Text

Oregon State University Triga Reactor (OSTR) Annual Report for July 1, 2002 Through June 30, 2003
	ML032950242
Person / Time
Site:	Oregon State University
Issue date:	10/08/2003
From:	Klein A; Oregon State University
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML032950242 (146)
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RADIATION CENTER October 8, 2003 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Reference:

Oregon State University TRIGA Reactor (OSTR) Docket No.

50-243, License No. R-106 OREGON STATE UNIVERSITY 100 Radiation Center Corvallis, Oregon 97331-5903 Telephone 541*737-2341 Fax 541-737-0480 In accordance with section 6.7.e of the OSTR Technical Specifications we are hereby submitting the Oregon State University Radiation Center and TRIGA Reactor Annual Report for the period July 1, 2002 through June 30, 2003.

The Annual Report continues the pattern established over the past few years by including information about the entire Radiation Center rather than concentrating primarily on the reactor. Because the report addresses a number of different interests, it is rather lengthy, but we have incorporated a short executive summary which highlights the Center's activities and accomplishments over the past year.

The executive summary indicates that the Radiation Center has had yet another successful and productive year. I would like to emphasize that the achievements of this last year would not have been possible without the support and assistance we received from the invaluable programs administered by the USDOE. In particular, the Reactor Sharing program and the University Research Reactor Upgrades program are very cost-effective in providing invaluable support to the university reactor community and its users. Thanks for all the help we get from USDOE.

Sincerely, Andrew C. Klein Director

$Q~c)

Im:srr l Enclosure i cc: Alexander Adams Craig Bassett David Stewart-Smith Edward Ray Time White Rich Holdren Steve Reese Gary Wachs Shirley Campbell Robin Keen

Oregon State University Radiation Center and TRIGA Reactor Annual Report July 1, 2002 - June 30, 2003

Annual Report of the Oregon State University Radiation Center and TRIGA Reactor July 1, 2002 - June 30,2003 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.

TaskOrderNo. 3, underSubcontractNo. C84-110499(DE-AC07-76ER01953)forUniversityReactor 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 S. C. Campbell, Business Manager M. R. Conrady, Analytical Support Manager J. E. Darrough, Health Physicist L. Mauer, Receptionist S. A. Menn, Senior Health Physicist S. R. Reese, Reactor Administrator J. M. Stueve, Office Specialist S. P. Smith, Scientific Instrument Technician G.M. Wachs, Reactor Supervisor 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 2003

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

Acknowledgements..........................

I-1 B.

Executive Summary..........................

1-1 C.

Introduction..........................

1-2 D.

Overview of the Radiation Center..........................

1-3 E.

History..........................

1-4 PART II - PEOPLE A.

Professional and Research Faculty II-1 B.

Visiting Scientists and Special Trainees 11-5 C.

OSU Graduate Students.............................

II-5 D.

Business, Administrative and Clerical Staff.............................

II-6 E.

Reactor Operations Staff.............................

11-6 F.

Radiation Protection Staff.............................

11-6 G.

Scientific Support Staff.............................

11-7 H.

Committees II-7

1.

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

II-7 PART III - FACILITIES A.

Research Reactor..............................

III -1

1.

Description...............................

111-1

2.

Utilization..

III-2

a.

Instruction................................................

111-2

b.

Research.............................

111-3 B.

Analytical Equipment.

III-3

1.

Description.

III-3

2.

Utilization.

III-3

Page1 C.

Radioisotope Irradiation Sources........................................

II1-4

1.

Description..

............................................... III-4 4

2.

U tilization.....................................................

11-4 D.

Laboratories and Classrooms................................... 111-4 i I.

Description....................................................

III-4

2.

Utilization....................................

III-5 E.

Instrument Repair and Calibration Facility................................. III-5

1.

Description....................................................

III-5

2.

Utilization....................................

III-5 F.

Libraries...........................................................

III-6

1.

Description III-6

2.

Utilization.

111-7 PART IV - REACTOR A.

Operating Statistics.........................

IV-I B.

Experiments Performed.........................

IV-1

1.

Approved Experiments.......................

I...... 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 I

1.

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

2.

10 CFR 50.59 Changes to Reactor Procedures.........................

IV-5

3.

10 CFR 50.59 Changes to Reactor Experiments........................

IV-6 E.

Surveillance and Maintenance...........................................

IV-6

1.

Non-Routine Maintenance......................................... IV-6

2.

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

.................... IV-7 F.

Reportable Occurrences..............................................

IV-7 PART V - PROTECTION A.

Introduction................................................. V-I B.

Environmental Releases................................................ V-1

1.

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

V-2

2.

Airborne Effluents Released.

V-2

3.

Solid Waste Released.............................................

V-3 C.

Personnel Doses.

V-3

Paie D.

Facility Survey Data.....................................

VA

1.

Area Radiation Dosimeters.....................................

V-5

2.

Routine Radiation and Contamination Surveys.......................... V-5 E.

Environmental Survey Data.................

V-6

1.

Gamma Radiation Monitoring.....................................

V-6

2.

Soil, Water, and Vegetation Surveys..................................

V-7 F.

Radioactive Material Shipments.....................................

V-8 G.

References V-9 PART VI - WORK A.

Summary...

VI-1 B.

Teaching...

VI-1 C.

Research and Service..

VI-1

1.

Neutron Activation Analysis..

VI-2

2.

Forensic Studies..

VI-2

3.

Irradiations..

VI-3

4.

Radiological Emergency Response Services..

VI-3

5.

Training and Instruction..

VI-3

6.

Radiation Protection Services..

VI-4

7.

Radiological Instrument Repair and Calibration..

VIA

8.

Consultation..

VI-5

9.

Public Relations..

VI-5 PART VII - WORDS A.

Documents Published or Accepted..

VII-1 B.

Documents Submitted for Publication..

VII-7 C.

Documents in Preparation..

VII-9 D.

Theses and Student Project Reports..

VII-9 E.

Presentations..

VII-10

LIST OF TABLES Table Title Page III.A. 1 OSU Courses Using the OSTR.............

III-8 III.C. 1 Gammacell 220 6 0Co Irradiator Use.............................

III-9 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..................................... III-10 IV.A. 1 OSTR Operating Statistics (Using the FLIP Fuel Core).....

......... IV-8 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 MultipleUse Time................................... IV-15 IV.B. 1 Use of OSTR Reactor Experiments............................

IV-16 IV.C.I Unplanned Reactor Shutdowns and Scrams...................... IV-17 V.A.1 Radiation Protection Program Requirements and Frequencies.....

.... V-10 V.B. 1.a Monthly Summary of Liquid Effluent Releases to the Sanitary Sewer............................................ V-ll 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. 1 Annual Summary of Personnel Radiation Doses Received.....

....... V-15

LIST OF TABLES (Continued)

Table Title Page V.D. 1 Total Dose Equivalent Recorded on Area Dosimeters Located Within the TRIGA Reactor Facility..I

......................... V-16 V.D.2 Total Dose Equivalent Recorded on Area Dosimeters Located Within 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-i9 V.E.1 Total Dose Equivalent at the TRIGA Reactor Facility Fence.V-20 V.E.2 Total Dose Equivalent at the Off-Site Gamma Radiation Monitoring Stations............

V-21 V.E.3 Annual Average Concentration of the Total Net Beta Radioactivity (Minus 3H) for Environmental Soil, Water, and Vegetation Samples...

V-22 V.E.4 Average LLD Concentration and Range of LLD Values for Soil, Water 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 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-27 VI.C. 1 Institutions and Agencies Which Utilized the Radiation Center..

VI-6 VI.C.2 Graduate Student Research Which Utilized the Radiation Center.........

VI-10

If LIST OF TABLES (Continued)

Table Title PaEge Vl.C.3 Listing of Major Research and Service Projects Performed or in Progress at the Radiation Center and Their Funding Agencies......

.. VI-14 VI.C.4 Summary of the Types of Radiological Instrumentation I

Calibrated to Support the OSU TRIGA Reactor and the Radiation Center.........

IV-31 VI.C.5 Summary of Radiological Instrumentation Calibrated to Support Other OSU Departments and Other Agencies.V I-3 2.......

I VI.F. 1 Summary of Visitors to the Radiation Center.V I-3 3...3....

V

LIST OF FIGURES FHiure Title Page I.D.1 Floor Plan of the Radiation Center..............

................. 1-7 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-24 V.D.1 Monitoring Stations for the OSU TRIGA Reactor......

............ V-28

- PartI Overview

Part I OVERVIEW A.

Acknowledgments Many individuals and organizations help the Radiation Center succeed, and in recognition ofthis, the staffofthe Oregon State University (OSU) Radiation Center and TRIGA Reactor (OSTR) would like to extend its appreciation to all ofthose who contributed to the information and events contained in this report: to the University administration; to those who provided our funding, particularlythe U. S. Department ofEnergy(USDOE) and the State of Oregon; to our regulators; to the researchers, the students, and others who used the Radiation Center facilities; to OSU Facilities Services; and to OSU Department ofPublic Safety and the Oregon State Police. We most earnestly say, "Thank you."

Putting this report together each year is a major effort for two people. This year, the burden of collecting the information, "twisting arms," and generallymaking the document beforeyou was placed upon LaVon. Erin has once again made collecting the information much easier by automating manyofthetables inthisreport. The amount ofperson-hours shehas savedallofus is more than we probably would like to admit. A special "thanks" goes out to each of them.

B.

Executive Summary In November 2002, S. A. Menn assumed the position of Senior Health Physicist after the resignation of K. M. Brock. Both Shari Brumbach and LaVon Mauer have come on board as the Radiation Center secretary and receptionist, respectively.

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

The Radiation Center supported 74 different courses this year, mostly in the Department of Nuclear Engineering. About 20% ofthese courses involved the OSTR. The number ofOSTR hours used for academic courses and training was 28, while 1869 hours0.0216 days 0.519 hours 0.00309 weeks 7.111545e-4 months were used for research projects. Seventy-three percent of the OSTR research hours were in support of off-campus researchprojects, which reflects the use ofthe OSTRnationallyand internationally. Radiation Centeruserspublished 56 articlesthisyear,with 13 moresubmittedforpublication. There were also 10 theses completed and 29 presentations made byRadiation Center users. The number of samples irradiatedinthereactor during thisreportingperiodwas 2000. Funded OSTRusehours Overview I - 1

l.

comprised 94% ofthe research use. This is consistent with the move to a more full co st recovery basis for services provided by the Center.

Personnel at the Radiation Center conducted 94 tours ofthe facility, accommodating 1,287 visitors.

I 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 I

engineers; and state, federal and international officials. The Radiation Center is a significant positive attraction on campus because visitors leave with a good impression ofthe facility and ofOregon State University.

Researchprojects ofpersonnel housed inthe Radiation Center totaled approximately $2.75 million for this year.

The Radiation Center projects database continues to provide ausefulwayoftracking the many 1

different aspects of work at the facility. The number of projects supported this year was 145.

Reactorprojects comprised 75% ofall projects. The totalresearch supported bythe Radiation Center, asreportedbyourresearchers, was $1,764,500). The actual total is likelyconsiderably I

higher. ThisyeartheRadiationCenterprovided serviceto 66 different institutions,33% ofwhich were from other states and 15% ofwhich 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.

Furthermore, with the closing ofthe State ofOregon's environmental radiological monitoring I

laboratory in Portland, the Radiation Center is essentially now the only place in the state where radiological monitoring can be performed.

The Radiation Center web site provides an easyway 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.

I C.

Introduction j

The current annual report ofthe Oregon State University Radiation Center and TRIGA Reactor follows theusual formatbyincluding informationrelating to the entire Radiation Center ratherthan 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 theperiod fromJuly 1,2002 throughJune 30,2003. Cumulativereactoroperating I

data in this report relate only to the FLIP-fueled core. This covers the period fromAugust 1,1976 throughJune30,2003. Forasummaryofdataonthereactor'soriginal20% enrichedcore, the reader is referred to Table IV.A.2 in Part IV ofthis report or to the 1976-77 Annual Report ifa i

more comprehensive review is needed.

Overview I - 2

In addition to providing general information about the activities ofthe Radiation Center, this report is designed to meet the reporting requirements ofthe U. S. Nuclear Regulatory Commission, 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 RadiationCenter is aunique facilitywhich serves the entire OSU campus, allother institutions withinthe OregonUniversitySystem, and manyotheruniversities 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 cosmochemistryprograms. Thereisnootheruniversityfacilitywith thecombined capabilities of the OSURadiation Center in the western haylof the United States.

Located in the Radiation Center are major items ofspecialized equipment and unique teaching and research facilities. They include a TRIGA Mark II research nuclear reactor; a 60Co gamma irradiator; a large number of state-of-the art computer-based gamma radiation spectrometers and associated germanium detectors; and a variety ofinstruments for radiation measurements and monitoring. Specialized facilities for radiation work include teaching and research laboratories with instrumentation and related equipment for performing neutron activation analysis and radiotracer studies; laboratories forplant expements involving radioactivity, a facility for repair and calibration of radiation protection instrumentation; and facilities for packaging radioactive materials for shipment to national and international destinations.

A major non-nuclear facility housed in the Radiation Center is the one-quarter scale thermal hydraulic advanced plant experimental (APEX) test facility for the Westinghouse AP600 reactor design. TheAP600 is anext-generationnuclearreactordesignwhichincorporatesmanypassive safetyfeatures asweli as considerablysimplifiedplant systems and equipment. APEX operates atpressuresup to 400 psia and temperatures up to 450'F using electrical heaters instead ofnuclear fueL All major components ofthe AP600 are included in APEX and all systems are appropriately scaled to enable the experimental measurements to be used for safety evaluations and licensing of the full scaleplant. Thisworld-class facilitymeets exacting qualityassurance criteria to provide assurance of safety as well as validity of the test results.

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.

OverviewI - 3

I The Radiation Center staffregularlyprovides 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, environmentalradioactivity, production ofshort-lived radioisotopes, radiation shielding, nuclear instrumentation, emergencyresponse, transportation of radioactive materials, instrument calibration, radiationhealth physics, radioactive waste disposal, and other related areas.

In addition to formal academic and research support, the Center's staffprovides awide varietyof other services includingpublic tours and instructionalprograms, andprofessional consultation associated with the feasibility, design, safety, and execution ofexperiments using radiation and radioactive materials.

E.

History Abriefchronologyofthekeydates and events inthehistoryoftheOSU Radiation Center and the TRIGA reactor is given below:

i i

1 i

I I

I i

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

Transfer ofthe 0.1 WAGN 201 reactor to the RadiationCenter. This reactor was initiallyhoused in the Department ofMechanical Engineering and first went critical in January, 1959.

I I

October 1966 March 1967 October 1967 August 1969 Completion ofthe second phase ofthe Radiation Center, consisting of 9,956 square feet of space for the TRIGA reactor and associated laboratories and offices.

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.

Formal dedication of the Radiation Center.

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.

I I

I1 I

1 I

Overview I - 4 I

June 1971 April 1972 September 1972 December 1974 March 1976 July 1976 July1977 January 1980 July 1980 June 1982 December 1984 August 1986 December 1988 December 1989 June 1990 March 1992 November 1992 June 1994 OSTR cooling capacity upgraded to allow continuous operation at I MW.

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

OSTR area fence installed.

AGN-201 reactor permanently shut down.

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

OSTR refueled with 70% enriched FLIP fuel.

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

Major upgrade of the electronics in the OSTR control console.

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

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

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

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

AGN-201 components transferred to Idaho State Universityforuse in their AGN-201 reactor program.

OSTR licensed power increased to 1.1 MW.

Installation of a 7000 Ci 60Co Gammacell irradiator.

25th anniversary of the OSTR initial criticality.

Start of APEX plant construction.

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

Overview I - 5

August 1994 August 1995 September 1998 January 1999 April 1999 July 2002 October 2002 APEX inauguration ceremony.

Major externalrefurbishment: new roof, complete repaint, rebuilt parking lot, addition of landscaping and lighting.

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

Installation of the Argon Production Facility in the OSTR.

Completion ofATHRL facilitybrings the Radiation Center complex to a total of 47,198 square feet.

I S. E. Binney retired. J. F. Higginbotham became interim director.

