microcontinent, Central Anatolia, Turkey:'Evaluation of rates and mechanisms using FT analysis. Submitted to Earth and Planetary, Science Letters, 192, p.

191-205.

Fleischer, R.L. 2002. Solution and defect hardening. In: Intermetallic Compounds Principles and Practice, v. 3. J.H. Westbrook and R.L. Fleischer, eds., J. Wiley and Sons, Chichester, UK. Chapter 18, p. 351-360. '

Fleischer, R.L. 2002. Ion tracks. In: Intermetallic Compounds- Principles and Practice, v.

3. J.H. Westbrook and R.L. Fleischer, eds., J.Wiley and Sons, Chichester, UK, Chapter 14, p- 263-273.

"*Fleischer, R.L., S. Fujita and M. Hoshi. 2001. Hiroshima neutron fluence at a glass button from near ground zero. Health Physics 81,720-723.

Fleischer, R.L. 2001. Solid state nuclear track detectors: applications. :In: Encyclopedia of Materials Science and Technology. K.H.J. Buschow, R.W. Cahn, M.C. Flemings, B.

Ilschner; E.J. Kramer, and S. Mahajan, eds.,Pergamon Press: P. 8737-8745.

Fleischer, R.L., S.A. Hadley, N.R. Meyer, J. MacDonald, and A. Cavall6o2001. Personal radon dosimetry from eyeglass lenses. Radiation Protection Dosimetry 79, 25 1-258.

"Fleischer,R.L. and R.H. Doremus. 2001. Uncertainties in retrospective radon exposure of glass:-possible effects of water. Health Physics 81,1 0-113.

• Fleischer, R.L. 2002. Serendipitous radiation monitorr. American Scientist. 90(#4), July August, 324-331.

"*Fodor, R.V.,-A.N. Sial, G. Gandhloh. 2002. Petrology of spinel peridolite xenoliths from northeastern Brazil: lithosphere withi a high geotheimal gradient import~d by'Fernando de Noconha plume. Jour. South American Earth Sciences 15:199-214.

• Indicates OSTR use.

" Words VII-3

• Fodor, R.V. 2001. The role of tonolite anid diouls in Mauna Kea volcano, Hawaiin magmatism: petrology of summit- region leucoratic xenoliths. Jour. Petrology 42:1685 1704.

Frietag, C.M. and J.J. Morrell. 2002. Effect of glycol on movement of borate from fused borate rods. Forest Products Journal 52(6):68-74.

• Freitag, C.M. and J.J. Morrell. 2001. Durability of a changing western red cedar resource. Wood and Fiber Science 33:69-75.

• Garver, J.I. 2002. Discussion: "Metamictization of natural zircon: accumulation versus thermal annealing of radioactivity-induced damage." Contributions to Minerology and Petrology. (In press June 2002).

• Garver, J.I. Etching age standards for fission track analysis: a survey of the methodologies used in active laboratories; Radiation Measurements. Submitted July 2001. Re-submitted March 2002. Accepted June 2002.

• Garver, J.I., and P.J.J. Kamp. 2002. Integration of zircon color and zircon fission track zonation patterns in Orogenic belts: Application of the Southern Alps, New Zealand. Special issue of Tectonophysics on: "Low Temperature Thermochronology: From Tectonics to Landscape Evolution". V. 349, n. 1-4, p. 203-219.

• Geist, D., E. Sims, S.S. Hughes, and M. McCurry. 2002. Open-system evolution of a single cycle'of Snake River magmatism, in Link, P.K., and L.L. Mink, eds., Geology, Hydrogeology and environmental Remediation, Idaho National Engineering and Environmental Laboratory, Eastern Snake River Plain: Geological Society of America Special Paper 353, p. 193-204.

• Hansen, K., C.K. Brooks, and S. Bernstein. 2002. Tracking the exhumation history of the East Greenland continental margin north of 72 N. In Barbero, L. and Columbo, F. (eds.)

International Workshop on "Fission-track Analysis: Theory and Applications: El Puerto de Santa Maria (Cadiz) 4-7 June 2002, Geotemas 4, 91-92.

• Hansen, H., A.K. Pedersen, R.A. Duncan, D.K. Bird, C.K. Brooks, J.J. Fawcett, J.

Gittins, M. Gorton, and P. O'day. 2001. Volcanic stratigraphy of the Southern Prinzen of Wales Bjerge region, East Greenland. Geol. Soc. London, Spec. Publication. In Press.

• Helgason, J. and R.A. Duncan. 2001. Glacial-interglacial history of the Skattafell region, .

southeast Iceland, 0-5 Ma. Geology, 29:179-182.

• Indicates OSTR use.

Words VII-4

Houfigan, J.K., A.V. Soloviev, G.V.-Ledneva, J.I. Garver, M.T. Brandon, and P.W.

Reiners. 2002 (in press). Dating of syenite intrusion of the eastern slope of Sredinny Range (Kamchatka): implication for exhumation rate of the accretionary complexes. Geochemistry International.

• Hughes, S.S., P.H. Wetmore, and J.L. Casper. 2002. Evolution of Quaternary tholeiitic basalt eruptive centers on the eastern Snake River Plain, Idaho, in Bonnichsen, B., White, C., and McCurry M., eds., Tectonic and magmatic evolution of the Snake River Plain volcanic province: Idaho Geological Survey Bulletin 30, in press.