A. C. Klein became new director.

Overview I - 6

Figure I.D. 1 Floor Plan of the Radiation Center I

I rYM1 w~um~

II I

It

~~~~~~~~~~~~~~~I V D104 AEACTOR BAY Overview I - 7

Part II People

Part HI PEOPLE This part contains a listing ofall people who were residents ofthe Radiation Center or who worked a significant amount oftime at the Center during this reporting period. Sections A, B, and C list the academic staff, trainees, and students, while sections D throughG list the Radiation Center's operating staff. Section H provides the composition of the Reactor Operations Committee.

It shouldbenotedthat not all ofthe facultyand studentswho used the Radiation Centerfortheirteaching and research are listed in this part. Summary information on the number ofpeople 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.

Professor Emeritus Nuclear Engineering and Radiation Health Physics

Brock, Kathryn M.

Senior Health Physicist Radiation Center

Conrady, Michael R.

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

OSTR users for research and/or teaching.

People II - I

Groome, John T.

Faculty Research Assistant ATHRL Facility Operations Manager Nuclear Engineering and Radiation Health Physics Gunderson, Chris E.

Faculty Research Assistant ATHRL Facility Operator/Test Engineer Nuclear Engineering and Radiation Health Physics

Hamby, David Associate Professor Nuclear Engineering and Radiation Health Physics Hart, Lucas P.

Faculty Research Associate Chemistry

Higginbotham, Jack F.

Interim Director, Oregon Space Grant 1

Professor Nuclear Engineering and Radiation Health Physics

Higley, Kathryn A.

Associate Professor Nuclear Engineering and Radiation Health Physics Hopson, John ATHRL DAS Coordinator/Test Engineer Nuclear Engineering and Radiation Health Physics Johnson, Arthur G.

Director Emeritus, Radiation Center Professor Emeritus Nuclear Engineering and Radiation Health Physics Klein, Andrew C.

Director, Radiation Center Department Head, Department of Nuclear Engineering and Radiation Health Physics Director, Oregon Space Grant Program (to 10/31/02)

Professor Nuclear Engineering and Radiation Health Physics

OSTR users for research and/or teaching.

People !-

2

-I

Krane, Kenneth S.

Professor Physics Lafi, Abd Y.

Assistant Professor Senior Research ATHRL Research Analyst Nuclear Engineering and Radiation Health Physics

Loveland, Walter D.

Professor Chemistry

Menn, Scott A.

Senior Health Physicist

Palmer, Todd S.

Associate Professor Nuclear Engineering and Radiation Health Physics

Paulenova, Alena Assistant Professor Senior Research Radiation Center Popovich, Milosh Vice President Emeritus

Reese, Steven R.

Reactor Administrator Radiation Center Reyes, Jr., Jos6 N.

ATHRL Principal Investigator Professor Nuclear Engineering and Radiation Health Physics Ringle, John C.

Professor Emeritus Nuclear Engineering and Radiation Health Physics

OSTR users for research and/or teaching.

People II - 3

Robinson, Alan H.

Department Head Emeritus Nuclear Engineering and Radiation Health Physics

Schmitt, Roman A.

Professor Emeritus Chemistry

Schijtfort, Erwin G.

Faculty Research Assistant Project Manager

Wachs, Gary Reactor Supervisor Radiation Center Wang, Chih H.

Director Emeritus, Radiation Center Professor Emeritus Nuclear Engineering and Radiation Health Physics Woods, Brian Assistant Professor Nuclear Engineering and Radiation Health Physics Wu, Qiao Assistant Professor Nuclear Engineer and Radiation Health Physics Young, Roy A.

Professor Emeritus Botany and Plant Pathology A

OSTR users for research and/or teaching.

People II - 4

B.

Visiting Scientists and Special Trainees Advisor or Research Name Field (Affiliation)

Program Director Cloughsey, Michael Gallant, Aaron Nicholas Myers Peterson, Don Visiting student, Notre Dame Visiting student, Univ. Rochester Saturday Academy Mentorship Program Summer Student Postdoctoral Assistant, Chemistry W. D. Loveland W. D. Loveland W. D. Loveland W. D. Loveland C.

OSU Graduate Students Name Abel, Kent Bak, Michael Bittle, Whitney Buchholz, Matthew Coleman, Joseph Davidson, Gregory Davis, Ian Frey, Wesley Huang, Zhongliang Jones, Quyen Keller, S. Todd Kincaid, Kevin Kriss, Aaron Lin, Lan Mallory, Stacy Napier, Bruce Nes, Elana Nes, Razvan Rajan, Ajith Rezvyi, Aleksey Rock, Mollie Sabharwall, Piyush Slauson, Maijorie Sriprisan, Sirikul Staples, Christopher Degree Program PhD MS MS MS MS MS PhD MS PhD MS MS MS PhD PhD MS PhD MS PhD MS PhD MS MS MS MS MS Field Nuclear Engineering Radiation Health Physics Nuclear Engineering Radiation Health Physics Radiation Health Physics Nuclear Engineering Nuclear Engineering Radiation Health Physics Nuclear Chemistry Radiation Health Physics Nuclear Engineering Nuclear Engineering Radiation Health Physics Radiation Health Physics Radiation Health Physics Radiation Health Physics Radiation Health Physics Nuclear Engineering Radiation Health Physics Nuclear Engineering Radiation Health Physics Nuclear Engineering Radiation Health Physics Nuclear Engineering Physics Advisor J. N. Reyes K. A. Higley T. S. Palmer J. F. Higginbotham S.E. Binney T. S. Palmer T. S. Palmer J. F. Higginbotham W. D. Loveland D.M. Hamby T. S. Palmer A. C. Klein D. M. Hamby D. M. Hamby D. M. Hamby D. M. Hamby S.R. Reese T. S. Palmer D. M. Hamby J. N. Reyes D. M. Hamby Q.Wu K. A. Higley D. M Hamby K. Krane

OSTR users for research and/or teaching.

People II - 5

Stringham, Michael MS Nuclear Engineering T. S. Palmer Tang, Hong PhD Nuclear Engineering Q. Wu Tavakoli, Farsoni PhD Radiation Health Physics D. M. Hamby Villamar, Glenda MS Radiation Health Physics K. A. Higley Welter, Kent B.

PhD Nuclear Engineering Q. Wu 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 Interim Director, Radiation Center through 9/30/02..............

J.F. Higginbotham I

Director, Radiation Center from 10/1/02..........

A. C. Klein Business Manager, Radiation Center and Nuclear Engineering and Radiation Health Physics.....

....... S. C. Campbell Office Coordinator, Radiation Center through 10/31/02...............

J. M. Stueve Administrative Assistant, Radiation Center and 1

Nuclear Engineering and Radiation Health Physics from 11/1/02....

R. A. Keen Office Specialist, Radiation Center through 11/30/02.......

.......... E. D. Jordan Office Specialist, Radiation Center and Nuclear Engineering and Radiation Health Physics from 11/18/02 S.M. Brumbach Office Specialist, Radiation Center from 1/2/03...........

.............. L. Mauer Custodian....................................

E. Cimbri Office Coordinator, Nuclear Engineering and Radiation Health Physics through 10/31/02...............................

R. A. Keen L

Office Specialist, Nuclear Engineering and Radiation Health Physics from 11/1/02...........

........... J. M. Stueve Office Specialist, ATHRL-Nuclear Engineering and Radiation Health Physics T.L. Culver Word Processing Technician, Nuclear Engineering and Radiation Health Physics through 9/30/02.........................

L. J. Robinson E.

Reactor Operations Staff Principal Security Officer through 9/30/02..........

........... J.F. Higginbotham Principal Security Officer from 10/1/02............................

A. C. Klein Reactor Administrator............

S. R. Reese Reactor Supervisor, Senior Reactor Operator.............

.......... G. M. Wachs Senior Reactor Operator.

S. P. Smith S. T. Keller F.

Radiation Protection Staff Senior Health Physicist through 9/3/02.............................

K. M. Brock Senior Health Physicist from 10/1/02............................... S. A. Menn People II - 6

Health Physicist through 9/30/02..................................

S. A. Menn Health Physicist..............

J. E. Darrough Health Physics Monitors (Students).................................

C. Hepler L. Dart A. Dombrowski A. Ernst J. Juarez J. Jun S. Kleeb G.

Scientific Support Staff Analytical Support Manager...................................

M. R. Conrady Projects Manager.................

E. G. Schiitfort Neutron Activation Analysis Technicians (Students).........

............. K. Gray J. Nazir M. Whittaker Scientific Instrument Technician..................................

S. P. Smith Nuclear Instrumentation Support...............................

M. M. Conrady H.

Committees

1.

Reactor Operations Committee Name Affiliation J.C. Ringle, Chair.........

Nuclear Engineering and Radiation Health Physics S. E. Binney..............

Nuclear Engineering and Radiation Health Physics G. M. Wachs...................

Radiation Center A. C. Klein...................

Radiation Center and Nuclear Engineering and Radiation Health Physics K. M. Brock through 9/30/02.........

Radiation Center W. J. Richards...................

McClellan Nuclear Radiation Center S. R. Reese...................

Radiation Center and Nuclear Engineering and Radiation Health Physics M. H. Schuyler...................

Chemistry W. H. Warnes...................

Mechanical Engineering S. A. Menn from 10/1/02......

Radiation Center D. M. Hamby.............

Nuclear Engineering and Radiation Health Physics T. S. Palmer..............

Nuclear Engineering and Radiation Health Physics R. H. Farmer....................

Radiation Safety Office People II - 7

Part III Facilities

Part III FACILITIES A. Research Reactor

1. Description TheOregonStateUniversityTRIGAReactor (OSTR) is awater-cooled, swimmingpooltypeof researchreactorwhichuses uranium/zirconiumhydride fuelelements inacircular grid array. The reactorcore issurroundedbyaringofgraphitewhichservesto reflect neutronsbackinto thecore.

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 1I.1 MW and can also be pulsed up to a peak power of about 2500 MW.

The OSTR has a number ofdifferent irradiation facilities including apneumatic transfer tube, a rotating rack, a thermal column, four beamports, 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 ahigh energyneutron flux. The OSTR also has an Argon Irradiation Facility for the production of 4 Ar.

The pneumatic transfer facility enables samples to be inserted and removed from the core in four to five seconds. Consequentlythis facilityis normallyused forneutron activation analysis involving short-livedradionuclides. Onthe otherhand, the rotating rack is used formuch longer irradiationofsamples (e.g., hours). Therackconsists ofacirculararrayof4O tubularpositions, each of which 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 ofsamples. 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 tubularpenetrations inthe reactor's main concrete shield which enable neutron andgammaradiationto streamfromthecorewhen abeamport'sshieldplugs areremoved. One ofthe beamports contains theArgon Production Facility for production ofcurie levels of4 'Ar.

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

If samples which are to be irradiated require a large neutron fluence, especiallyfromhigher energy neutrons, theymaybe inserted into a dummyfuelelement. This device will thenbeplaced into Facilities III-1

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 (CLICH) enables samples to be irradiated in a high flux regionnear the center ofthe core. The cadmium lining inthe facilityelimrinates thenmalneutrons and thus permits sample exposure to higher energyneutrons only. The cadmium-lined end ofthis air-filled aluminum irradiation tube is inserted into an inner grid position ofthe reactor core which would normallybe occupied bya fuel element. It is the same as the ICIT except for the presence of the cadmium lining.

2. Utilization Thetwo main uses oftheOSTRareinstruction and research. During this reporting period, the reactor was in use an average of 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months during a typical work week.

a. Instruction Instructionaluse ofthereactor is twofold. First, it isusedsignificantlyforclasses inNuclear Engineering, Radiation Health Physics, and Chemistryat both the graduate and undergraduate levels to demonstratenumerousprincipleswhichhavebeenpresented intheclassroon. Basic neutron behavior is the same in small reactors as it is in large power reactors, and many demonstrations andinstructional experiments canbeperformedusingthe OSTRwhichcannot be carried out with a commercialpower reactor. Shorter-term demonstration experiments are also performed for manyundergraduate students inPhysics, Chemistry, andBiologyclasses, as well as forvisitors fromotheruniversities and colleges, fromhigh schools, and frompublic groups.

The second instructional application ofthe OSTR involves education ofreactor operators, operations managers, andhealthphysicists. The OSTR is inaunique position to provide such education since curricula must include hands-on experience at an operating reactor and in 1

associated laboratories. The manytypes ofeducational 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 10 different OSU academic classes and other academic programs. In addition, portions of classes from other Oregon universities were also supported bythe OSTR. The OSU teaching and training programs utilized 28 hours3.240741e-4 days 0.00778 hours 4.62963e-5 weeks 1.0654e-5 months of reactor time. Tables III.A. 1 and Table III.D. 1, provide detailed information on the use ofthe OSTR for instruction and training.

1 Facilities III -2 1

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

This is a particularly sensitive method ofelemental analysis which is described in more detail in Part VI (SectionVI.C. 1). Part III.B provides alisting ofequipmentused inINAAat the Radiation Center.

The OSTR's irradiation facilities provide a wide range ofneutron flux levels and neutron flux qualities which are sufficient to meet the needs ofmost researchers. This is true not onlyfor INAA, but also for other experimentalpurposes such as the 39Ar/" 0Arratio and fissiontrack methods of age dating samples.

Details ofthe reactor's use are given in Table mI.A.4. Additional information regarding reactor use forresearch, thesis, and service canbe found inTablesVI.C. I throughVI.C.3. InTable VI.C.l OSTR use is indicated with an asterisk.

B. Analytical Equipment

1. Description The Radiation Center has a largevarietyofradiationdetection instrumentation. This equipment is upgraded as necessary, especially the gamma ray spectrometers with their associated computers and germanium detectors. Duringthepreviousyear fournew germanium detectors and sixdigital multichannel analyzers werepurchased. Tables III.B. 1 through III.B.3 provide abrieflisting of laboratorycounting devices present at the Center. Additional equipment for classroomuse and an extensive inventory of portable radiation detection instrumentation are also available.

2. Utilization Radiation Center nuclear instrumentation receives intensive use in both teaching and research applications. In addition, service projects also use these systems and the combined use often results in 24-hour per day schedules for many ofthe 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.

Facilities III -3

C. Radioisotope Irradiation Sources

1. Description The Radiation Center is equipped with a 1,644 curie (as of 7/27/01) Gammacell 220 60Co irradiatorwhich is capableofdeliveringhighdosesofganmaradiationover arange ofdoserates to a variety of materials.

Typically, the irradiator is usedbyresearchers wishingto perform mutation and otherbiological 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 60Co irradiator, the Center is also equipped with a varietyofsmaUer 6 0Co, 1 3 7Cs, 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 ofprojects using the 'Co irradiator. These projects included the irradiationofavarietyofbiologicalmaterials including different types of seeds. In addition, the irradiatorwas used for sterilizationofseveralmediaandtheevaluationof the radiation effects on different materials. Table III.C. 1 provides use data for the Gammaceli 220 irradiator.

D. Laboratories and Classrooms

1. Description The Radiation Center is equipped with a number ofdifferent 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 radiochemistryand a nuclear instrumentation teaching laboratoryequippedwithmodular sets of countingequipmentwhichcanbeconfigured to accommodate avarietyofexperiments involving the measurement ofmanytypes ofradiation. The Center also has four student computer rooms equipped with a large number of personal computers and UNIX workstations.

In addition to these dedicated instructionalfacilities, manyotherresearch laboratories and pieces of specialized equipment areregularlyusedforteaching. In particular, classes are routinely given accessto gamnmaspectrometryequipment located inCenterlaboratories. Anumberofclasses also regularlyusetheOSTRand the Reactor Bayas an integralpart oftheirinstructionalcoursework.

Facilities I -4

There are two classrooms in the Radiation Center which are capable ofholding about 35 and 18 students, respectively. In addition, there are two smaller conference rooms and a librarythat 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 ofthe American Nuclear Society and the Health Physics Society.

This reporting period saw continued high utilization ofthe Radiation Center's thermalhydraulics laboratory. This laboratoryisbeingusedbyNuclearEngineeringfacultymemberto accommodate a one-quarter scale model of the Palisades Nuclear Power reactor. The multi-million dollar advanced plant experimental(APEX) facilitywas ftillyutilizedbytheU. S. NuclearRegulatory Commission to provide licensing data and to test safiety systems in "beyond design basis" accidents.

The fMlly scaled, integralmodelAPEX acilityuses electricalheating elementsto simulatethefuel elements, operates at 450'F and 400 psia, and responds at twice real time. It is the only facility of its type in theworld and is ownedbythe U. S. Department ofEnergyand operatedbyOSU.

In addition, a new building, the Air-water Test Loop for Advanced Thermal-hydraulics Studies (ATLATS), was constructed next to the ReactorBuilding 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 82 courses accommodated at the Radiation Center during this reporting period along with their enrollments is given in Table III.D. 1.

E. Instrument Repair and Calibration Facility

1. Description TheRadiationCenterhasafacilityfortherepairandcalibrationofessentiaflyalltypesofradiation monitoring instrumentation. This includes instrumentsforthedetectionandmeasurement 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.

2. Utilization The Center's instrument repair and calibration facilityisusedregularlythroughouttheyearand is absolutelyessentialto the continuedoperationofthe manydifferentprograms carried out atthe Center. In addition, the absence of any comparable facility in the state has led to a greatly Facilities III -5

expanded instrument calibrationprogramfortheCenter, including calibration of essentiallyall I

radiation detection instruments used by state and federal 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 offEnergy, 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 TheRadiationCenterhasalibrarycontaining significant collections oftexts, research reports, and videotapes relating to nuclear science, nuclear engineering, and radiation protection.

The Radiation Center is also a regular recipient ofa great variety ofpublications from commercial publishers in the nuclear field, from many ofthe 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 regulatorydocumentation. In addition, the Centerhas acollectionover 50 sets ofnuclearpower reactor SafetyAnalysis Reports and EnvironmentalReports specificallypreparedbyutilities for their facilities.

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

CodeofFederalRegulations fortheU.S. NuclearRegulatoryCommission, theU.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 formost ofthe technicalorientationswhich arerequiredforpersonnelworking with radiation and radioactive materials. These tapes are produced, recorded, and edited by Radiation Center staff, using the Center's videotape equipment and the facilities of the OSU Communication Media Center.

Facilities III -6 L

2. Utilization The RadiationCenter library is used mainlyto 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.

Facilities III -7

Table III.A.1 OSU Courses Using the OSTR Course Number Course Name Chem 462 Experimental Chemistry II Chem 103 General Chemistry Chem 205 General Chemistry Chem 225H Honors General Chemistry NE 114 Introduction to Nuclear Engineering and Radiation Health Physics NE 116 Introduction to Nuclear Engineering III NE 451 Neutronic Analysis and Lab I NE 452/552 Neutronic Analysis and Lab II NE 453/553 Neutronic Analysis and Lab In SMILE Science and Math Investigative Learning Experiences.

Facilities III-8

Table IH.C.1 Gammacell 220 60Co Irradiator Use (1276 Ci: 7/1/03)

Purpose of Dose Range Number of Use TIme Irradiation Samples (rads)

Irradiations (hours)

wood, bioflex strips, 2 x 104 Sterilization

sponges, to 53 1,477 biological 2.5 x 106 samples Material electronic 5.0 x 104 to 1

3 Evaluation components 9 x 106 Bio-Medical anticancer 2.0 x 104 Studies vaccine 8.0 x 104 TOTALS 55 1,481 Facilities III -9

ok Table llI.D.1 Student Enrollment in Nuclear Engineering, Radiation Health Physics and Nuclear Science Courses Which Are Taught or Partially Taught at the Radiation Center Number of Students Course Credit Course Title Fall Winter Spring Summer 2002 2003 2003 2003 Nuclear Engineering and Radiation Health Physics Department Courses NERHP1 14 2

Introduction to Nuclear Engineering and 21 Radiation Health Physics NE/RHP1 15 2

Introduction to Nuclear Engineering and 28 Radiation Health Physics NE/RHP116*

2 Introduction toNuclear Engineering and 27 Radiation Health Physics NE/RHP234 4

Nuclear and Radiation Physics I 27 NEIRHP235 4

Nuclear and Radiation Physics U 26 NE/RHP236*

4 Nuclear Radiation Detection and 25 bntrurentation NE319 3

Societal Aspects of Nuclear Technology 75 NE/RHP4 01 1-16 Research I

NE405H 1-16 R&C/Used Nuclear Fuel: Garbage or 4

Gold NE405 1-16 Reading and Conference 1

RHP405 1-16 Reading and Conference NE/RHP406 1-16 Projects 1

1 NE/RHP407 1

Nuclear Engineering Seminar 14 14 17 NE/RHP410 1-12 Internship 3

2 2

1 NE/RHP415 2

Nuclear Rules and Regulations 32 NE416**

4 Radiochemtsy 7

NE450 3

STI Nuclear Medicine NE451*

4 NeutronicAnalysis and LabI 8I-NE452**

4 Neutronic Analysis and Lab II 8

NE4S3*

4 Neutronic Analysis and Lab m 7

I I

I t1 i

ST

= Special Topics

= OSTR used occasionally for demonstration and/or experiments.

= OSTR used heavily.

Facilities III -10

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 Lb.oratozy l

l NE467 4

Nuclear Reactor Thermal Hydraulics 11 I NE474 4

Nuclear Systems Design I 9

NE475 4

Nuclear Systems Design H 9

NE/RHP479 1-4 Individual Design Project 1 I NE/RHP481 4

Radiation Protection 13 NERHP482*

4 Applied Radiation Safety RHP483 4

Radiation Biology RHP487 3

Radiation Biology RHP488 3

Radioecology 3

NE/RHP49O 4

Radiation Dosimetby 8

RHP493 3

Non-reactor Radiation Protection NE/RHP499 1-16 St/Enviomnental Aspects Nuclear Systems NERHP501 1-16 Research I

NE/RHP503 I

Thesis 9

9 9

NE/RHP505 1-16 Reading and Conference 2

NE/RHP506 1-16 Projects I

NE/RHP5071607 1

NuclearEngineeringSeainar 13 11 12 NE/RHP5IO 1-12 Intenship 6

5 7

NE/RHP515 2

Nuclear Rules and Regulations 6

NE526 3

Computational Methods for Nuclear 3

Reactors NE/RHP535 3

Nuclear Radiation Shielding NE/RHP539 3

ST/Nuclear Physics for Engineers and 6

L ________

I__

Scientists I

I ST

= Special Topics

= OSTR used occasionally for demonstration and/or experiments.

= OSTR used heavily.

Facilities III -II

I

-1 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 NE/RHP543 3

Hi-Level Radioactive Waste Management l

l l

NE/RHP549 3

Low Level Waste NE550 3

Nuclear Medicine NE551**

4 Neutronic Analysis and Lab I 2

NE552**

4 Neutronic Analysis and Lab I 1

NE553**

4 Neutronic Analysis and Lab I I I NE557**

3 Nuclear Reactor Laboratory NE559 I

ST/Nuclear Reactor Analysis: Criticality 5

=

Safety NE567 4

Advanced Nuclear Reactor Thenmal 1

Hydraulics NE568 3

Nuclear Reactor Safety NE5691-3 ST/Thermal Hydraulic Instumentation 10 NE574 4

Nuclear Systems Design I 2

NE575 4

Nuclear Systems Design II NE/RHP581 4

Radiation Protection 2

NE /RHP582*

4 Applied Radiation Safety RHP583 4

Radiation Biology 4

NE585 3

Environmental Aspects Nuclear Systems RHP585 3

Environmental Aspects Nuclear Systems NE/RHP586 3

Advanced Radiation Dosimetry RHP588 3

Radioecology 3

RHP589 1-3 ST/Radiation Protection and Risk Assessment RHP593 3

Non-Reactor Radiation Protection NE599 I

ST/Principles of Nuclear Medicine I

ST

= Special Topics

= OSTR used occasionally for demonstration and/or experiments.

= OSTR used heavily.

Facilities III -12 I

--.L

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 NFJRHP601 1-16 Research 1

NE4RWP603 1-16 Thesis 3

4 6

2 NE/RHP605 1-16 Reading and Conference RHP610 1-12 Internship 6

3 2

NE654 3

Neutron1ransport Theory NE667 3

Advanced Thermal Hydraulics 5

Courses fiom Other Departments CH103*

l_

l_General Chemistry CH222*

5 General Chemistry (Science Majors) 247 CH225H 5

Honors General Chemistry 39 CH462*

3 Experimental Chemistry 11 Laboratory 4

ENGR331 4

Momentum, Energy and Mass GEO300 3

Envimnmental Conservation 130 PH202 5

General Physics 217 Courses from Other Institutions ENGRII11 COCC Engineering GS105*

LBCC General Science 27 ~

29

~

30 I

NOTE:

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

ST

= Special Topics

= OSTR used occasionally for demonstration and/or experiments.

= OSTR used heavily.

Facilities III -13

Part IV Reactor

Part IV REACTOR A.

Operating Statistics Reactor operations to meet customer demand, operational testing and calibrations, and to maintain core activity requirements resulted in the generation of 1,025,472 kW Hours ofthermalpower during this reporting period. This equates to 42.7 megawatt days generatedbetweenJuly 1,2002 and June 30, 2003. The cumulative thermal energy generated by the OSTR FLIP core now totalsl 028.6 MWD fromAugust 1,1976 throughJune 30,2003. Theproductivityofthe reactor irradiation facilities canbe calculatedbased onreactor availabilityin accordance with specific use categories. A normal nine-hour, five-day per week schedule sets the total available reactor operating hours. Critical reactor operation averaged 48.9% of each day. Of the 2250 total available annual operating hours, 100 were at power, 481 hour0.00557 days 0.134 hours 7.953042e-4 weeks 1.830205e-4 months swere spent conducting facility startup and shutdown operations, 430 hours0.00498 days 0.119 hours 7.109788e-4 weeks 1.63615e-4 months were expended for maintenance and sample decay delays and 239 hours0.00277 days 0.0664 hours 3.95172e-4 weeks 9.09395e-5 months the reactor was not operating for reasons other than listed above.

Table WIA. 1 provides information related to the OSTR annual energyproduction, fuelusage and use requests. Table IV.A.2 sunmarizes statistics for the original 20% enriched fuel loading.

Tables IV.A.3 through 5 provide additional details on reactor use categories, multiple use and other tracked data.

B.

Experiments Performed

1.

Approved Experiments During the current reporting period there were eight approved reactor experiments available for use in reactor-related programs. These are listed below.

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

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

B-I l Irradiation ofMaterials Involving Specific Quantities ofUranium 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-31 TRIGA Flux Mapping.

B-32 Argon Production Facility.

Reactor IV-I

Ofthese available experiments, sixwereusedduringthereportingperiod. Table IV.B.1 provides informationrelatedto the frequencyofuse andthe generalpurpose oftheiruse.

2.

Inactive Experiments Presently32 experiments are in the inactive file. This consists of experimentswwhichhave beenperformed in thepast and maybe reactivated. Manyofthese experiments arenow 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.

I B-i ActivationAnalysis ofStone Meteorites, Other Meteorites, and TerrestrialRocks.

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 8F.

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.

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

C-1 PuO2 Transient Experiment.

Reactor IV -2

C.

Unplanned Shutdowns There were nine unplanned reactor shutdowns during the current reporting period. A scram occurs whenthecontrolrods drop inas a result ofan automatic trip or as aresult oftheoperatorpushing the manual trip button. Due to unusual conditions or operational anomalies ofa less critical nature, thereactormayalso be securedbymanualrodinsertion. TableIV.C.1 containsasummaryofthe 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 CF`R 50.59 The information contained in this section of the report provides a summary of the changes performed during the reporting period under the provisions of 10 CFR 50.59. For each item listed, there is a briefdescription ofthe action taken and a summary ofthe applicable safety evaluation.

1.

10 CFR 50.59 Changes to the Reactor Facility There were 4 changes to the reactor facility during this reporting period. For additional information regarding these changes, or copies of the changes, contact the OSTR Operations staff.

(1) 01-08, Evacuation Horn Removal (a)

Description The RadiationCenteris servedby3 individualsystemsproviding information and alarms capable ofprompting facility evacuation during emergency conditions.

These systems include the public address system (PA), the fire alarm system and a series of 12 volt automobile horns.

The car horn system was deemed to be substandard in its installation and less reliable, requiring high levels ofmaintenance. It was subsequentlyremoved and replaced bythe installation ofan integrated circuit addition to the PA announcing system Apre-recorder messagecanbeactuatedbyevacuationswitcheslocated at the front ofthe Radiation Center and within the OSTRcontrolroom. Additional speakers and signal amplifiers were added as necessaryto ensure the evacuation message is audible throughout the facility.

(b)

Safety Evaluation Both the PA and fire systems are powered from the inverter backed emergency power system and have demonstrated excellent reliability. Changes to this system Reactor IV - 3

will not affect the need for actuation, but will increase reliability due to the PA system's frequency of use and standardization of message.

(2) 02-03, Installation of a Primary Tank Camera (a)

Description A standard color CCD camera, contained within a waterproof housing was mounted on the reactor tank liner to provide a clear view of the reactor core during all modes ofoperation. In addition to providing the operator with visual clues relatedto operation, thevideo signalprovides the meansforfacilityvisitors to observe the core from the visitor's gallery.

(b)

Safety Evaluation Primary concerns related to thepossible introduction ofcamera housingpieces during reactor operation were shown not to create unanalyzed damage.

(3) 02-04, Replacement of the Secondary Chemical Addition System (a)

Description The current non-functionalsecondarysystemconductivitybased chemical addition system was replaced by a batch flow system based on cooling tower makeup flow. Additionally, chemical injectionpoints were altered to increase mixng and reduce injection head requirements. Chemical addition andblowdownrates are adjusted based on periodic water chemistry analysis.

(b)

Safety Analysis Although a loss ofcoolant accident is considered to be the most pertinent event related to a failure of the secondary cooling system, the specifically addressed analysis ofreactor damage associated while operating the reactor with only air cooling results in no cladding damage.

(4) 02-08, Insertion of a Bismuth Filter into Beam Port #3 (a)

Description Abismuthfilterwas inserted into BeamPort #3 to reduce thephotoncontent of the neutron beam produced during operation. This was necessaryto further assess the suitability ofthe beamport for use as a neutron radiography source following initial neutron flux testing.

Reactor IV-4

(b)

Safety Analysis The installedplug filter ispassive andplacedexternalto the reactorprimarytank.

No effect on reactor operation is expected.

2.

10 CFR 50.59 Changes to Reactor Procedures Numerous changesto procedures related to reactor operationwerepromptedbyfacility changes and the periodic review of the Reactor Operations Committee (ROC).

Foradditionalinformationregarding these changes, or copies ofthe changes, contact the OSTR Operations staff.

(1) 02-07 and 03-01, Revisions to OSTROP 17, 26 (a)

Description Changesto OSTROP 17, ReactorRoomVentilation SystemProcedures,were identifiedbythe Operations Staff and subsequent reviewbythe ROC inresponse to equipment changes.

Changes Made to OSTROP 26, Procedures for the Connection of External Monitoring and Recording Devices, resulted froman ROC audit and were mostly related to clerical corrections.

(b)

Safety Evaluation The intent ofthese OSTROPS will not be significantlyaltered. The changes simply clarify the original intent or make it consistent with the current regulations.

(2) 0 02-09 and 03-04, OSTROP 6 (a)

Description OSTROP 6, Administrative and Personnel Procedures, was altered to include the ROC Charter as an integral part ofthe OSTROP. This change also increased the conservativeness ofassistance to the Reactor Operator during at power operation byrequiring the presence ofa select list of individuals within the Radiation Center.

(b)

Safety Evaluation Theintent ofthe OSTROP willnotbesignificantlyaltered. Thechanges simply clarify the original intent or make it consistent with the current regulations.

Reactor IV-5

Ir-1I (3) 02-10, OSTROP 18 (a)

Description Changes made to this OSTROP, Procedures for the Approval and Use ofReactor Experiments, are meant to assist the experimenter to complete the necessary forms correctlyandto complywith changesnmadeintemallyto trackandrecordreactor use data. Forms have been standardized and computerized allowing web access with streamlined instructions.

(b)

Safety Analysis The intent of the OSTROP will not be significantly altered.

(4) 03-02, OSTROP 11 (a)

Description Grammatical and clerical errors in OSTROP 11, Fuel Element Handling Procedures, were identified by the ROC audit and corrected in this revision.

Removed ambiguity in the form of"should" statements byreplacement with "shalr'.

(b)

Safety Analysis The intent ofthe OSTROP will not be significantlyaltered. The changes simply clarify the original intent or make it consistent with the current regulations.

3.

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

E.

Surveillance and Maintenance I1.

Non-Routine Maintenance i

i 1

1 1

-I July 2002 August 2002 September 2002 Replaced Lazy Susan argon ventilation system HEPA filter.

Replaced PB test switch on HRV test circuit which seems to have eliminated spurious High Volts scrams.

Replaced reactor bay air supply damper actuator diaphragm in D 106.

Replaced reactor bay ventilation steam supply diaphragm in D400.

Painted reactor bay visitor's gallery (D300).

II Reactor IV-6 i

October 2002 December2002 January2003 February 2003 April 2003 Replaced the emergencypower system inverter with anew upgraded unit. Unit has gel cells vs. lead acid batteries. Initial wiring error required the replacement of AC input switch.

Replaced the emergency generator battery.

Recovered and removed detached internal source from reactor top CAM.

Fabricated 3 new polyethylene thermal column sample holding 'pizza boards" for replacement of deteriorating ones.

Inspected and load tested reactor bay crane.

Drilled 2.5" hole in floor north of console for re-routing of wiring associated with console upgrade.

Disassembled temporary Beam Port #3 shield blockhouse and returned internal assembly to original configuration.

Upgraded reactor bay crane to operate using radio control vs.

pendant. Changed oil in all gearboxes.

Located new computer adjacent to console with internal data acquisitions system installed.

2.

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

Examples oftypical S&M checklists are presented in Figures N.E. 1 through IV.E.4.

Items identified by shading are required by the OSTR Technical Specifications.

F.

Reportable Occurrences NRC notified ofa "Self-Identified Violation ofthe OSTR Physical SecurityPlan". Details are restricted from general release.

Reactor IV - 7

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

Io2 C5E

It1.4

'11t

I00 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 June 30, 1978 June 30, 1979 June 30, 1980 June 30,1981 June 30, 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 Grams 23 5 U Used 24.0 25.9 13.4 29.8 52.5 52.4 48.6 49.3 Hours at Full Power 401 481 218 552 998 973 890 929

(_ MW)

Numbers of Fuel Elements Added or 85 0

2 0

0 1

0 0

Removed (-)

Number of Irradiation 44 375 329 372 348 408 396 469 Requests t--

I---

W._-_

C-C----

I----

C---.--

W---*-

L.

[-- --

I -

F

r---

r

--- I f

r

[--

I r-------

r---- r r-- r r

r- ---

r-_-

I----- I -

Table IV.A.1 (Continued)

OSTR Operating Statistics (Using the FLIP Fuel Core) a'11

\\0 Operational Data July 1, 1984 July 1, 1985 July 1, 1986 July 1, 1987 July 1, 1988 July 1, 989 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 H o u r s_

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 (I MW) w, Numbers of Fuel Elements 0

0 0

-2 0

-1,+1

-1 0

0 Added or Removed (-)

a 2cl

11

-N

'111

I CZ 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 June 30, 1996 June 30,1997 June 30,1998 June 30, 1999 June 30,2000 June 30,2001 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 H o u r s_

Megawatt 46.7 46.6 46.0 41.0 38.6 46.5 35.5 37.3 38.2 Urams 235u58.6 58.4 57.8 51.5 48.5 58.3 44.6 46.8 47.7 Hours at Full Power 1109 1110 1101 980 921 1109 843 890 912 (I MW)

Numbers of Fuel Elements 0

0

-10

-I, +7 0

-1(5) 0

°

-10)

Added or Removed (-)

Number of Irradiation 303 324 268 282 249 231 234 210 239 Requests I------

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[

r r "

-- r r

r r--- -

r~

r I- -

r I

V I

0 2cl

%-4 NI k-.

h..

Table IV. A.1 (Continued)

OSTR Operating Statistics (Using the FLIP Fuel Core)

Operational July 1, 2002 July 1, 2003 July 1, 2004 July 1, 2005 July 1, 2006 July 1, 2007 July 1, 2008 July 1, 2009 July 1, 2010 Data for Through Through Through Through Through Through Through Through Through FLIP Core June30 2003 June 30, 2004 June30, 2005 June30, 2006 June 30,2007 June 30,2008 June 30,2009 June 30,2010 June 30, 2011 Operating 1100 Hours (critical)

Megawatt 1025 Hours Megawatt 42.7 Days Grams 23U 50.5 Used Hours at Full 1023 Power (I MW)

Numbers of 0

Fuel Elements Added or Removed (-)

Numberof 215 Irradiation Requests (1)

(2)

(3)

(4)

(5)

(6)

(7)

The reactorwas shutdown on July 26, 1976 forone month m order to completelyrefuel the reactor with a new FLIP fuel core.

No fuel elements were added, but one fueled follower control rod was replaced.

Two fuel elements were removed due to cladding deformation.

One fuel element removed due to cladding deformation and one new fuel element added.

One fuel element removed for core excess adjustment No fuel elements were added, but the instiumented fuel element was replaced.

One fuel element removed due to cladding deformation and one use fuel element added.

10 2(13

E

It11-4

'114

k14 Table IV.A.2 OSTR (eatine atisticsi hthe Oria nal 20% Enriched) Standard TRIGA Fuel Core Operational TTL Data Mar 8,67 Jull,68 Jul1,69 Aprl,70 Aprl,71 Aprl,72 Aprl, 73 Aprl,74 Aprl,75 Aprl,76 TMOTAL:

for 20%

Through Through Through Through Through Through Through Through Through Through Th 67 Cnrkhed Jun30,68 Jun3O,69 Mar31,70 Mar31,71 Mar3l,72 Mar31,73 Mar31,74 Mar31,75 Mar31,76 JuI26,76 July 76 C o r e_

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 H o u rs I

Megawatt 4.9 4.3 5.8 9.3 8.1 20.7 14.1 13.4 17.0 9.0 106.4 D a y s Used 6.1 5.4 7.2 11.7 10.2 26.0 17.6 16.8 21.4 10.7 133.0 Hours at Full Power 429 369 58 856 (2

5 0 k W )_

Hours at Full Power 20 23 100 401 200 291 460 205 1700 Number of 70 Fuel Elements 1

2 13 1

2 2

2 0

94 Added to Core (nta)21 Number of Irradiation 429 433 391 528 347 550 452 396 357 217 4100 Requests of 202 236 29092991439 5

Number of 202 236 299 102 98 249 109 183 43 39 1560 P u l s e s I__

_I__

(1)

(2)

(3)

(4)

Reactor went critical on March 8, 1967 (70 element core; 250kW). Note: This period length is 1.33 years as initial criticality occurred in March of 1967.

Reactor shutdown August 22, 1969 for one month for upgrading to 1MW (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.

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

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.

V-

[

[---- -----

I--

[---

V--

F - ---

1-----

Table IV.A.3 Present OSTR Operating Statistics Operational Data Annual Values Cumulative Values for FLIP Core (2002/2003) for FLIP Core MWH of energy produced 1025 24,686 MWD of energy produced 42.7 1,028 Grams 235U used 50.5 1,287.5 Number of fuel elements added fo 0

79 + 3 FFCR(1 )

(+) or removed from (-) the core Number of pulses 10 1,377 Hours reactor critical 1100 24,343 Hours at full power (1 MW) 1023 24,266 Number of srtup and shutdown 250 6,817 checks Number of irradiation requests 215 8,768 processed Number of samples irradiated 2000 110,985 (1)

Fuel Follower Control Rod. These numbers represent the core loading at the end of this reporting period.

Reactor IV-13

11 Table IY.A.4 OSTR Use Time in Terms of Specific Use Categories i

Annual Values Cumulative Values OSTR Use Category (hours) for FLIP Core (hours)