• Hughes, S.S. and M. McCurry. 2002. Geochemical evidence for time-space evolution of Snake River Plain rhyolites, in Bonnichsen, B., White, C., and McCurry M., eds., Tectonic and magmatic evolution of the Snake River Plain volcanic province: Idaho Geological Survey Bulletin 30, in press.

• Hughes, S.S., M. McCurry, and D.J. Geist. 2002. Geochemical correlations and implications for the magmatic evolution of basalt flow groups at the Idaho National Engineering and Environmental Laboratory, in Link, P.K., and L.L. Mink, eds., Geology, Hydr6geology and :Environmental Remediation, Idaho Nation'al .Engineering and Environmental Laboratory, Eastern Snake River Plain: Geological Society of America Special Paper 353, 15. 151-173.

• Ingle, S.P., P.A. Mueller, A.L. Heatherington; and M. Kozuch.' Isotopic evidence for the magmratic and tect6oiic histories of the Carolina terraine: implications for stratigraphy and terrane affiliation. Submitted to Journal of Geology, ieviewed and in revision.

J.H. Westbrook and R.L. Fleischer, eds. 2002. Intermetallic Compunds-Principles and Practice. J. Wiley and Sons, Chichester, UK.

• Jun,,B., S. Subramanian, A. Peszalksi. 2001. Neutron- irradiation effects in high electron mobility transition'. IEEE Trans. Nucl. Sci. v. 48; n. 6, p.-2250-2261.

Kirner, N. 2002. Annual ALARA Report f6r ESCO. Submitted to State of Oregon.

Lebow, S., S. LeVan, J.J. Morrell, and N.D. Christofferson. 2002. Assessment of the treatability of small-diameter grand fir posts. Resear'ch Note FPL-RN-0285. U.S.D.A.

Forest Service, Forest Products Labbratory, Madison, Wisconsin. 4 pages.

• Indicates OSTR use.

,Words VII-5

• Lyons, J.O., R.S. Coe, X. Zhao, P.R. Renne, A.Y. Kazansky, A.E. Izokh, L.V.

Kungurtsev, and D.V. Mitrokhin. 2002. Paleomagnetism of the early Triassic Semeitau igneous series, eastern Kazakhstan: Journal of Geophysical Research 107:10.1029/2001JB000521.

• Mahoney, J.J. R.A. Duncan, G.R. McCormick and E. Gnos and W. Khan. 2002.

Cretaceous volcanic rocks of the Southern Tethya Suture Zone, Pakistan: Implications for the reunion hotspot. Earth Planet. Sci. Letts. In Press.

• Marra, F., C. Freda, P. Scarlato, J. Taddeucci, D.B. Karner, P.R. Renne, M. Gaeta, D.M.

Palladino, R. Trigila and G. Cavarretta. 4°Ar/ 39Ar Geochronology and Compositional Features of Young Volcanic Rocks from the Alban Hills Volcanic District (Rome, Italy):

Evidence of Rejuvenation-Volcanism: Bulletin of Volcanology, in press.

• Maughan, L.L., E.H. Christiansen, M.G. Best, C.S. Gromm&, A.L. Deino, and D.G.

Tingey. 2002. The Oligocene Lund Tuff, Great Basin, USA: a very large volume monotonous intermediate: Journal of Volcanology and Geothermal Research 113:129-157.

• Mertz, D.F. A. Weinrich, W.D. Sharp, and P.R. Renne. 2001. Alkaline intrusions in a near-trench setting, Franciscan Complex, California: Constraints from geochemistry, petrology, and 4°Ar/ 39Ar geochronology: American Journal of Science 301(10): 877-911.

Morrell, J.J. 2001. Biodeterioration of wood-based composites and its prevention.

Proceedings International Particleboard Symposium, Washington State University, Pullman, Washington. Pages 17-24.

Morrell, J.J. 2002. Protecting untreated wood from wetting. Proceedings American Wood Preservers Association (in press).

Morrell, J.J. 2001. Remedial treatments for wood poles. In: Proceedings, Western Energy Institute Utility Pole Conference, October 25-26, 2001. Reno, Nevada. Pages97-107.

Morrell, J.J. 2002. Wood-based building components: what have we learned? International Biodeterioration and Biodegradation 49:253-258.

Morrell, J.J. and C.S. Love. 2002. Long term release of chloropicrin in Douglas-fir and western redcedar poles from a controlled release ampule. In: Proceedings 7 th International Conference on Utility Line Structure, March 25-27, 2002, Fort Collins, CO. EDM International, Ft. Collins, Colorado.

• Indicates OSTR use.

Words VII-6

• Morell, J.J., C.S. Love, R.J. Leichti, and R.J. Scott. 2001. Predicting decay rates in structures: the effects of wood moisture content on decay rate. In: Proceedings Second Annual Conference on Durability and Disaster Mitigation in Wood-Frame Housing.

November 6-8, 2000. Madison, WI. Forest Products Society, Madison, WI. Pages 43 49.

• Morrell, J.J., C.S. Love, and C.M.:Freitag. 2002., Preventing discoloration of unseasoned hem-fir and Douglas-fir lumber with selected fungicide formulations. Forest Products Journal 52(2):53-61.

Morrell, J.J. and P.I. Morris. 2002. Methods for improving preservative penetration into wood: a review. International Research group on Wood Preservation Document No.

IRG/WP/02-40227. Stockholm, Sweden 17 pages.

Morrell,.J.J. and R.G. Rhatigan. 2002. Ability of an acoustic inspection device to detect internal voids in untreated pole sections. International Research group on Wood "PreservationDocument No. IRG/WP/02-20246. Stockholm, Sweden 8 pages.