~~~(hours)

Teaching (departmental and others)(')

28 13,176 OSU Research 505 9,372 Off-campus research 1,364 18,733 Forensic services 0

2340)

Reactor preclude time 911 21,566 Facility time(3) 19 7,117 1

TOTAL REACTOR USE TIME 2,827 70,198

-A (1)

See Tables II.A.2 and III.D. 1 for teaching statistics (reactor tours are not logged as use).

(2)

Prior to the 198 1-1982 reporting period, forensic services were grouped under another use category and the cumulative hours have been compiled beginning with the 1981-1982 report.

(3)

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

I Reactor IV-14 1

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

Cumulative Values Number of Users Annual Values for FLIEP Core (hours)

(hours)

Two 479 4,933 Three 179 1,642 Four 17 576 Five 9

142 Six 0.5 59 Seven 0

12 TOTAL MULTIPLE USE TIME 684.5 7,364 (1)

Multiple use time is that time when two or more irradiation requests are being concurrently fulfilled by operation of the reactor.

Reactor IV - 15

- I 11 Table IV.B.1 Use of OSTR Reactor Experiments Experiment NRC Number Research Teaching Forensic License Other Total Requirement A-1 0

0 0

4 8

12 B-3 143 20 0

0 16 179 B-12 12 0

0 0

0 12 B-23 0

0 0

0 3

3 B-31 7

0 0

7 B-32 2

0 0

2 Total 164 20 0

1 27 215

.L.

I I

-.1 I

I, Reactor IV-16

Table IV.C.1 Unplanned Reactor Shutdowns and Scrams Type of Event Number of Cause of Event Occurrences High Voltage 1 2

Scram occurs while shimming rods, acknowledging Scram alarms and other seemingly unrelated events. HVI PB test switch, internal spring was failing to keep contacts closed when external vibrations applied. Switch replaced.

Safety Power Scram 1

Operator error. Rod height balance allowed Safe channel power to exceed 106% during initial temperature rise at 1MW.

Period Scram 1

Scram occurs during rod withdrawl at very low power levels. No positively identified cause for what appears to be AC noise.

Manual Reactor Shutdown I

Shutdown due to high activity on ARM#1. Cause determined to be clogged filter on outlet of Lazy Susan argon vent manifold. Low flow allowed argon concentration to accumulate in discharge header and raise local area background activity.

Manual Reactor 2

Reactor shutdown from 15 watts and 1 MW to replace Shutdown stack monitor particulate filter paper.

Manual Reactor 1

Reactor shutdown due to activation of the Radiation Shutdown Center Fire Alarm Percent Power Scram 1

No positively identified cause for what appears to be AC noise.

Reactor IV-17

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

OSTROP 13 Rev. 8 SURVEILLANCE & MAINTENANCE FOR THE MONTH OF SURVEILLANCE & MAINTENANCE I [SHADE INDICATES LICENSE REQUIREMENT] I TARGET DATE NOT TO BE l DATE REMARKS AS FOUND l

DATE EXCEEDED

COMPLETED

& INITIALS LIMITS Tu M

z Do 4

PRIMARY WATER Ph MEASUREMENT MIN: 5 MAX: 8.5 5

BULK SHIELD TANK WATER Ph MIN: 5 MEASUREMENT MAX: 8.5 6

CHANGE LAZY SUSAN FILTER FILTER CHANGED 7

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

8 PROPANE TANK LIQUID LEVEL CHECK

> 50%

9 PRIMARY PUMP BEARINGS OIL LEVEL OSTROP 13.13 NEED OIL?

10 WATER MONITOR CHECK

Date not to be exceeded is only applicable to shaded items. It is equal to the time completed last month plus six weeks.

t I I~~ ~~ I

[I I

I tI I

I I

I I.

I

r- -

I--- -

r -

[--

r r-- -

r r

r u

[

I r

i I-1-I r

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

OSTROP 14 Rev. 6 SURVEILLANCE & MAINTENANCE FOR THE 1" / 2d / 3d / 4* QUARTER OF 20_

I SURVEILLANCE & MAINTENANCE I TARGET I

DATE NOT TO I

DATE I REMARKS &

I ATB A

BB UqU'UUT~rT*

BCADDT I

IOMPBTBAT C

2n k"

lli

b..

0 6

ROTATING RACK CHECK FOR UNKNOWN SAMPLES EMPTY 7

WATER MONIIDR ALARM CHECK FUNCTIONAL MOTORS OILED 8

STACK MONITOR CHECKS P

._V (OIL DRIVE MOTORS, H.V. READINGS)

PART: 1150 V

_V GAS: 900V4 50 V

9 CHECK FILTER TAPE SPEED ON STACK MONITOR 1"/HR 0.2 10 INCORPORATE 50.59 & ROCAS INTO DOCUMENTATION QUARTERLY I

STACK MONITOR ALARM CIRCUIT CHECKS ALARM ON ARM SYSTEM ALARM CHECKS CHAN 1 2 3

4 6

7 8 91011 12 13 14 12 AUD PFUNCTIONAL PAN__

JANN I_

P Date not to be exceeded is only applicable to shaded itenm.

It is equal to the date completed last quarter plus four mnths.

Figure IV.E.2 (Continued)

Quarterly Surveillance and Maintenance (Sample Form)

OSTROP 14 Rev. 6 (CONTINUED)

SURVEILLANCE & MAINTENANCE FOR THE 1 / 2"d / 3"d / 4th QUARTER OF 20 SURVEILLANCE & MAINTENANCE l

l TARGET [ DATE NOT TO [ DATE REMARKS &

(SHADE INDICATES LICENSE REQUIREMENT1 LIMITS AS FOUND j

DATE BE EXCEEDED*

COMPLETED INrAI.LS OPERATOR LOG a) T

__E b) OPERAThIG EXERCISE a) 24hours: at console (RO) or as Rx. Sup. (SRO) 13 b) Complde Operating Exercise

0 2cl

%-4 111

NJ Q,

Date not to be exeede is only aplpicable to oh-ded itens. It is equal to the date completed last quarter plus four months.

K-...

K K

I.

I-..

I-_

F--

F -

F

.F F

.F

{f I-r{[

rI-F I

[

r r

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

OSTROP 15 Rev. 9 SEMI-ANNUAL SURVEILLANCE AND MAINTENANCE FOR 1n /2' HALF 20

.URVEMLMCE&M~nfnW AN DATE NOT I

D REMARKS SURVE MIANCE R

MAlNAENANC TAMET TO BE DATE I

A&

[SHDE DND!CATE UCENS EURMETIUTR Ad lfN fASR PX!-1f D MTw~nINATE iq IEDC C13

Date not to beexceeded isonly applicable to shaded items. It is equal to the date led timc plus 7 % months.

Figure IV.E.3 (Continued)

Semi-Annual Surveillance and Maintenance (Sample Form)

OSTROP 15 Rev. 9 (CONTINUED)

SEMI-ANNUAL SURVEILLANCE AND MAINTENANCE FOR 1" /2"d HALF 20_

0 R"I t

SURVEILLANCE & MAINTENANCE 1

DATE NOT REMARKS SURVEILLANCE & MAlNTEN4ANCB TARGET TO BE DATE (SHADE INDICATES LICENSE REQUIREMENT LIMITS ASPOUND DATE EXCEEDBD COMPLETED NITIS 10 LUBRICATION OF THE ROTATING RACK BEARNGS 1OW OIL 11 CONSOLBECHEaC LIST OSTROP 15XI 12 NVERTER MAINT.BNANCEI See Usar MlR 13 PTANDARD CONTROL ROD MOTOR CHECKS LO178odiweil NONE 14 ION CHAMBER RESISTANCE MEASUREMENTS IAF____CHANNEL_

O__)

WITH MEGGAR INDUCED VOLTAGE NONE 1/JOWERCHANNEL (No OnEy)

@IOOV.I-____

15~~~~~~~~~~~~~~~~~~~~~~~~~~~ @V AMPS PISSION CHAER RESISTANCE R. 800V 9V.D V-AIS NONE 15 CACULA1ON Al 1__1AMPS (Info Only)

R-_______

HIGH 16 FUNCTIONAL CHECK OF HOLDUP TANK WATER LEVEL ALARMS OSTROP 3RBEN 15.XVI REENf RUSH INSPECTION 17 WSPECTION OF THE PNEUMATIC TRANSFER LBNOlD VALVE INSPECTION FUNCTIONAL LE INSERTION TIME CHECK s6 SECONDS Daft not to be exceeded is only applicable to shaded items. It is equal to the date last time plus 7 'A months.

I_---- -

I - -

1--

V

-F v---

F----

I ---

I----

F-

i--- I - -

f, I

I I

I

[ -

[

Ir I

I l I

V Figure IV.E.4 Annual Surveillance and Maintenance (Sample Form)

OSTROP 16.0 Rev. 7 Annual Surveillance and Maintenance for 20 SURVEILLANCE AND MAINTENANCE A

INDI TCTfhA'ATES T TLICME DRT ffDMEM AS TARGET DATE NOT TO BE EXGEI)ED~n DATE COMPT PTE REMARKS &

I TNMATTASI ft It N

- LJaf t w oe excceaea Ly orny apj completed lat time plus 2 % years.

Figure IV.E.4 (Continued)

Annual Surveillance and Maintenance (Sample Form)

OSTROP 16.0 Rev. 7 (Contlnued)

Annual Surveillance and Maintenance for 20_

SURVEILLANCE AND MAINTENANCE rADE ThDnTATPQ T TfLCENSE D1PRETOTD1ThAU LRVMlT AS FOUND TARGET DATE DATE NOT TO BE EXCEEDED*

DATE COMPLETED REMARKS &

INITLLS

>4 2

0ZIt

'11-i L

REACTOR TANK AND CORE COMPONENT INSPECTION I --

j-17 EMERGENCY LIGHT LOAD TEST RCHPP 18.0 l

18 FUEL ELEMENT INSPECTION FOR SELECTED PASS Pulse #_

ELEMENTS (Bl, B2, B3, B5, B6, C3, C5, DS, D6)

ONOGO DAte 19 FUNCTIONAL TEST OF THE REACTOR WATER LOW

-3 INCHESNS LEVEL ALARM

_ANN, ANNUAL REQUALIFICATION BIENNIAL MEDICAL EVERY 6 YEARS LICENSE REACTOR OPERATOR LICENSE CONDIIONSWN ERATON w~rrrm4 OPEtATNM Mrs APPLICATION MAN EXAM DATE DATE

~~~~DATEDU OPERATOR NAME DATE DATl DATE DATE tIED DUE DATE 20 DUE PA mmD DUE PASSBD DATE MAIRED

- LiA no0 to oe ewxeaad Is oA1. applicable to shaaea iemns. it aI equa o e a.

me dre complaed astyear phis 15m months. ror bienial license requiremenus, ft is equal to the date completed last time plus 2 ' yewas.

I--

V I--

I F--

F-F-

[-

F--

F-F----

iF- --

Part V Protection

Part V PROTECTION A.

Introduction This sectionofthe report deals withthe radiationprotectionprogramat the OSU Radiation Center.

The purpose ofthis 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 regulatoryrequirements ofthe state ofOregon, the U. S. Nuclear Regulatory Commission, and otherregulatoryagencies. The comprehensive nature oftheprogramis showninTable V.A. 1, which lists the program's major radiationprotection requirements and the performance frequency for each item.

The radiationprotectionprogram is implemented byastaffconsisting ofa Senior Health Physicist, a Health Physicist, and several part-time Health Physics Monitors (see Part HY.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 ofNuclearRegulatoryCommission(NRC) FacilityLicenseNo. R-106 (DocketNo.

50-243) and the Technical Specifications contained in that license. The material has also been prepared in compliance with Oregon Office ofEnergyRule No. 345-30-010, whichrequires an annual report of environmental effects due to research reactor operations.

Within the scope of Oregon StateUniversity's radiationprotectionprogram, it is standard operating policyto maintainallreleases ofradioactivity 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 of radioactive 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-I

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 L

effluent is analyzed for radioactivity content at the time it is released to the collection point. However, liquidsarealwaysanalyzedforradioactivitybeforethe holdup tank is discharged into the unrestricted area (the sanitary sewer system).

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

b.

Liquid Waste Generated and Transferred Liquid waste generated from glassware and laboratoryexperiments is transferred bythe campus Radiation Safety Office to its waste processing facility. The annual I

summary ofliquid waste generated and transferred is contained in Table V.B. 1.b.

2.

Airborne Effluents Released Airborne effluents are discussed in terms ofthe 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., prior to, during, and after reactor operations. It is normal for the reactor facility stack effluent monitor to begin operationasone ofthe first systems inthe morning and to cease operation as one ofthe last systems at the end ofthe 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 ofthe detectable particulate radioactivity in the stack effluent confirmed its origin as naturally-occurring radon daughter products, within a range of approximately3 x 10.11 pCi/ml to 1 x 10 iiCi/m[. This particulate radioactivity ispredominantly 214Pb and"2 4Bi which is not associatedwithreactoroperations.

There was no release ofparticulate effluents with a halflife greater than eight days and therefore the reporting ofthe average concentration of radioactive particulates with half lives greater than eight days is not applicable.

3.

Solid Waste Released Data for the radioactive material inthe 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. Solidradioactivewaste is routinelytransferred to theOSU Radiation Safety Office. Until this waste is disposed of by the Radiation Safety Office, it is held along with other campus radioactive waste on the University's state ofOregonradioactive materials license.

Solidradioactivewaste is disposed ofbytheUniversityRadiationSafetyOfficebytransfer to the University's radioactive waste disposalvendor, Thomas GrayAssociates, Inc., for burial at its installation located near Richland, Washington.

C.

Personnel Doses The OSTR annual reporting requirements specify that the licensee shallpresent asummaryofthe radiation exposurereceivedbyfacilitypersonnelandvisitors. For the purposes ofthis report, the summary includes allRadiationCenterpersonnelwho mayhavereceivedexposureto radiation.

These personnel have been categorized into six groups: fiacility operating personnel, key facility researchpersonnel, fcilities services maintenance personnel, students in laboratoryclasses, police and security personnel, and visitors.

Facilityoperatingpersomelincludethereactoroperationsandhealthphysicsstaff Thedosimeters 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 facilityresearchpersonnel consist ofRadiation Center staff, faculty, and graduate students who perform research using the reactor, reactor-activated materials, or using other research Protection V-3

facilities present at the Center. The individual dosimetryrequirements for these personnel will vary with the type ofresearch being conducted, but will generally include a quarterly TLD film badge andTLD (finger) extremitydosimeters. Ifthepossibilityofneutronexposureexists, 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 quarterlyXp(y) TLD badge and other dosimeters as appropriate for the work being performed.

Students attending laboratory classes are issued quarterly Xj3(G) TLD badges, TLD (finger) extremity dosimeters, and track-etch/albedo or other neutron dosimeters, as appropriate.

Students or small groups ofstudents 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.

OSUpolice and securitypersonnel are issued a quarterlyXf3(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 Centerpolicydoes not normally allow people in the visitor categoryto become actively involved in the use or handling of radioactive materials.

An annual sumnmaryofthe radiation doses received byeach ofthe above six groups is shown in Table V.C. 1. There were no personnel radiation exposures in excess ofthe 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 summaryofthe 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-39 plastic track-etch neutron detector has also been included in the monitoring package.

The totaldose equivalent recorded onthevariousreactorfacilitydosimeters is listed in Table V.D.1 and the total dose equivalent recorded on the Radiation Center area dosimeters is listed inTableV.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'sprogramforroutine radiationand contaminationsurveys consists ofdaily, weekly, and monthlymeasurements throughout the TRIGA reactor facility and Radiation Center. The frequencyofthese surveys isbasedonthenatureoftheradiationworkbeing carried out at aparticular 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 assureregularlyscheduled surveillanceoverselectedwork areas inthe reactorfacilityand in the Radiation Center, in order to provide current and characteristic data on the status of radiological conditions. A second objective of the program is to assure frequent on-the-spot personal observations (along with recorded data), which willprovide advance warning ofneeded corrections and thereby help to ensure the safe use and handling of radiation sources and radioactive materials. A third objective, which is reallyderived from successful execution ofthe 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 sunmnaryofradiation and contamination levels measured during routine facility surveys for the applicable reporting 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."

AL I.

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 descnbed in Section V.B.2 and nine environmental monitoring stations. These iL 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 (normallythree Harshaw 7LiF TLD-700 chips per

'Li monitor in a plastic "LEGO" mount). These monitors are exchanged and processed quarterly. The total number ofTLD 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 reportingperiod, each fence environmental stationutilized an LIF TLD monitoring packet suppliedandprocessedbylCN Worldwide DosimetryService (ICN), Costa Mesa, California. Each ICN packet contained three LIF TLDs and was exchanged quarterlyfor a total of 108 samples during the reporting period (9 stations x 3TLDs per station x 4 quarters). The total number of ICN TLD samples for the reporting period was 90. A summary ofthe ICN TLD data is also shown in Table V.E. 1.

Monthly measurements ofthe direct gamma dose rate (liremh 1') 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" Nal detector.

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

From Table V.E. 1 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 L.

b.

Off-site Monitoring The off-site gamma environmental radiation monitoring programconsists oftwenty monitoring stations surrounding theRadiation 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 processedTLD monitor. Eachmonitor consistsoftbreeHarshaw7LiF 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 LaboratoryandNationalForage SeedLaboratory, respectively). These monitors are exchanged and processed quarterly, and the total number ofTLD samples during the current one-year reporting period was 240 (20 stations x 3 chips per stationper quarterx4 quartersperyear). Asummaryofthe OSU off-site TLD data is provided in Table V.E.2. The total number ofICN TLD samples for the reporting period was 144 (12 stationx 3 TLDs per stationx4 quarters). The total number ofICN TLD samples for the reporting period was 128. A summary of ICN TLD data for the off-site monitoring stations is also given in Table V.E.2.

In a manner similar to that descn1bed for the on-site fence stations, monthly measurements ofthe direct gamma exposure rate inmicroremperhour (premh')

are made at each ofthe twenty off-site radiation monitoring stations. As noted before, these measurements are madewitha Bicronmicro-remperhour survey meter containing a l"x l"NaI detector. Atotalof240 iremh7' measurements were made during the reporting period (21 stations per month x 12 months per year). Thetotaldose equivalent foreachstationwas determinedbyaveragingthe 12 separate premh1 measurements and multiplying this average by 8760 hours0.101 days 2.433 hours 0.0145 weeks 0.00333 months per year. A summary of these data is given in Table V.E.2.

Afterareview ofthe datainTableV.E.2, it is concluded that, likethe dosimeters onthe TRIGA facilityfence, allofthe dosesrecordedbythe off-site dosimeters can be attributed to natural background radiation, which is about 110 mremper year for Oregon (Refs. 1, 2).

2.

Soil, Water, and Vegetation Surveys The soil, water, andvegetationmonitoringprogramconsists ofthe collection and analysis of a limited number of samples in each category on a quarterly basis. The program monitors highlyunlikelyradioactive materialreleases fromeither the TRIGA reactor facility Protection V-7

concentration in each of the various substances sampled. See Figure V.E. 1 for the locations ofthe 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 aradius of about ten feet at the positions indicated in Figure V.E. 1.

There are a total of 22 quarterly sampling locations: four soil locations, four water locations (when water is available), and fourteenvegetationlocations. The totalnumber ofsamples taken during this reporting period is 86 (16 soil samples, 14 water samples, and 56 vegetation samples).

The annual average concentration oftotal net beta radioactivity (minus tritium) for samples collected at each environmental soil, water, and vegetation sampling location (sampling station) is listed in Table V.E.3. Calculation of the total net beta disintegration rate incorporates subtraction of only the counting system background from the gross beta counting rate, followed by application of an appropriate counting system efficiency.

The annual average concentrations were calculated using sample results which exceeded the lower limit ofdetection (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 theaverageLLD concentration and the range ofLLD valuesforeachsamplecategoryfor 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 radionucides is not routinelycarried out as part ofthis monitoring program, but would be conducted ifunusualradioactivitylevels above natural background were detected. However, fromTableV.E.3 it canbe seenthat the levels ofradioactivity detected were consistent with naturally occurring radioactivity and comparable to values reported in previous years.

F.

Radioactive Material Shipments Asummaryofthe radioactive material shipments originating fromthe TRIGA reactor facility, NRC license R-106, is shown in Table V.F. 1. A similar summary for shipments originating from the Radiation Center's state ofOregon 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 10 CFR 110.23 is shown in Table V.F.3.

Protection V-8 L

G.

References

1.

U. S. EnvironmentalProtectionAgency, "Estimates oflonizing RadiationDoses inthe United States, 1960-2000," ORP/CSD 72-1, Office ofRadiation Programs, Rockville, Maryland (1972).

2.

U. S. EnvironmentalProtectionAgency, "Radiological Qualityofthe Environment inthe 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 Perfonn routine area radiation/contamination monitoring.

Perform routine response checks of radiation monitoring instruments.

Monitor radiation levels (irem h-l) 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.

Quarterlbr 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.

I l

-L-1 Protection V-10

r -r I

r--

r--- r r

I r--

r -

r F

r- -- '

I --

[-- I -

Table V.B.1.a Monthly Summary of Liquid Effluent Releases to the Sanitary Sewer1'2 )

(OSTR Contribution Shown in () and Bold Print)

Specific Activity For T

AegePercent of TtlVlm Each Detectable T

Quantity Aerage Applicable Monthly l olume Total Quantity Detectable Radionuclide in the of Each Concentraton of Average of Liqjuid of Radionuclides We Detectable Released Cocnrto o

Efluease Date of Discharge Radioactivity in Waste, Where the Radsonuclide Radioactive Concentration for Rel (Month and Year)

Released the Waste Release W Released in Material at the Released Including (Curies)

~~~~~>1 X~ 10 pCi/CM3 teWse Point of Release Material

~

l (Curies)________

(pCi x 1

'7 (Curies)

([lci ml')

(D/o) (3)

(gal)

April 2003 0

0 0

1696 Annual Total for 0

0 0

1696 Radiation Center 0

0 0

1696 OSTR Contributiont to N/A N/A N/A N/A N/A N/A N/A A bove "l.

(1)

OSU has implemented a policy to reduce to the absolute minimum radioactive wastes disposed to the sanitary sewer. There were no liquid effluent releases 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 disposal.

(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 a

-S.

3

'-S4 Dates of Waste Volume of Liquid Detectable Total Quantity of Pickup for Origin of Waste Radionuclides in Radioactivity in the Transfer to the Liquid Waste Packaged("

the Waste Waste (Curies)

Waste (gallons)

Processing Facility TRIGA Reactor None Facility Radiation Center 0.5 131I 5.00 x 10i 10/25/02 Laboratories TOTAL 0.5 131i 5.00 x 104 (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.

W.

W i.

I _

F-----

V ---

F-F

Table V.B.2 Monthly TRIGA Reactor Gaseous Waste Discharges and Analysis(')

Estimated

~Fraction of the Total Estimated Estimated Technical Total Estimated Quantity of Atmospheric Diluted Specification Month Activity Released Argont41 Concentration of Annual Average (Caries)

Releasedgo )

Argon41 at Point of Argon~l (Caries)

Reles Concentration Limit July 0.42 0.42 3.49E-08 0.87 August 0.37 0.37 3.09E-08 0.77 September 0.25 0.25 2.16E-09 0.54 October 0.39 0.39 3.27E-08 0.82 November 0.19 0.19 1.65E-08 0.41 December 0.19 0.19 1.63E-09 0.41 January 0.25 0.25 2.07E-08 0.52 February 0.16 0.16 1.51E-08 0.38 March 0.24 0.24 2.03E-08 0.51 April 0.18 0.18 1.56E-08 0.39 May 0.20 0.20 1.70E-08 0.43 June 0.37 0.37 3.26E-08 0.81 TOTAL

('02-'03) 3.21 3.21 2.28E-08 0.57 (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 argon41.

Protection V-13

IF Table V.B.3 Annual Summary of Solid Waste Generated and Transferred Dates of Waste Volume of Detectable Total Quantity Pickup for Origin of Solid Waste Red ouc ables of Radioactivity Transfer to the Solid Waste Packaged('O Radionuclides in Solid Waste OSU Waste (Cubic Feet) ste (Curies)

Processing Facility TRIGA M~~~~~'

3 CS, 46SC, 58CO, TRGA 6'Co, 4 n, 7 Se 46x10/25/02,1/9/03, Reactor 21.5 133 1 152Eu 141 045/23/03 Facility

,E,'L Radiation 14C, 4Sc, 47Sc, 10/25/02,1/9/03, Center 13.75

'1Co, "U, ~'Rb, 1.2 x 10~

02/2 //3 Laboratories Sr 232Th 5/23/03 TOTAL 35.25 See Above 4.7 x 104

-L

-L.

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

Protection V-14

Table V.C.1 Annual Summary of Personnel Radiation Doses Received Average Annual Greatest Individual Total Person-mrem Dose<')

Dose(')

For the Group(')

Whole Whole Whole Body Extremities Body Extremities Body Extremities (m__ _

_(mrem) mrem)

(mrem)

FacilityOperating 13 6

92 490 320

.954 Personnel Key Facility Research Personnel

<1 3

18 96 29 295 Facilities Services Maintenance Personnel 0

N/A 0

N/A Laboratouynass

<I 2

44 59 127 482 Students__

Campus Police and 1

N/A 19 N/A 58 N/A Security Personnel I

N__ __

9 N_ _

N_ _

Visitors

<1 N/A 8

N/A 81 N/A (1) "N/A" indicates that there was no extremitymonitoring conducted or required for the group.

Protection V-15

-I I1

Table V.D.1 Total Dose Equivalent Recorded on Area Dosimeters Located Within the TRIGA Reactor Facility Total Recorded Monitor TRIGA Reactor Dose Eq ivalentQX)(

I.D.

Facility Location WY)

Neutron (See Figure V.D.1)

(Mrem)

Neur MRCTNE D104:

North Badge East Wall 155 ND MRCTSE D104:

South Badge East Wall 112 ND MRCTSW D104:

South Badge West Wall 289 ND MRCTNW D104:

North Badge West Wall 91 ND MRCTWN D104:

West Badge North Wall 139 ND MRCTEN D104:

East Badge North Wall 324 ND MRCTES D104:

East Badge South Wall 916 ND MRCTWS D104:

West Badge South Wall 283 ND MRCTTOP D104:

Reactor Top Badge 343 ND MRCTHXS D104A: South Badge HX Room 375 ND MRCTHXW D104A: West Badge HX Room 153 ND MRCD-302 D302:

Reactor Control Room 196 ND MRCD-302A D302A: Reactor Supervisor's Office 48 N/A MRCBP1 D104: Beam Port Number 1 101 ND MRCBP2 D104: Beam Port Number 2 149 ND MRCBP3 D104: Beam Port Number 3 609 ND MRCBP4 D104: Beam Port Number 4 382 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 fiast 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.

i I

I

-L 1

i Protection V-16

Table V.D.2 Total Dose Equivalent Recorded on Area Dosimeters Located Within the Radiation Center Total Recorded Radiation Center Dose Ea ivalente')

Monitor Facility Location xj(y)

Neutron I.D.