• Morse, L. H. and M. McCurry. 2001. In press. Genesis of alteration of Quaternary basalts within a portion of the eastern Snake River Plain aquifer, in Link, P.K., and L.L.

Mink, eds., Geology, Hydrogeology and Environmental Remediation, Idaho National Enginieering and Environmental Laboiatory, Eastern Snake River Plain: Geological Society of America Special Paper 353, p. 213-224.

"*Mueller,P.A., A.L. Heatherington, D.M: Kelly, J.L. Wooden, and D.W. Mogk. 2002.

"Paleoproterozoiccrust within the Great Falls tectonic: Implications for the assemnbly of southern Laurentia, Geology.'.'

• Peate, D.W., J.A. Baker, J. Blichert-Toft, D.R.ý M. Storey, A.J.R. Kent, C.K.'Brooks, H.

Hansen, A.K. Pedersen and R.A.'Duncan'. 2002. The Prinzen of Wales Bjerge Formation lavas, East Greenland: the transition from tholeiitic to alkali miagmatism during Palaeogene continental break-up. J. Petrol. In press.,,

Reinerss, P.W., T.A. Ehlers, J.I. Garver, S.G. Mitchell, D.P: Montgomery, J:A.'Vance, and S. Nicolescu., In Press (2002). Rapid late Miocene uplift of the Washington Cascades:

Low-temperature thermochronometric evidence. Geology. . .

"*Renne,P.R., W.D. Sharp, I.P.'Montafiez, T.A. Becker and R.A. Zierenberg. 2001.

"Ar/ Ar dating of Late Permian evaporites, southeastern New Mexico, USA: Earth and Planetary Science Letters 193(3/4):539-547.

• Indicates OSTR use.

Words VII -7

Rhatigan, R.G., C.M. Freitag, and J.J. Morrell. 2002. Performance of ammonicacal copper arsenate treated Douglas-fir poles. Proceedings American Wood Preservers Association.

(In Press).

Rhatigan, R.G., C.S. Love, and J.J. Morrell. 2002. Seasonal variations in moisture content of inservice poles in the Willamette Valley. In: Proceedings 7 th International Conference on Utility Line Structures, march 25-27, 2002, Fort Collin, Colorado. EDM International, Ft.

Collins, Colorado. Pages 69-77.

Robbins, C. and J. Morrell. 2002. Mold, housing and wood. Western Wood Products Association, Portland, Oregon. 11 pages.

• Roden-Tice, M.K. In press. Best kept secrets of the Adirondacks and Champlain Valley.

New England Intercollegiate Geological Conference and New York State Geological Association Field Trip Guidebook, Lake George, New York; September 27-29, 2002.

• Roden-Tice, M.KX', and R.P. Wintsch. 2002. Early Cretaceous normal faulting in Southern New England: Evidence from apatite and zircon fission-track ages. The Journal of Geology, v. I10, p. 159-178.

• Shakalov, A., S. Subramanian, and A. Klein. 2001. Correlation between nonionizing energy loss and no offset voltage shift in Ir P-IrAaAs HBIs. IEEE Trans. Nucl. Sci. v. 48, n.

6, p. 2262-2269.

Shapiro, M.N., A.V. Soloviev, J.I. Garver, and M.T. Brandon. 2001. Sources of zircons from Cretaceaous and lower Paleogene terrigenous sequences from the southern Koryak upland and western Kamchatka. Lithology and Mineral Resources, v. 36, n. 4, p. 322-336.

Shapiro, M.N., A.V. Soloviev, E.A. Shcherbinina, Kravchenko-Berezhnoi, and J.I. Garver.

2001. New data on the time of collision of Island Arc with the continent on Kamchatka.

Russian Geology and Geophysics. v. 42, n. 5. Pp. 841-85 1.

Schowalter, T.D. and J.J. Morrell. 2002. Nutritional quality of Douglas-fir wood: effect of vertical and horizontal position on nutrient levels. Wood and Fiber Science 34:158-164.

• Silva, A., C. Freitag, J.J. Morrell. 2001. Effect of fungal attack on creep behavior and strength of wood plastic composites. In: Proceedings, Sixth International Conference on Woodfiber-Plastic Composites, Forest Products Society Proceedings 7251, Madison, WI.

Pages 73-77.

• Indicates OSTR use.

Words VII -8 I

• Simonsen, J., C. Freitag, and J.J. Morrell. 2001. Effect of.wood-plastic ratio on the performance of borate biocides against brown rot fungi. In: Proceedings, Sixth International

- Conference on Woodfiber-Plastic Composites, Forest Products Society,Proceedings 7251, Madison, Wisconsin., Pages 69-72.,.

Soloviev A.V., M.N. Shapiro, J.I. Garver. 2002 (in press) Lesnaya"ttarust, Northern Kamchatka. Geotectonics, n. 6.

Soloviev, AV., M.N. Shapiro, J.I. Garver, E.A. Scherbinina, I.R. Kravchenko-Berezhnoy.

2002. New age data from the Lesnaya Group: a key to understanding the timing of arc continent collision, Kamchatka, Russia. Island Arc, 11 (1), p. 79-90.

Soloviev, A.V",A.V. Lander, T.N. Palechek, G.V. Ledneva,'V.E. Verzhbitsky, D.V.

Kurilov, J.I. Gaiver.'2001. Structure and age of Omgon Ridge complexes', Western Kamchatka. Modem questions of tectonics. Moscow, Scientific' W6rld p. 35-40 (in Russian).