(See Figure V.D.l)

(mrem)

MRCA100 A100:

Receptionist's Office ND N/A MRCBRF A102H:

Front Personnel Dosimetry Storage Rack 38 N/A MRCA120 A120:

Stock Room 44 N/A MRCA120A A120A:

NAA Temporary Storage ND N/A MRCA126 A126:

Radioisotope Research Lab 120 N/A MRCCO-60 A128:

"Co Irradiator Room 251 N/A MRCA130 A130:

Shielded Exposure Room 28 N/A MRCA132 A132:

TLD Equipment Room 24 N/A MRCA138 A138:

Health Physics Laboratory ND N/A MRCA146 A146:

Gamma Analyzer Room (Storage Cave)

ND N/A MRCB100 B100:

Gamma Analyzer Room (Storage Cave) 121 N/A MRCB114 B114:

a Lab (n6Ra Storage Facility) 1,431 ND MRCBI 19-1 B 19:

Source Storage Room 250 N/A MRCB119-2 B119:

Source Storage Room 834 N/A MRCB119A BI19A:

Sealed Source Storage Room 4,020 1831 MRCB120 B120:

Instrument Calibration Facility 27 N/A MRCB122-2 B122:

Radioisotope Storage Hood 40 N/A MRCB122-3 B122:

Radioisotope Research Laboratory 40 N/A MRCB124-1 B124:

Radioisotope Research Lab (Hood) 21 N/A MRCB124-2 B124:

Radioisotope Research Laboratory 48 N/A MRCB124-6 B124:

Radioisotope Research Laboratory 41 N/A MRCB128 B128:

Instrument Repair Shop 24 N/A MRCC100 C100:

Radiation Center Director's Office 19 N/A MRCC106A C106A:

Staff Lunch Room 12 N/A MRCC106B C106:

Solvent Storage Room 44 N/A MRCC106-H C106H:

East Loading Dock 43 N/A MRCC118 C118:

Radiochemistry Laboratory 22 N/A MRCC120 C120:

Student Counting Laboratory 17 N/A MRCF100 F100:

APEX Facility 11 N/A Seefootnotesfollowing the table.

Protection V-17

I III Table V.D.2 (continued)

Total Dose Equivalent Recorded on Area Dosimeters Located Within the Radiation Center I

Total Recorded Radiation Center Dose E ulvalente')

Monitor Facility Location X(Y)

Neutron I.D.

(See Figure V.D.1)

(mrem)

MRCF102 F102:

APEX Control Room 13 N/A MRCB125N B125:

Gamma Analyzer Room (Storage Cave)

ND N/A MRCB125S B125:

Gamma Analyzer Room 34 N/A MRCC124 C124:

Student Computer Laboratory 39 N/A MRCC130-1 C130:

Radioisotope Laboratory (Hood) 10 N/A MRCD100 D100:

Reactor Support Laboratory 164 N/A MRCD102 D102:

Pneumatic Transfer Terminal Lab 247 ND MRCD102-H DI02H:

Ist Floor Corridor at DI02 68 ND MRCD106-H D106H:

Ist Floor Corridor at D106 138 N/A MRCD200 D200:

Reactor Administrators's Office 181 ND MRCD202 D202:

Senior Health Physicist's Office 180 ND MRCBRR D200H:

Rear Personnel Dosimetry Storage Rack 54 N/A MRCD204 D204 Health Physicist Office 122 ND MRCF104 F104:

ATHRL 44 ND MRCD300 D300:

3rd Floor Conference Room 115 ND I

i (I)

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 vendors gamma dose reporting threshold of 10 mrem or that each of the fast neutron dosimeters was less than the vendor's threshold of 10 mirem. "N/A" indicates that there was no neutron monitor at that location.

Protection V-18

-I

-tL

-t

-i

Table V.D.3 Annual Summary of Radiation Levels and Contamination Levels Observed Within the Reactor Facility and Radiation Center During Routine Radiation Surveys Whole Body Contamination Accessible Location Radiation Levels Levels(')

(See Figure V.D.1)

(mre (dpmlcm2 Average Maximum Average Maximum TRIGA Reactor Facility:

Reactor Top (D104) 1 70

<500 1250 Reactor 2nd Deck Area (D104) 4 38

<500 1000 Reactor Bay SW (D104)

<1 3

<500 1000 Reactor BayNW (D104)

<1 5

<500 3250 Reactor BayNE (D104)

<1 6

<500 3800 Reactor Bay SE (D104)

<1 14

<500 2250 Class Experiments (D104, D302)

<1

<500

<500 Demineralizer Tank-Outside Shielding (D104A)

<1 2

<500

<500 Particulate Filter-Outside Shielding (D104A)

<1

<500 9800 Radiation Center:

NAA Counting Rooms (A146, B100)

<1

<500

<500 Health Physics Laboratory (A138)

<1

<500

`0Co Irradiator Room and calibration

<1

<500

<500 rooms (A128, A130, B120)

Radiation Research Labs (B108, B114, B122, B124, C130, C132A)

<500

<500 Radioactive Source Storage (AI20A, B 19,

<1 2

<500

<500 BI 19A)

Student Chemistry Laboratory (C 18)

<1

<500

<500 Student Counting Laboratory (C120)

<1

<500

<500 Operations Counting Room (B136, C123)

<1

<500

<500 Pneumatic Transfer Laboratory (D102)

<1 3

<500 600 TRIGA Tube Wash Room (D1OO)

<1

<500

<500 (1) <500 dprn/100 cm2 = Less than the lower limit of detection for the portable survey instrument used.

Protection V-19

I.

i 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 pirem h7l Station TLDs0')

TLDs°23 Dose Rate°3 (See Figure V.E.1)

(mrem)

MRCFE-1 93*3 58*6 69* 15 MRCFE-2 90*2 52 +/- 3 65

13 MRCFE-3 83 2

53 +/- 3 62 +/- 14 MRCFE-4 87 2 55*5 65* 14 MRCFE-5 81 3

49

3 61 +/- 15 MRCFE-6 89+/- 1 54+/- 4 68

16 MRCFE-7 85 +/- 2 54

4 64+/- 13 MRCFE-8 84+ 2 51

4 57* 13 MRCFE-9 81*1 I 50

6 63

18 i

-J-(1)

Average Corvallis area natural background using ICN TLDs totals 74

5 mrem for the same period.

(2)

OSU fence totals include a measured natural background contribution of 55 i 3 mrem.

(3)

+ values represent the standard deviation of the total value at the 95% confidence level.

1-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 prem/h Station(O)

TLDs°)

TLDsOXO)

Exposure Rate()

(See Figure V.E.2)

(mrem)

(inrem)

(mrem)

MRCTE-2L 51

3 53

11 MRCTE-3 88 d:1 54* 5 69

17 MRCTE-4 81*1 591 10 81 +/-16 MRCTE-SL 47

12 59*: 14 MRCTE-6 76 *1 46

5 61 9

MRCTE-7L 46 +/- 6 72 14 MRCTE-8 95 *1 57 *:8 74* 14 MRCTE-9 88 *1 48

6 691+

I MRCTE-10 82*1 I 53* 9 56

17 MRCTE-12 89 I

59* 7 61

13 MRCTE-13L 53 *E7 69*E 9 MRCTE-14L 43

6 49* 14 MRCTE-15 74* 3 47 + 5 42

10 MRCTE-16L 53

10 66 12 MRCTE-17 80*1 57* 12 55* 11 MRCTE-18L 49 5

56* 13 MRCTE-19 89* 1 56 4 74

10 MRCTE-20L 52*7 60* 11 MRCTE-21 74*2 49*6 47* 13 MRCTE-22 79* 1 44*4 52 *7 (1)

Monitoring stations coded with an "L" contained one standard OSU TLD pack only. Stations not coded with an Lt contained, in addition to the OSU TLD pack, one ICN TLD monitoring pack.

(2)

Average Corvallis area naftual background using ICN TLDs totals 74

5 mrcm for the same period.

(3)

OSU off-Site totals include a measured natunal background contribution of 55 4 3 srem.

(4)

values represent the standard deviation of the total value at the 95% confidence lveL Protection V-21

I i

Table V.E.3 Annual Average Concentration of the Total Net Beta Radioactivity (Minus 3H) for Environmental Soil, Water, and Vegetation Samples i

Sample Annual Average Concentration iLocation Sample of the Total Net Beta (Mnus Reporting (See Figure Type RadloactivlW' units V.E.2) 1-W Water 2.35E-07

6.96E-7(2) uCi ml" 4-W Water 4.38E-8:E 1.21E-08°)

uCi ni-t I -W Water 6.12E-08 4 1.37E-09(2) uCi ml' 19-RW Water 6.47E-08

1.43E-08°2 )

uCi Mnr, 3-S Soil 3.41E-OS 5 4.97E-05 uCi g ' of dry soil 5-S Soil 1.97E-05

4.78E-06 uCi g ' of dry soil 20-S Soil 2.00E-05 1.45E-05 uCi g' of dry soil 21-S Soil 4.3913-O5 A: I.73E-05 tLCi g-' of dry soil 2-G Grass 2.55E-4 *L 2.01E-04 Ci g ' of dzy ash 6-G Grass I.95E-04* 1.80E-04 uCi g ' of dry ash 7-G Grass 3.13E-04

3.62E-05 uCi g' of dry ash 8-G Grass 2.98E-04 : 1.74E-04 juCi g' of dry ash 9-G Grass 2.49E-04

1.71E-04 uCi g-' of dry ash IO-G Grass 2.57E-04 : 3.21E-04 uCi g-' of dry ash 12-G Grass 3.54E-04 + 1.06E-04 uCi g-' of dry ash 13-G Grass 3.49E-04

1.73E-04 uCi g' of dry ash 14-0 Grass 2.OOE-04* 2.12E-04 uCi g" of dry ash 15-G Grass 1.73E-04 1.48E-04 uCi g' of dryash 16-G Grass 3.08E-04* 1.93E-04 uCi g-' of dry ash 17-0 Grass 2.88E-04 t 2.07E-04 uCi g-of dry ash 18-G Grass 2.37E-04 +/- 2.64E-04 Ci g-' of d&y ash 22-G Grass 3.92E-04

1.55E-04 uiCi sC' of dr ash

1 LI II, LI 1

A I

I (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 I

I

Table V.E.4 Average Beta-Gamma 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 1.25E-05 8.76E-06 to 1.77E-05 IiCi g' of dry soil Water 1.12E-07 5.97E-08 to 6.43E-07 pCi mY' Vegetation 3.44E-05

1. 14E-05 to 6.65E-05 VCi g of dry ash Protection V-23

I I

Table V.F.1 Annual Summary of Radioactive Material Shipments Originating From the TRIGA Reactor Facility's NRC License R-106 Total Number of Shipments Shipped To Activlty L

(TBq)

Limited Yellow Yellow (T13q)

Quantity II I

Total Berkeley Geochronology Center Berkeley, CA USA

~~8.83E-06 91 0

10 Berkeley, CA USA Cal State Fullerton 5

i Fullerton, CA USA California Institute of Technology Pasadena, CA USA 1.12E-05 I

0 l

0 Columbia University l~~.60E-06I 2

0 0

2 Palisades, NY USA General Dynamics I

Scottsdale, AZ USA 1.07E-06 0

0 1

Idaho State University 2.51E-5 0

4 0

4 Pocatello, ID USA Nu-Trek, Inc I

Poway, CA USA 8.55E-06]

0 1

Oregon State University Corvallis,OR USA 1.51E-04 3 1 0

1 Plattsburgh State University 1.29E-06 2

0 0

2 Plattsburgh, NY USA I

1.29E-0 O

O 1

Rutgers i

I 0

0 Piscataway, NJ USA I

Stanford University 1.50E-06 3

0 0

3 Stanford, CA USA I

1.50E-06 3_l_0_I_0_l Syracuse University 1.16E-06 2

0 0

2 Syracuse, NY USA Union College 3

I 4

Schenectady, NY USA 3

0 University of California at Berkeley j2 0

0 2

Berkeley, CA USA I

3.44E-06 2

0__0__

University of California at Santa Barbara 2

5 0

0 5

Santa Barbara, CA USA I

I i

1 I1 Il 1

~i I,

I 1

LI Li I

LI Li I1 Protection V-24 A

Table V.F.1 (continued)

Annual Summary of Radioactive Material Shipments Originating From the TRIGA Reactor Facility's NRC License R-106 I Total Number of Shipments Shipped To Activity L

I TB )

Limited Yellow Yellow

_IQuantity

]I III Total University of Florida 5.82E-06 I

1 0

2 Gainesville, FL USA 5

1 0

l 2

University of Southern California l

j Los Angeles, CA USA 1.03E-06 2

0 0

2 University of Washington Seattle, WA USA 1.83E-06 3

O O

3 University of Wisconsin-Madison 2.98E.05 1

3 Madison, WI USA 2

l Totals J 2.61E-04 43 14 0

57 Protection V-25

I i

Table V.F.2 Annual Summary of Radioactive Material Shipments Originating From the Radiation Center's State of Oregon License ORE 90005 1 Total Number of Shipments Totalt Limited White Yellow Shippe ToLQuantity I

H Total Lawrence Berkeley National Laboratory 5.OOE-08 7

1 I

0 0

8 Berkeley, CA USA PGE Trojan Nuclear Plant 1.60E-06 0

1 I

0 0

1 Rainier, OR i

Totals 1.65E-06 7

2 0

0 9

LI ii-LL Li II I1 I

i I

I I

A Protection V-26 I

Table V.F.3 Annual Summary of Radioactive Material Shipments Exported Under NRC General License 10 CFR 110.23 1Total Number of Shipments Shipped~~

~

ToToAtivtyl Shipped To Activity Limited Yellow Yellowl l T q)

Quantity II HII Total Geological Institute Copenhagen, DENMARK 4.87E-07 1

O 0

Polish Academy of Sciences Krakow, POLAND

[ 7.77E-09 1

0 0

Ruhr-Universitat Bochum I

I Bochum,, GERMANY 3.26E-08 1 1 0

0 I

Scottish Universities Research and Reactor Centre I

I East Kilbride, SCOTLAND 5.49E-07 1 I 0

0 l

1 Universita'Degi Studi di Bologna l

4.63E-07 1

0 1

Bologna, ITALY O i Universitat Potsdam Postdam, GERMANY 5.06E-08 I

0 7

Universitat Tubingen 6

I I

3 Tubingen, GERMANY 6.01E-07 3

0 0

3 University of Geneva Geneva, SWITZERLAND University of Montpellier I

I I

Montpellier, FRANCE 8.76E07 j 2

j 0

0 2

University of Queensland 5

0 3

Brisbane, Queensland AUSTRALIA I0 I

Totals I 8.99E-06 18 1 3 10 21 Protection V-27

.i Figure V. D. I Monitoring Stations for the OSU TRIGA Reactor

'i I'

I i

I I

I loam 'UU3LOCA1=SW=WT Or=AVTMCrA WM~A=A1ZM I

Protection V-28 I

l Part VI Worlk

Part VI WORK A.

Summary The Radiation Centeroffers awidevarietyofresourcesforteaching, research, and service related to radiation and radioactive materials. Some ofthese are discussed in detail in other parts ofthis report. The purpose ofthis part is to summarize the teaching, research, and service efforts carried out during the current reporting period.

B.

Teaching An important responsibility ofthe Radiation Center and the reactor is to support OSUs academic programs. Inmlementation ofthis support occurs through direct involvement ofthe Centers staff andfacilitiesintheteachingprogrmsofvarousdepartmtsandthroughparticipationinUniversity research programs. For example, during the current reporting period, the Radiation Center accommodated 74 academic classes involvinganumberofdifferent academicdepartments from OSU and other Oregon universities. The OSU teaching programs (not including research) utilized 28 hours3.240741e-4 days 0.00778 hours 4.62963e-5 weeks 1.0654e-5 months ofreactor time. Tables III.A. 1 and III.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 servicework is tracked bymeans ofaproject database.

When a request for facilityuse is received, aproject 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 project, Radiation Center resources needed, the Radiation Center project manager, status of individual runs, billing information, and the funding source.

Table VI.C. 1 provides a summary of institutions which used the Radiation Center during this reporting period. This table also includes additional information about the number ofacademic personnel involved, the number of students involved, and the number ofuses logged for each organization. Details on graduate studentresearchwhichusedthe RadiationCenter 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 Work VI-1

personneland institutioninvolved, thetypeofproject, andthefunding agency. Projectswhichused 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 ofmajor, minor, trace, and rare elements. The principle involved inNAA consists of first irradiating a sample with neutrons in a nuclear reactor such as the OSTR to produce specific radionuclides. After the irradiation, the characteristic gamma rays emitted by the decaying radionuclides are quantitatively measured by suitable semiconductor radiation detectors, and the gamma rays detected at a particular energyare i

usuallyindicative ofa specific radionucide's presence. Computerized datareduction of the gammarayspectrathenyields the concentrations ofthevarious elements insamples 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 of detection is on the order ofparts per million orparts per billion, depending on the element.

I The Radiation Center's NAA laboratoryhas analyzed the major, minor, and trace element i content oftens of thousands of samples covering essentially the complete spectrum of material types and involving virtually every scientific and technical field.

While someresearchersperformtheirownsamplecounting ontheir own or onRadiation Centerequipment, the Radiation Centerprovides a completeNAA service for researchers and others who mayrequire it. This includes sample preparation, sequential irradiation and L

counting, and data reduction and analysis.

Data onNAAresearchand serviceperformed during thisreportingperiod are included in Table VI.C.3.

2.

Forensic Studies Neutron activation analysis can also be advantageouslyused in criminal investigations. The principle underlying such application usually invo lves matching trace element pro files in objects orsubstancesbyNAA. Thisintum canhelp identifymaterials orproducts(e.g.,

identifythenmanufacturerofagivenobject), and insome casescanmatchbullets andother materialsrecoveredfromavictinto similarmaterials obtained from suspects. Materials whichhavebeen analyzedbytheRadiationCenter for forensicpurposes includebullets, metals, paint, fuses, coats, glass, meat, and salts.

Work VI-2

Forensic studies performed inthis reportingperiod 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 irradiationofalargevarietyofsubstanceswithgammarays 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 emergencyresponse team capable ofresponding to all types ofradiological accidents. This team directly supports the City ofCorvallis and Benton County emergency response organizations and medical facilities. The team can also provide assistance at the scene of anyradiological incident anywhere in the state of Oregon onbehalfofthe Oregon Radiation Protection Services and the OregonOffice ofEnergy.

The Radiation Center maintains dedicated stocks of radiological 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.

5.

Training and Instruction In addition to the academic laboratory classes and courses discussed in Parts III.A.2, III.D, andVI.B, and inadditionto theroutine trainingneeded to meet the requirements of the OSTR EmergencyResponse Plan, Physical SecurityPlan, and operator requalification program, the Radiation Center is also used forspecialtrainingprograms. RadiationCenter staffarewell experienced in conducting these special programs and regularlyoffer 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.

Special trainingprograms generallyfall into one ofseveral categories: visitingffacultyand research scientists; International Atomic Energy Agency fellows; special short-term courses; or individualreactor operator orhealthphysics training programs. During this reporting period there were a large number of such people as shown in Part II.B.

Work VI-3

-ti 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.

I

6.

Radiation Protection Services The primarypurpose ofthe radiation protectionprogram 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 ofexpertise and equipment available, the Radiation Center is also able to provide health physics services in support ofOSU Radiation Safety and to assist other state and federal agencies. The Radiation Center does not compete withprivate 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.

i The Radiation Center is capable ofproviding healthphysics services in anyofthe areas which are discussed in Part V. These include personnel monitoring, radiation surveys, sealed source leak testing, packaging and shipment ofradioactive materials, cahbration 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 I

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 ofa radiological emergency within the state of Oregon. In this role, the Radiation Center will provide gamma ray spectrometric analysis ofwater, soil, milk, food products, vegetation, and air samples collected by OSHD radiological response field teams. As part ofthe ongoing preparation frthis emergency support, the Radiation Centerparticipates in inter-institution I

drills.

7.

Radiological Instrument Repair and Calibration While repair ofnuclear instrumentation is apracticalnecessity, routine calibrationofthese instruments is a licensing and regulatoryrequirement which must be met. As a result, the Radiation Center operates a radiation instrument repair and calibration facilitywhich can accommodate a wide variety of equipment.

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

Work VI-4

In addition to the instrument repair capability, the Radiation Center has a facility for calibratingessentiallyalltypes ofradiation monitoring instruments. This includes typical portablemonitoringinstrumentationforthedetectionandmeasurement ofalpha, 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 certifiedbytheNationalInstitute ofStandards and Technology(NIST) ortraceable 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 andthe OSTREmergencyPlan, while Table VI.C.5 shows instruments calibrated for other OSU departments and non-OSU agencies.

8.

Consultation Radiation Center staffare available to provide consultation services in any ofthe 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 telephoneconversationswithresearchers encounteringproblems orplanning the designof 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 because they were in the vicinity, a total of 99 scheduled tours including 1,287 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 I

Number of Number of Number of Institution Numbects° Faculty Students UCse te Projectsw ~~~vo~~ve~~

hvo~v~

Facilities Oregon State Universityf 20 21 3

97 Corvallis, OR USA

Oregon State University - Educational Tours CorvallisOR USA l5 13 0

52 AVI Bio Phanna CanahkOR USA

~

~~1 0

0 4

Corvallis, ORUSA Corvallis Clinic 0

0 1

Corvallis, OR USA I

Crmscent Valley High School 1

1 0

1 Corvallis, OR USA l

1 O_1

Linn Benton Community College 1

0 0

6 Albany, OR USA I

O O_6 Marist High School 1

0 0

1 Eugene, OR USA 0

0

McKay High School 1

0 0

1 Sakm, OR USA 0_0_I National Council of Stream and Air Inprovement 1

1 0

4 Corvallis, OR USA IIO_4

Non-Educational Tours I

0 0

29 Coalls OR USA l

O O_29 University of Oregon 3

3 0

4 Eugene, OR USA York Engineering Corvallis, OR USA 2

Douglas High School 0

Roseburg, OR USA II_0 Hemcon, Inc.

1 0

0 2

Tigard, OR USA IOO_2

Madison High School Portland, OR USA 1

Neahkahnie High School Rockaway Beach, OR USA I

If I

I 1

I I

1 I

A Work VI - 6 A

Table VI.C.1 (continued)

Institutions and Agencies Which Utilized the Radiation Center Number of Number of Number of institution Nmer Faculty StudentsU

.rojects.3)

Involved Involved CaeInte

Prodence Medical Center Portland, OR USA 1_I_0_1 Providence St. Vincent Hospital 1

0 0

19 Portland, OR USA 19 Rogue Community College 1

0 0

1 Chants Pass, OR USA

Thurston High School I

I 0

1 Springfield, OR USA

Idaho State University I

0 2

Pocatello, E) USA

University of Washington 2

2 0

4 Seattle, WA USA

Berkeley Geochronology Center 1

0 4

16 Berkeley, CA USA

Cal State Fullerton 1

1 2

1 Fullerton, CA USA Nu-Trek, Inc 1

0 0

2 Poway, CA USA

Stanford University 2

2 0

3 Stanford, CA USA

University of California at Berkeley 2

2 0

2 Berkeley, CA USA

University of California at Santa Barbara 2

3 5

3 Santa Barbara, CA USA

University of Southern California 1

1 0

2 Los Angeles, CA USA

General Dynamics I

0 1

Scottsdale, AZ USA s* ovic Ltd 1

0 0

16 Grand Junction, CO USA 1

0_0_16

University of Wisconsin 2

2 5

8 Madison, WI USA Columbia University I

1 2

Palisades, NY USSA I

I _

I Work VI-7

-1 Table VI.C.1 (continued)

I Institutions and Agencies Which Utilized the Radiation Center t

Number of Number of Number of Institution Number of Faculty Students UCsentrf Involved Involved Facilitle

George Washington University 1

0 1

Washington, DC USA

North Carolina State University I

1 O

I Raleigh, NC USA

Pattsburgh State University 2

2 0

2 Plattsburgh, NY USA

Syracuse University 1

1 3

1 Syracuse, NY USA

Union College 3

3 O

4 Schenectady, NY USA

Rutgers 1

I 1

4 Piscataway, NJ USA

Univrsity of Florida I

I O

3 Gainesville, FL USA Vectron International Norwalk Inc.

I O

I Norwalk, CT USA

Scottish Universities Research and Reactor Centre I

O O

3 East Kilbride, SCOTLAND University of Montpellier I

0 0

3 Montpellier, FRANCE

GeoFbschunVZentnnn Potsdam I

I 0

3 Potsdam, GERMANY

Geological Institute I

O O

1 Copenhagen, DENMARK Polish Academy of Sciences 1

O O

1 Kralcow, POLAND

Ruhr-Universitat Bochum 2

2 0

3 Bochum, GERMANY

Universita' Degli Studi di Bologna 1

2 0

1 Bologna, ITALY

Unversitat Potsdam I

O O

4 Potsdan, GERMANY

University of Tuebingen I

1 3

3 Tuebingen, GERMANY i

I 1

I I

I I,

Work VI-8 I

Table VI.C.1 (continued)

Institutions and Agencies Which Utilized the Radiation Center Number of Number of Number of Institution Number of Faculty Students UCsesterf ProJeCtS03)

Involved involved Faciities

University of Queensland Brisbane, Queensland AUSTRALIA 3

Total 95 77 41 333

Project which involves the OSTR (1) Use by Oregon State University does not include any teaching activities or classes accommodated by the Radiation Center.

(2) This number does not include ongoing pnojects 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.

(3) This does not include projects pertaining to instrument calibretions.

Work VI - 9

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

Link, PhD Mineralogy Rahn 1595 Fission track dating of Mid-Katharina European Rhine graben shoulder uplift 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 4OAr/39Ar Geochronology

Zhou, MA Earth and Planetary Renne 920 Rates and Tempo of Permian-Zhensheng Science Triassic Boundary Events.

Cal State Fullerton

Irwin, MS Geological Sciences Armstrong 1625 Uplift of the Puente Hills using Christine fission track data Oregon State University

Huang, PhD Chemistry Loveland 1598 Zhongliang

Sinton, PhD Oceanography Duncan 444 Age and Composition of Two Christopher Large Igneous Provinces: The North Atlantic Volcanic Rifted Margin and the Caribbean Plateau Rutgers

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

i i

Work VI-10

Table VI.C.2 (continued)

Graduate Student Research Which Utilized the Radiation Center Student's Name Degree Academic Department Scottish Universities Research and Reactor Centre

Barry, PhD Leicester University T.

Blecher, PhD Oxford University J.

Cam, PhD Cambridge University S.

Chambers, PhD Edinburgh University L.

Dixon, PhD Bristol University H.

Harford, PhD Bristol University C.

Heath, PhD Lancaster University E.

May, PhD Aberdeen University G.

McElderry, PhD Liverpool University S.

Najman, PhD Edinburgh University Y.

Purvis, PhD Edinburgh University M.

Shelton, PhD Queens University R.

Sowerbutts, PhD Edinburgh University A.

Faculty Advisor Project Thesis Topic Pringle Pringle Pringle Pringle Pringle Pringle Pringle Pringle Pringle Pringle Pringle Pringle Pringle Work VI-1 1073 1073 1073 1073 1073 1073 1073 Mongolian Basalts/Tectonics Aden Volcanic Differentiation Indonesian Volcanics North Atlantic Tertiaiy Province Subglacial Volcanics Montserrat Volcanic Hazards St. Vincent Volcano Hazards 1073 1073 1073 1073 1073 Chilean Basins Chilean Tertiary Faulting Himalayan Foredeep Turkish Basin Tectonics North Channel Basin Evolution 1073 Sardinia Evolution

Table VI.C.2 (continued)

Graduate Student Research Which Utilized the Radiation Center Student's Name Degree Academic Department Faculty Advisor Project Thesis Topic

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

White, PhD Leicester University Pringle 1073 Caribean Crustal Growth R

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 Universitat Tubingen 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 California at Santa Barbara

Calvert, PhD Geological Sciences Gans 1020 Tectonic Studies in Eastern-Most Andy Russia

Nauert, MS Geological Sciences Gans 1020 Volcanism in the Eldorado Jon Mountains, Southern Nevada I

I LI LI Li LI 1i Work VI-12

Table VI.C.2 (continued)

Graduate Student Research Which Utilized the Radiation Center Student's Name Degree Academic Department Faculty Advisor Project Thesis Topic University of Manchester

Flude, PhD Earth Sciences Burgess 1592 Rhyolite volcanism in Iceland:

Stephanie timing and timescales of eruption University of Wisconsin Barquero-Molina, PhD Geology and Geophysics Singer 1612 Miriam

Harper, MS Geology and Geophysics Singer 1612 Melissa

Jicha, MS Geology and Singer 1465 Brian Geosciences

Jicha, MS Geology and Geophysics Singer 1612 Brian

Relle, MS Geology and Geophysics Singer 1465 Monica 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 Hilgen/Wijbrans 1074 Intercalibration of astronomical Klaudia and radioisotopic timescales Work VI-13

IL I

Table VI.C3 Listing of Major Research and Service Projects Performed or In Progress at the Radiation Center and their Funding Agencies i

Project Users Organization Name Project Title Description Funding 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 Instrument calibration.

Oregon Health Sciences University Sciences University 488 Farmer Oregon State Instrument Calibration Instrument calibration.

OSU Radiation University Center 519 Martin US Environmental Instrument Calibration Instrument calibration.

USEPA-Corvallis Protection Agency 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 Instrument calibration.

USEPA, Protection Agency Calibration Cincinnati, OH 664 Reese Oregon State Good Samaritan Hospital Instrument calibration.

OSU Radiation University Instrument Calibration Center 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 Stanford University Ar-40/Ar-39 Dating of Geological Samples Irradiation of mineral grain samples for specified times to allow Ar-40/Ar-39 dating.

Stanford University Geological &

Environmental Sci I

i I

INAA = Instrumental Neutron Activation Analysis REE = Rare Earth Elements 1

Work VI-14 1

Table VI.C.3 (continued)

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 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 Instrument calibration.

Occupational Health Lab Instruments 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 Markos Army Corps of Instrument Calibration Instrument calibration.

U.S. Army Engineers 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 4OAr-39Ar dating of rocks Vrije Rocks and Minerals and minerals.

Universiteit, Amsterdam 1075 Teaching and Tours 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.

INAA = Instrumental Neutron Activation Analysis REE = Rare Earth Elements Work VI-15

i Table VI.C.3 (continued)

Listing of Major Research and Service Projects Performed or In Progress at the Radiation Center and their Funding Agencies i

Project Users Organization Name Project Title Description Funding 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, 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 sanidine 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; hormblends and feldspar from the Amazon to assess climatic changes and differences in Amazon drainage basin provenance.

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

1354 Wright Radiation Radiological Instrument Instrument calibration.

Oregon Health Protection Services Calibration Division 1..

I i

I A

II II I

I INAA = Instrumental Neutron Activation Analysis REE - Rare Earth Elements lI Work VI-16 I

Table VI.C.3 (continued)

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 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 tJniversite Paris-Ar-Ar Geochronology Deterrnination of geological Universite Paris-Sud samples via Ar-Ar Sud radiometric dating.

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 1406 Pate Tracerco Production of Argon-41 Production ofArgon-41 for Tracerco various field uses 1415 McGinness ESCO Corporation Calibration of Instruments Instrument calibration ESCO Corporation 1423 Turrin Rutgers 40Ar/39Ar Analysis Petrology and geochemical Department of evolution of the Darnavand Geological trachyandesite volcano in Sciences Northern Iran.

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 Patterson AVI Bio Pharma Instrument Calibrations Instrument calibration AVI Bio Pharma 1464 Slavens USDOE Albany Instrument Calibration Instrument calibration.

USDOE Albany Research Center Research Center INAA = Instrumental Neutron Activation Analysis REE = Rare Earth Elements Work VI - 17

I Table VI.C.3 (continued)

Listing of Major Research and Service Projects Performed or In Progress at the Radiation Center and their Funding Agencies

'Ii Project Users Organization Name Project Title Description Funding 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 Kirner Kirner Consulting, Instrument Calibration Instrument calibration.

Kirner Consulting Inc 1468 Nitsche University of Chemistry 146 Experiment Sample irradiations for University of California at Chemistry 146 class California at Berkeley Berkeley 1470 Bolken SIGA Instrument Calibration Instrument calibration.

Siga Technologies, Inc.

Pharmaceuticals 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 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 i

I1 i-INAA - Instrumental Neutron Activation Analysis REE - Rare Earth Elements L

Work VI-18 I

Table VI.C.3 (continued)

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 1502 Teaching and Tours Portland Portland Community OSTR tour and half-life USDOE Reactor Community College Tours/Experiments experiment.

Sharing College 1503 Teaching and Tours Non-Educational Non-Educational Tours Tours for guests, university OSU Radiation Tours functions, student Center recruitment.