Soloviev, A.V., M.N. Shapiro, and J.I. Gar'ver.'2001. Velocity of collisional thrusting (Lesnaya thrust, Northern Kamchatka). Bull.' Mosk. ObschestvaIspyt. Prir., Otd. Geol. v.

76, n. 5, pp. 29-32 (in Russian).

• Struzik, A.A., M. Zattin, R. Anaxhieuriz. 2002. Timing of uplift and denudation of the Polish Western Carpathians. In! International Workshop on "Fission Track Analysis Theory and Applications," Al Puerto de Santa Maria'(Cadiz). Geotemas, 14:15-754.

• Stuzik,'A.A.,-M. Zattin, and R. Anaxhieuriz2(2002. Apatite fission track analyses from the Polish Western Carpathians. In: Proceedings of the fourth meeIting of the Czech Tectonic Studies Group, Zelamo, Gedines. 14:87-89

• Sweezy, J.E., A. Lennox, and N.E. Hertel. 2002. Paired tissue equivalent ionization chambers for boron enhanced fast neutron therapy. 1 0 thInternational Congress on Neutron Capture Therapy*,NCT Essen 2002, September 8-11, Essen, Germanr,.y.

• Sweezy, J.E., N.E. Hertel, and A. Lennox. 2002. A conceptual design of a filter and collimation'system for boron enhanc~ed fast neutron therapy. Proceedings of the 12' Biennial ANS Radiation Protection'and Shielding Division Topical Meeting. April 14-18, Santa Fe, New Mexico. - "

• Indicates OSTR use.

Words VII -9

• Teixeira, W.', J.P.P. Pinese, M. lacumin, V.A.V. Girardi, E.M. Piccirillo, H., Echeveste, A.

Ribot, R. Fernandez, P.R. Renne and L.M. Heaman. Geochronology of calc-alkaline and tholeiitic dyke swarms of Tandilia, Rio De La Plata Craton, Argentina, and their role in the Paleoproterozoic tectonics of southern South America and African counterpart: Precambrian Research, in press.

• Thomson, S.N. 2002. Late Cenozoic geomorphic and tectonic evolution of the Patagonian Andes between latitudes 420 S and 46' S: An appraisal based on fission-track results from the transpressional intro-arc Liquine-Ofqui fault zone. Geological Society of America, Bulletin. Accepted for publication.'

• Thomson, S.N. F. Herr6, and B. St6ckhet. 2001. The Mesozoic-Cenozoic denudation history of the southern Chiliean Andes and its correlation to different subduction processes.

Tectonics v. 20, n. 5, p. 693-711.

• Tollo, R.P., J.N. Aleinikoff, M.J. Bartholomew, and D.W. Rankin. Late Neoproterozoic A-type granitoids, Blue Ridge Province, Southeast New York to North Carolina: Extension related intraplate magmatism of the Rodinian supercontinent. Submitted to special volume of Precambrian Research on anorogenic granites.

• Tollo, R.P., E.A. Borduas, A.A. Antignano IV, and C.C. Claflin. In press. Bedrock geologic map of the Fletcher 7.5 minute Quadrangle, Greene, Madison, Page, and Rockingham Counties, Virginia: Virginia Division of Mineral Resources; scale 1:24,000.

• Tollo, R.P., E.A. Borduas, and P.C. Hackley. In press. Geology of basement rocks in the Thornton Gap, Old Rag Mountain, and Fletcher quadrangles, Blue Ridge province, Virginia, Virginia Division of Mineral Resources Report.

• Ukstins, I.A., P.R. Renne, E. Wolfenden, J. Baker, M. Menzies, and D. Aleyew. 2002.

Matching conjugate'volcanic margins: 4°Ar/ 39Ar chionostratigraphy of pre- and syn-rift bimodal flood volcanism in Ethiopia and Yemen: Earth and Planetary Science Letters 198(3/4):289-306.

• Umhoefer, P.J., R.J. Dorsey, S. Willsey, L. Mayer, and P.R. Renne. 2001. Stratigraphy and geochronology of the Comonddi Group near Loreto, Baja California sur, Mexico:

Sedimentary Geology 144(1-2): 125-147.

• Wolf, R.F., H. Xiic, J. Petty, J.S. Teach, and S.A. Pashl. 2002. Argon Ion Besm hemostasis with albumin with liver resection. Amer. Journ. Surg. 183(5):584-587.

• Indicates OSTR use.

Words VII -1

• Wright, K.E., M. McCurry, and S.S. Hughes. 2002. Petrology and geochemistry of the Neogene Tuff of McMullen Creek, central Snake River Plain, in Bonnichsen, B., White, C.,

"andMcCurry M., eds., Tectonic and magmatic evolution of the Snake River Plain volcanic province: Idaho Geological Survey Bulletin 30, in press.

• Zattin, M., V. Picotti., and G.G. Zuffa. Fission-track reconstruction of the front of the northern Apennine thrust wedge and overlying Ligurian unit.-American Journal of Sciences, in press.

- f

• Indicates OSTR use.

Words VII,-1

B. Documents Submitted for Publication Bernet, M., Brandon, M.T., and Garver, J.I. 2002b, Downstream changes in detrital zircon FT cooling ages in large modem rivers, submitted to Journal of Sedimentary Research.

Bernet, M., Brandon, M.T., Garver, J.I., Balestrieri, M.-L., Ventura, B., and Zattin, M.,

2002c, Exhuming the Alps through time: clues from detrital zircon fission-track ages:

Geological Society of America Bulletin,. In review.

Bernet, M., Brandon, M.T., Garver, J.I., and Molitor. Accepted, Testing detrital fission track analysis on modem river sediment of the European Alps; Basin Research, Submitted June 2001.

Bondarenko, G.E., Soloviev, A.V., Tuchkova M.I., Garver J.I., Podgomy, 1.1. 2002. The primary detrital zircon fission-data from Mesozoic flyschof South-Anui sututre (Western Chukotka, NE Asia); DQklady of the Earth Science.

Bullen, M.E., Burbank, D.W., Garver, J.I., and Farley, K.A. In review. Episodic rock uplift of the Kyrgyz Range, Northern Ten Shan. Submitted to Journal of Geology, 6/2002.

• Coffin, M.F., M.S. Pringle, R.A. Duncan, T.P. Gladezenko, M. Storey, R.D. Muller and L.A. Gahagan. 2002. Kerguelen hotspot magma output since 130 Ma. Journal of Petrology.

• Couli6 E., X. Quidelleur, J.C. Lef'evre and P.Y. Gillot. 2002. A multi-collection system for 4

the °Ar/ 39 Ar technique. Submitted to Chemical Geology.

• Couliý E., X. Quidelleur, P.Y. Gillot, V. Courtillot, J.C. Lefevre, and S. Chiesa. 2001.

Combined 4°Ar/39Ar and K/Ar dating of Ethiopian and Yemenite Traps volcanism.

Submitted to Earth Planet. Sci. Lett.

• Duncan, R.A. 2000. A time frame for construction of the Kerguelen Plateau and Broken Ridge. Jounal of Petrology.

• Garver, J.I. Submitted. Etching age standards for fission track analysis: a survey of the methodologies used in active laboratories; Radiation Measurements.

• Heatherington, A.L. and P.A. Mueller. Submitted. Mesozoic igneous activity in the Suwannee Terrane, Southeastern USA. American Geophysical Union Memoir, The Central Atlantic Magmatic Province.

• Heatherington, A.L. and P.A. Mueller. Mesozoic igneous activity in the Suwannee Terrane, Southeastern USA, submitted to American Geophysical Union Memoir, The Central Atlantic Magmatic Province.

• Indicates OSTR use.

Words VII-12

• Hughes, S.S., S.E. Lewis, M.J. Bartholomew, A.K. Sinha, and N. Herz. 2003. Geology and geochemistry of Fe-Ti-rich granitic and chamockitic rocks in the central Lovngston massif of the Grenvillian Blue Ridge terrane, U.S.A.: submitted to R.P. Tollo, L. Corriveau, J.B. McLelland, M.J. Bartholomew, editors, Proterozoic Tectonic Evolution of the Grenville Orogen in Eastern North America.

• Jun, B. and S. Subramanian. Carrier removal and mobility degradation in heterojunction field effect transistor structures. Submitted to IEEE Trans. Nucl. Sci. December 2002.

• Knight, K.B., P.R. Renne, A. Halkett, and N. White. 4°Ar/ 39Ar dating of the Rajahmundry Traps, Eastern India, and their relationship to the Deccan Traps: Earth and Planetary Science Letters, in review.

• Mueller, P.A., J.L. Wooden, A.L. Heatherington, and H.R. Burger. Evidence for Paleoproterozoic Metamorphism in the Tobacco Root Mountains, Montana, submitted to Geology.

• Ravenhurst, C.E., M.K. Roden-Tice, and D.S. Miller. Submitted. Thermal annealing of fission tracks in apatite: experimental results. Canadian Journal of Earth Sciences.

• Ring, M., S.N. Thomson, and M. Br6cker. 2002. Fission-track data supply evidence for fast-slipping extensional detachment in the magmatic arc of the Late Miocene Hellenic subduction zone, Cyclades, Greece. Geology. Submitted for publication, May 2002.

• Thomson, S.N. and F. Herr&. 2002. Integrating detrital zircon fission-track and U-Pb shrimp age to estimate the age of deposition, metamorphism and later reheating of metamorphic complexes at the ancestral Gondwana margin of southern Chile 1420 S-52' S.

Revista Geol6gica de Chile. Submitted for publication April 2002.

• Tollo, R.P., J.N. Aleinikoff, E.A. Borduas, and P.C. Hackley. Petrologic and geochronologic evolution of the Grenville orogen, northern Blue Ridge, Virginia. Submitted to Geological Society of North America Memoir entitled" Proterozoic Tectonic Evolution of the Grenville Orogen in North America", edited by Tollo, R., Corriveau, L., McLelland, J.,

and Bartholomew, M.; publication expected by April 2004.

• Weinstein, J. D. R.V. Fodor, G.R. Bauer. Koolau shield basalt as xenoliths entrained during rejuvenated-stage eruptions: perspectives on magma mixing. Submitted to Bull.

Volcanology.

• Indicates OSTR use.

Words VII -13

• Zattin, M. C. Stefani, and S. Martin. Detrital fission-track analysis and petrographyas keys of Alpine exhumation: the example of the Veneto Foreland (Southern Alps, Italy): Journal of Sedimentary Research, submitted for publication.

• Indicates OSTR use.

Words VII-14

C. Documents in Preparation

• Baxter, A. F., Grain Boundary P~irtitioning of Ar and He. In prepairation. c.

• Bernet, M., M.T. Brandon, J.I. Garver, B. Ventura, M. L. Balestrieri and M. Zattin. 2001.

Exhuming the Alps through time: clues from detrital zircon fission-track ages, GSA Bulletin.

Brandon, M.T., M. Bernet, J.I. Garver, P.W. Reiners, and P.G. Fitzgerald. 2002. Natural calibration of zircon fission-track closure temperature at Gold Butte, Nevada.

• Burton et al.,-in preparation., Thermal history and exhumation of the Okanogan area, Washington State.

• Farrell, J., J.S. MacDonald, M.A. Zalesky, R.L. Fleischer and R. Doremius. Leaching of Imbedded Alpha-Recoil Atoms in Glasses. In preparation.,

Garver, J.I., D.T. Rodbell, and M. Montario. 2002. Climate change drives rapid tectonic exhumation in Cordillera Blanca, Northern Peru. Target submittal: Geology, September 2002.

• Heatherington, A.L. and P.A. Mueller. Crustal sources of the Stone Mountain granite and Elberton batholith, and the origin of the Inner Piedmont terrane. In preparation for submission to Southeastern Geology.

• Heatherington, A.L. and P.A. Mueller. Alleghanian plutonism in the Suwannee terrane. In preparation.

Hourigan, J.K., M.T. Brandon, J.I. Garver, A.V. Soloviev and P.W. Reiners. 2002. A comparison of the detrital zircon grain-age distributions from the Ukelayat Group and Shiktinskaya Complex: Implications for the origin of the Sredinniy Range, Kamchatka.

• Hughes, S.S., D.J. Geist, and M. McCurry. In preparation. Petrogenesis of olivine tholeiites on the eastern Snake River Plain. To be submitted to Journal of Petrology, 2003.

• John, B., J.M. Murphy, and D.L. Foster. In review. Extremely rapid cooling rates in Late Tertiary diabase from the Indian Ocean spreading ridge offshore of South Africa. Apatite and zircon fission track and 4°Ar/39Ar dating results of ODP core samples.

Kirner, N. Annual ALARA Report for ESCO-2002. In preparation.

• MacDonald, J.S. and R.L. Fleischer. Uranium and Thorium in Cores from Two New York State Lakes. In preparation.

• Indicates OSTR use.

Words VII 415

• MacDonald, J.S. and R. L. Fleischer. Neutron Fluence Near Ground Zero at Hiroshima from Nuclear Tracks in Porcelain. In preparation.

Soloviev, A.V., J.I. Garver, M.T. Brandon, and M.N. Shapiro. 2001. Eocene arc-continent collision in northern Kamchatka, Russian Far East. Target submittal: Geology, December 2002.

• Strecker, U., J.M. Murphy and J. Steidtmann. In preparation. Early Tertiary uplift history of the Black Hills, South Dakota, using fission track thermochronology.

• Wetmore, P.H., S.S. Hughes, D.W. Rodgers and S.R. Anderson. In preparation.

Competing processes of s'ulbsideifce and volcanic constriiction during late Pleistocene evolution of the southern Big Lost Trough, Axial Volcanic Zone, and Arco-Big Southern Butte volcanic rift zone.

• Zattin, M. and G.G. Zuffa. Unravelling source rocks of wedge-top and foredeep Late Eocene-Miocne arenites of northern Apennines and southern Alps.

• Indicates OSTR use.

Words VII-16

D. Theses and Student Project Reports

• Bartlett, R. 2002. Measurement of n,n' cross sections of Sn and Pt. Department of Physics, Oregon State University, Corvallis, Oregon.

• Beland, P.E. 2002. Apatite fission track and (U-Th)/He thermochronology and vitrinite reflectance of the Casper Arch, Maverick Springs Dome, and the Wind River Basin:

Implications for Late Cenozoic deformation and cooling in the Wyoming foreland. MS thesis.

Geology Department, University of Wyoming, Laramie, Wyoming, 97p.

• Borduas, E. 2002. Petrologic significance of Grenville-age leucocratic granitoids, Blue Ridge Province, Virginia. BS thesis. George Washington University, Washington, D.C.

• Chen, S. 2001. 'Hydrogeochemical studies of the Portneuf River, Southeastern Idaho: M.S.

Thesis, Idaho State University, Pocatello, Idaho. 134p.

• Couli6, E. 2001. Chronologie 4°Ar/ 39Ar et K/Ar de la d~chirure continentale en Afar depuis 30 Ma, Doctoral Dissertation, Universit6 Paris sud, Orsay, 380p.

Johnston, S.J. 2002. Zircon fission-track cooling ages of the Sredinniy Range metamorphic complexes, Kamchatka: Implications for post Orogenic exhumation. Department of Geology, Union College, Schenectady, NY. 77p.

• Jun. B. July 2002. Radiation effects in IJI-IV heterostructure devices. Doctoral Dissertation. Oregon State University. Corvallis, Oregon.

• MacDonald, J.S., 2002. Fission and alpha track etching techniques for measuring uranium and thorium concentrations in core samples from Ballston and Quichy Lakes, and sedimentation rates from near-surface decay of radon progeny. BS thesis. Union College, Schenectady, New York.

Mankowski, M.N. 2002. Biology of carpenter ants Camponotus vicinus (Mayr) and Camponotusmodoc (Wheeler) in western Oregon. Doctoral Dissertation, Oregon State University, Corvallis, Oregon.

• McCarther, R.L. 2002. Compositional evolution and crystallization of a prehistoric Mokuaweoweo lava lake, Mauna Loa volcano, Hawaii: petrology fo gabbroic xenoliths. MS thesis. North Carolina State University, Raleigh, North Carolina. 95p.

• Min, K. Improved Calibration and Applications of the 4°Ar/39Ar Dating Method. Doctoral Dissertation. University of California at Berkeley, Berkeley, California. Filed.

• Indicates OSTR use.

Words VII-17

• Rosenstein, D. 2002. Ceramic production as a reflection of technological and social complexity in the Late Iron Age of South Africa: an ethnographic and petrographic study. BA thesis. George Washington University, Washington, D.C.

• Struzik, A.A. Comparison of thermal evolution recorded by the Uite-smeolite and AFT in the Polish Western Carpathians" MS thesis. Institute of Geological Sciences, Polish Academy of Sciences, Seacha 1-81-002, Krakow, Poland.

• Sweezy, J.E., Devel6pment of a boron neutron capture enhanced fast neutron therapy beam.

PhD Thesis. Nuclear Engineering, Georgia Institute of Technology, March 2002.

Wilson, J. 2002. The effect of sterilization method on the activity of surface-bound nisin.

Honors thesis. Bioengineering Department, Oregon State University, Corvallis, Oregon.

• Indicates OSTR use.

Words VII-18

E.. Presentations

• Abbate, E., M.L. Balestrieri, G. Bigazzi; M. Brandon, V. Picotti, P. Reiners, M. Zattin, and G.G. Zuffa. 2001. -Space and time variability of exhumation in N6rthern Apennines.

Workshop "Uplift and erosion: driving processes and resulting landforms:, Certosa di Pontignano (Italy), September 20-21.

• Balestrieri,rM.L.; and M. Zattin. 2002. Exhumation of the Northern Apennine chain: do we "needsomething more than apatite fission-track data? International Workshop on "Fission track Analysis: theory and applications", El'Puerto de Santa Maria (Spain), June 4-7.

• Baxter, Asimo;v, Farley. 2001. Experimental Study of Graif Boundary Partitioning of Ar.

AGU 2001 Fall Meeting, San Francisco, California.

• Beland, et al., 2001. Fission track evidence of cooling and 'exhiumation of the Wind River Basin, Wyoming. Geological Society of America Annual Meeting, Boston, Massachusetts.

• Brandon, M. E. Abbate, M.L. Balestrieri, M. Bernet, G. Bigazzi, V. Picotti, P. Reiners, M.

Zattin and G.G. Zuffa. 2001. Quantifying exhumation history across the Northern Apennines.

"AGU2001 Fall Meeting, San Francisco,-10-14 December 2001L

"*Chiarenzelli,J., M. Roden-Tice. 2002. History and tectonic evolution of the Sask Craton, Trans-Hudson Orogen. Saskatoon 2002 Proceedings. Geological Association of Canada.

May 24, 2002.

"*Deford, D. 2001. Vascular angstomosis using a pulse diode laser. SPIE, San Jose, California.

• Fellin, M.G., V. Picotti and M. Zattin. 2002. Late Quaternary compression revealed by surface faults at the western margin of Corsica basin. EGS 2002 Annual Meeting, Nice, April S21-26.,

"*Ga~rv5 , J.I., AV. Soloviev, M.T. Brandon, M.N. Shapiro, and J.K, Hourigan.'2001.

Tectonic and magmatic history 6f Kamchatka and NE Asii revealed through detrital zircon thermochronology of Cretaceous to Miocene deep-water strata, Kamchatka (Russia). 7 th Zoneshain International Conference on plate tectonics, Moscow, Russia, p. 503.

• Garver, J.I., B.C.D. Riley and G.Wang. 2002.: Partial resetting of-fission tracks in detrital zircon, European Fission-tra'ck conference, Cadiz, Spain, Geotemas, v.4, p.73-75.

• Indicates OSTR use.

Words VII-19

• Hansen, K. C.K. Brooks and S. Bernstein. 2002. Tracking the exhumation history of the East Greenland continental margin north of 72 N. In Barbero, L. and Colombo, F. eds.,

International Workshop on "Fission-track Analysis: Theory and Applications" El Puerto de Santa Maria (Cadiz) 4-7 June 2002, Geotemas 4, 91-92.

Hourigan. J.K., M.T. Brandon, J.I. Garver, and A.V. Soloviev. 2001. A comparison of the detrital zircon grain-age distributions from the Ukelayat Group and the Kamchatsky Complex:

implications for the origin of the Sredinniy Range, Kamchatka. 7t' Zoneshain International Conference on plate tectonics, Moscow, Russia, p.504.

• Hughes, S.S., and M. McCurry. 2002. Geochemical diversity of Quaternary olivine tholeiites on the eastern Snake River Plain: Geological Society of America Abstracts with Programs vol. 34, no. 5.

• Hughes, S.S., and M. McCurry. 2002. Geochemistry of Precambrian charnockitic rocks of the central Lovingston massif, Grenvillian Blue Ridge Terrane, Virginia: Geological Society of America Abstracts with Programs vol. 33, No. 6, p. A-28.

• Hughes, S.S., S.E.H. Sakimoto, and T.K.P. Gregg. 2002. Plains volcanism in the eastern Snake River Plain: Quantitative measurements of petrologic contributions to topography with comparisons to Mars: Geological Society of America Abstracts with Programs vol. 34, No.

6.

Ledneva, G.V., J.1., Garver, J.R. Lederer, M.N. Shapiro, M.T. Brandon and K. Hollocher.

2001. Geochemistry and FT ages of felsic cobbles in Oligocene flysch and m6lange (Karaginski Island, Kamchatka, Russian Far East): implications for reconstruction of post collisional paleogeology. 7 th Zoneshain International Conference on plate tectonics, Moscow, Russia, p. 509-5 10.

• MacDonald, J.S., and R.L. Fleischer. 2002. Neutron fluence near ground zero at Hiroshima from nuclear tracks in porcelain. Northeastern Section Meeting, Geological Society of America, Springfield, Massachusetts, March 25-27.

• McCurry, M. and K. Schmidt. 2001. Petrology and oxygen isotope geochemistry of the Puc6n Ignimbnite -Southern Andean Volcanic Zone, Chile: Implications for genesis of mafic ignimbrites, III South American Symposium on Isotope Geology, Extended Abstracts Volume (CD), p. 317-320, Sociedad Geol6gica de Chile, Santiago, Chile.

• Indicates OSTR use.

Words VII -20

• Roden-Tice, M.K., S.J. Tice, R.P. Wintsch and K.A: Farley. 2001. Evidence for 4-ridespread early Cretaceous unroofing in the southeastern Adirondacks, Champlain Valley and Vermont based on'apatite fission-track ages. 'Geological Society of America Abstracts with Programs, v. 33, p. A-82, Annual Meeting of the Geological Society of America, November 1-10, 2001, Boston, Massachusetts.

• Scarberry, K., S., Hughes, and M. McCurry. 2002. Geochemistry, stratigraphy, and petrogenetic implications of the F basalt flow group, eastern Snake River Plain, Idaho:

Geological Society of America Abstracts with Programs Vol. 34, No. 5.

Shoemaker, S.,,M. Ducca, P.W. Reiners,;J.I.Garver, and M.F. Campa. 2002. Cenozoic plate tectonic history of southwestern Mexico; constraints from low temperature thermochronology, European Fission-track conference, Cadiz, Spain, Geotemas, v. 4, p.

137-138.

Soloviev, A.V. and J.I. Garver. 2002. Fision-track study of the Omgon accretionary complex, Western Kamchatka (Russian Far East): possible northern continuation of the Shimanto belt (Japan); European Fission-track conference, Cadiz, Spain, Geotemas, v.4, p.

143-146.

Solovie'V, A.V., J.I. Garver, M.T.:Brandon. 2001. Dating terrigenious sediments by zircon fission-track (ZFT) thermochronology. 7th Zoneshain International Conference on plate tectonics, Moscow, Russia, p. 515.

Soloviev A.V., M.N. Shapiro, and J.I. Garver. 2001; Estimation of the forming speed of the collision thrust by isotopic dating (Lesnaya thrust, Northern Kamchatka) Tectonics: general and regional questions. Moscow. February 1-4, 2001. V.2. p. 211-214. (In Russian).

"*Stahle,*K.A., M.C.'Young, and M:K. Roden-Tice. 2002. Mesozoic unroofing history of Eastern New York and Western New England based on apatite fission-track ages.

Geological Society of America Abstracts with Programs, v. 34, p. A-69.

• Struzik, A.A., M. Zattin and R. Anczkiewicz. 2002. Timing of uplift and exhumation of the Polish Western Carpathians. International Workshop on "Fission-track Analysis: theory and applications", El Puerto de Santa Maria (Spain), June 4-7.

• Subramanian, S. Radiation effects in III-V heterostructure devices. Seminar. University of California at Berkeley. October 2001.

• Indicates OSTR use.

Words VII -21

• Sweezy, J.E., N.E. Hertel and A. Lennox. 2002. A conceptual design of a filter and collimation system for boron enhanced fast neutron therapy. Proceedings of the 12' biennial ANS Radiation Protection and Shielding Division Topical Meeting. April 14-18, Santa Fe, New Mexico.

• Sweezy, J.E., A. Lennox, and N.E. Hertel. 2002. Paired tissue equivalent ionization chambers for boron enhanced fast neutron therapy. 10th International Congress on Neutron Capture Therapy, NCT Essen 2002, September 8-11, Essen, Germany.

Thomson, S.N. 2002. Cenozoic geomorphic and tectonic development of the Patagonian Andes (420 S to 52' S). Talk presented at International Workshop on Fission-track Analysis:

Theory and Applications, Cadiz, Spain, June 2002.

Thomson, S.N. F. Hen6, B. St6ckhert, and M.R. Brix. 2001. Late Cenozoic uplift and erosion history of the Patagonian Andes between 420 S and 52' S. International Workshop on Uplift and Erosion: Driving Processes and Resulting Landforms, September, 2001, Siena, Italy.

Thomson, S.N. 2001. The geomorphic and tectonic response of the upper plate to different subduction processes assessed using fission-track thermochronology: an example from the southern Chilean Andes. German Geological Society Annual Meeting, Kiel Germany, October, 2001.

• Tollo, R.P. and J.N. Aleinikoff. 2001. Petrologic and temporal characteristics of Grenville age orogenesis, Blue Ridge province, Virginia: Geological Society of America, November 2001, Boston, Massachusetts.

• Zattin, M., G. Fellin, V. Picotti, and J. Vance. 2002. Fission-track record of exhumation of Northern Corsica (France). 98' Annual Meeting GSA Cordilleran Section, Corvallis (OR USA), May 13-15.

• Indicates OSTR use.

Words VII -22