1504 Teaching and Tours Oregon State OSU Nuclear Engineering OSTR tour and reactor lab.

USDOE Reactor University -

& Radiation Health Sharing Educational Tours Physics Department 1505 Teaching and Tours Oregon State OSU Chemistry OSTR tour and half-life USDOE Reactor University -

Department experiment.

Sharing Educational Tours 1506 Teaching and Tours Oregon State OSU Geosciences OSTR tour.

USDOE Reactor University -

Department Sharing Educational Tours 1507 Teaching and Tours Oregon State OSU Physics Department OSTR tour.

USDOE Reactor University -

Sharing Educational Tours 1508 Teaching and Tours Oregon State Adventures in Learning OSTR tour.

USDOE Reactor University -

Class Sharing Educational Tours 1509 Teaching and Tours Oregon State HAZMAT course tours First responder training tours. Oregon Office of University -

Energy Educational Tours 1510 Teaching and Tours Oregon State Science and Mathematics OSTR tour and half-life USDOE Reactor University -

Investigative Learning experiment.

Sharing Educational Tours Experience 1511 Teaching and Tours Oregon State Reactor Staff Use Reactor operation required OSU Radiation University -

for conduct of operations Center Educational Tours testing, operator training, calibration runs, encapsulation tests and other.

INAA = Instrumental Neutron Activation Analysis REE - Rare Earth Elements Work VI-19

I i

Table VLC3 (continued)

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 OSTR tour and half-life USDOE Reactor Community College Tours/Experiments experiment.

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

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

1520 Teaching and Tours Western Oregon Western Oregon University OSTR 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 1525 Teaching and Tours Life Gate High Life Gate High School OSTR tour and half-life USDOE Reactor School experiment.

Sharing 1526 Crawford Hot Cell Services Instrument calibration Instrument calibration.

Hot Cell Services 1527 Teaching and Tours Oregon State Odyssey Orientation Class OSTR tour.

USDOE Reactor University -

Sharing Educational Tours 1528 Teaching and Tours Oregon State Upward Bound OSTR tour.

USDOE Reactor University -

Sharing Educational Tours I

1 i

I 1

I I

1, I

i I.

I INAA = Instrumental Neutron Activation Analysis REE - Rare Earth Elements i

Work VI - 20 I

Table VI.C.3 (continued)

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 1529 Teaching and Tours Oregon State OSU Connect OSTR tour.

USDOE Reactor University -

Sharing Educational Tours 1530 Teaching and Tours Newport School Newport School District OSTR tour.

USDOE Reactor District Sharing 1531 Teaching and Tours Central Oregon Central Oregon OSTR tour.

USDOE Reactor Community Community College Sharing College Engineering 1535 Teaching and Tours Corvallis School Corvallis School District OSTR tour.

USDOE Reactor District Sharing 1536 Nuclear Oregon State Gamma Irradiations for Irradiation of samnples for OSU Radiation Engineering Faculty University NE/RHP 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 Department OSTR tour.

USDOE Reactor University -

Sharing Educational Tours 1538 Teaching and Tours Oregon State OSU Speech Department OSTR tour.

USDOE Reactor University -

Sharing Educational Tours 1539 Most Universitat Fission track studies Age dating by the fission Universitat Tubingen track method.

Tubingen 1540 Teaching and Tours McKay High McKay High School OSTR tour and half-life USDOE Reactor School experiment.

Sharing 1542 Teaching and Tours Oregon State Engineering Sciences OSTR tour.

USDOE Reactor University -

Classes Sharing Educational Tours 1543 Bailey Veterinary Instrument Calibration Instrument calibration.

Veterinary Diagnostic Diagnostic Imaging &

Imaging &

Cytopathology Cytopathology INAA = Instrumental Neutron Activation Analysis REE = Rare Earth Elements Work VI-21

Table VI.C.3 (continued)

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 1544 Teaching and Tours West Albany High West Albany High School OSTR tour and half-life USDOE Reactor School experiment.

Sharing 1545 Teaching and Tours Oregon State OSU Educational Tours OSTR tour.

USDOE Reactor University -

Sharing Educational Tours 1548 Teaching and Tours Willamette Valley Willamette Valley OSTR tour.

USDOE Reactor Community School Community School Sharing 1554 Fleischer Union College Fission Track Irradiations Use of fission track to USDOE Reactor determine age dating in Sharing apatites 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.

1558 Binney Oregon State Measurement of cross Irradiations to measure USDOE University sections for medical neutron cross sections for radionuclides medically important radionuclides.

1564 Krane Oregon State Measurement of neutron Measurement of neutron USDOE Reactor University capture cross sections capture cross sections.

Sharing i

i I

I i

1567 Johnson University of Houston Compositions of apatites from magnetite-rich segregation deposits in the Cornucopia stock, NE Oregon Study of chemical composition of apatites from magnetite deposits in Cornucopia stock to determine processes responsible for their genesis.

USDOE Reactor Sharing I

I I

I INAA - Instrumental Neutron Activation Analysis REE - Rare Earth Elements I

Work VI-22 I

Table VI.C.3 (continued)

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 1571 Hansen Geological Institute Fission track analysis Study of East Greenland Geological contionental margin to Institute determine thermotectonic evolution as an aid in understanding rifting and opening of a continental volcanic margin with formation of a new ocean.

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.

1578 Monie University of Fission Track Analysis of Use of fission tracks from U-University of Montpellier U-235 235 to determine 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.

1583 Teaching and Tours Neahkahnie High Neahkahnie High School OSTR tour.

USDOE Reactor School Sharing 1584 Teaching and Tours Reed College Reed College Staff &

OSTR tour.

USDOE Reactor Trainees Sharing 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 rhyolites.

1594 Teaching and Tours Jefferson High Jefferson High School OSTR tour and half-life USDOE Reactor School experiment.

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

-it i

Table VI.C.3 (continued)

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 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.

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 octanoVwater partition Department coefficients for a series of chemically related organically bound metals.

1601 Crutchley Josephine County Instrument Calibrations Instrument calibration.

Josephine County Public Works 1602 Teaching and Tours Crescent Valley Crescent Valley High This project supports the USDOE Reactor High School School AP Physics Class 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.

1603 Teaching and Tours Thurston High Thurston High School OSTR tour and half-life USDOE Reactor School Chemistry experiment.

Sharing 1604 Buckovic Geovic Ltd.

Support of Cobalt-Nickel Analysis of Co/Ni in soil Geovic, Ltd.

Laterite Analyses samples from Africa.

i

1 I

I I

INAA = Instrumental Neutron Activation Analysis REE = Rare Earth Elements I

Work VI-24

Table VI.C.3 (continued)

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 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.

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.

1611 Teaching and Tours Grants Pass High Grants Pass High School OSTR tour.

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 Silver Falls School District OSTR tour.

USDOE Reactor District Sharing 1614 Teaching and Tours Marist High School Marist High School OSTR tour and half-life USDOE Reactor experiment.

Sharing 1615 Teaching and Tours Liberty Christian Liberty Christian High OSTR tour and half-life USDOE Reactor High School School experiment.

Sharing 1616 Doyle Evanite Fiber Instrument Calibration Instrument calibration.

Evanite Fiber Corporation Corporation 1618 Teaching and Tours Fall City High Fall City High School OSTR tour and half life USDOE Reactor School experiment.

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

Table VI.C3 (continued)

I Listing of Major Research and Service Projects Performed or In Progress at the Radiation Center and their Funding Agencies A

Project Users Organization Name Project Title Description Funding 1619 Teaching and Tours Sheridan High Sheridan High School OSTR tour and half-life USDOE Reactor School experiment.

Sharing 1620 Teaching and Tours Eddyville High Eddyville High School OSTR tour.

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.

1623 Blythe University of Fission Track Analysis University of Southern California Southern California 1624 Porter Oregon State Irradiation of MacCema Testing of MacCema OSU Industrial &

University Buttons memory buttons for failure in Manufacturing high radiation (gamma only)

Engineering environments.

1625 Armstrong Cal State Fullerton Fission Track Irradiations Measurement of fission track USDOE Reactor ages to determine erosion Sharing amounts and timing.

1626 Eastburn Corvallis Clinic Radiation Survey Release survey of a Corvallis Clinic laboratory formerly using I-125 and Co-58.

LL i

1 1;

I I

I 1

I INAA - Instrumental Neutron Activation Analysis REE - Rare Earth Elements 1-Work VI-26 I

Table VI.C.3 (continued)

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 1627 Fleischer Union College Fission Track Irradiations The primary project is the USDOE Reactor use of tracks to study the Sharing leaching out of imbedded radionuclides from alpha-activity in materials. The radionuclide could be a decay product of U-238 or Th-232 in studying the geochemistry of natural materials, or of Rn-222 in dealing with environmental materials that are used to assess radon exposures.

Here we will use an analogue case - the embedding in the laboratory of U-235 recoils from the alpha activity of Pu-239.

1628 Garver Union College Fission Track Irradiations Use of fission track to USDOE Reactor determine age dating of Sharing apatites.

1629 Rauch Nu-Trek, Inc GaAs 1 MeV Equivalent Neutron damage to GaAs to Nu-Trek, Inc.

Damage Evaluation reduce carrier lifetime to make flash x-ray photoconductive detectors 1631 Sivaramakrishnan Oregon State Radiation Damage to GaAs Neutron damage to GaAs for USDOE Reactor University use in semiconductors Sharing 1633 Goles University of Evolution and lateral Selected terranes of the New USDOE Reactor Oregon growth of active Zealand basement contain Sharing continental margins metasediments that are ideal for testing the model and learning about the evolution of this part of the ancient Gondwana active margin; clasts of terrane congimerates will be characterized by INAA.

INAA = Instrumental Neutron Activation Analysis REE = Rare Earth Elements Work VI-27

Table VI.C.3 (continued)

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 1634 Tollo George REE Geochemistry of NAA of apatite samples to USDOE Reactor Washington Meta-Igneous Rocks using determine metal composition Sharing University INAA (TBC) in ingneous rocks.

1635 Fodor North Carolina Determination of REE's in To be edited when samples USDOE Reactor State University Ultrarnafic Rocks by NAA.

are received.

Sharing 1637 Johnson University of Geochemistry of gold The purpose of this project is USDOE Reactor Houston bearing horblendite vains to provide geochemical Sharing analysis of golde hornblendite veins that are gold mineralized and part of a larger porphyry copper stock.

1638 Lee University of Geochemistry of Relationships bewteen USDOE Reactor Oregon lithological matter to regional geologic features Sharing determine provenance can be contraint by the geochemical analysis of rocks in formations.

1640 Gans University of Age dating of Neogene Age dating of rock samples USDOE Reactor California at Santa volcanism from Sierra Nevada, Sonora, Sharing Barbara Mexico, and Chilean Andes 1641 Hughes Idaho State Independent Study of NAA Development of NAA for USDOE Reactor University Thesis Research Sharing 1643 York York Engineering INAA of Paint Scrapings The purpose of this York Engineering experiment is to determine the chemical composition of paint scrapings from marine vessels as a potential identification technique.

1645 Gustafson Oregon State Pulmonic and Vascular I am using a biomaterial to OSU Veterinary University Repair with Biomaterial repair an induced lung injury Medicine Patch, Phase 1: Acute in rabbits.

studies 1647 Graefe GeoForschungsZen Fission Track Irradiations Use of fission track to study GeoForschungsZe trum Potsdam zircon.

ntrum Potsdam 1

I I

I

.1 IL 1

I I

INAA = Instrumental Neutron Activation Analysis REE = Rare Earth Elements I

Work VI-28 1

Table VI.C.3 (continued)

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 1648 Stewart University of Fission-track Dating of Fission-track Dating of University of Washington Zircon Zircon from the Exhumation Washington of Avaloatz Mountians in California 1653 Teaching and Tours Madison High Madison High School OSTR tour.

USDOE Reactor School Senior Science Class Sharing 1655 Teaching and Tours Future Farmers of OSTR Tour OSTR tour USDOE Reactor America Sharing 1656 Mourich AVI Bio Pharma Avasive anitcancer vaccine Using a mouse model for AVI Bio Pharma mechanism of immuno-cancer. Tumor cells are protein irradiated and then coated with anitbodies produced by the vaccine. This complex is use to vaccinate mice to determine if subsequent anti-tumor specific immune responses are generated.

1657 Teaching and Tours Richland High Richland High School OSTR tour.

USDOE Reactor School Sharing 1658 Hensel Hemcon, Inc.

Sterilization of Bandages Sterilization of Army Hemcon Inc.

bandages used for hemorrhage control.

1660 Reese Oregon State Industrial Isotope Testing of containers and University Production Testing source material to produce various industrial

-radiography and tracer sources 1661 Wroblewski Vectron Gamma Irradiation of Parts Gamma irradiation of parts.

Vectron International International Norwalk Inc.

1662 Retallack University of Geochemistry of Soil from Determination of the trace USDOE Reactor Oregon Eugene Hills element chemistry of soils.

Sharing INAA = Instrumental Neutron Activation Analysis REE = Rare Earth Elements Work VI-29

Table VI.C.3 (continued)

Listing of Major Research and Service Projects Perforned or In Progress at the Radiation Center and their Funding Agencies Project Users Organization Name Project Title Description Funding 1664 Ciarella Providence Determination of Neutron Activation Analysis Providence Medical Center Gadolinium in Spinal Cord of spinal cord fluid and Medical Center Fluid Omniscan RX (gadodiamine) for gadolinium after radiochemical separation of sodium on HAP.

1665 LaFleur National Council Preparation of Hog Fuel The purpose of this project is National Council of Stream and Air Standard Reference to prepare a NAA standard for Air & Stream Improvement Material of composite wood waste Improvement material as a reference material for laboratory analyses.

1666 Teaching and Tours Douglas High Douglas High School AP OSTR tour and half-life USDOE Reactor School Physics Class experiment.

Sharing 1668 Meigs Oregon State Fission Track Dating Use of fission tracks from U-USDOE Reactor University 235 to determine the Sharing locationand concentration of U238 in apatite/zircon crystals for age dating 1669 Hamby Oregon State Activation of Black Beans Activation of black beans USDOE Reactor University used as a natural tracer in Sharing laboratory animal nutrition studies 1670 Teaching and Tours Toledo High Toledo High School OSTR tour and half-life USDOE Reactor School experiment.

Sharing 1671 Roden-Tice Plattsburgh State Fission Track Dating Use of fission tracks to USDOE Reactor University determine location of U-235 Sharing and Th232 in natural rocks and minerals 1672 Brix Ruhr-Universitat Fission track analysis of Fission track analysis of Ruhr-Universitat Bochum apatites and zircon.

apatites and zircon.

Bochum I

I

!i 1

i I

I I

I 1673 Teaching and Tours Heal College Heal College Physics Department OSTR tour.

USDOE Reactor Sharing I

INAA - Instrumental Neutron Activation Analysis REE - Rare Earth Elements I

Work VI-30 I

Table VI.C.4 Summary of the Types of Radiological Instrumentation Calibrated to Support the OSU TRIGA Reactor and the Radiation Center Type of Instrument Number of Calibrations Alpha Detectors 2

GM Detectors 28 Ion Chambers 12 Micro-R Meters 2

Personal Dosimeters 31 TOTAL 75 Work VI - 31

LL Table VI.C.5 Summary of Radiological Instnunentation Calibrated to Support Other OSU Departments and Other Agencies Department/Agency Number of Calibrations OSU Denartments Animal Science I

Biochemistry/Biophysics 9

Botanv and Plnt Pathology 7

Chemistry I

CiviL Constmction and Environmentl Engineering 1

Crop Science 3

E.M.T.

6 Fisheies and Wildlife 2

Forest Science 3

Horticulture 3

Linus Pauling Institute 4

Microbiology 8

Oceanic and Atmospheric Sciences 3

Pharmacy 5

Physics 5

Radiation Safety Office 15 Vetary Medicine 7

Zoology 3

OSU Departnents Total

[

86 Non-OSU Agencies ESCO Corporation Evanite Fiber Corp I

Federal Aviation Administration 5

Good Samaritan Hospital 7

Hot Cell Services 4

Kirner Consulting I

Oregon Office of Energy 35 Oregon Department of Transportation 4

Oregon Health Sciences University 23 Oregon Public Utilities Commission 5

Oregon State Health Division 39 USDA Agricultural Research Service 2

U.S. Environmentd Protection Agency 3

Valley Landfills, Inc.

2 Veterinary Diagnostic Imaging Cytopathology 3

Non-OSU Agencies Total 136 i

I i

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'I I

I I

I Work VI - 32 I

Table VI.F.1 Summary of Visitors to the Radiation Center Date 7/12/2002 7/15/2002 7/17/2002 7/17/2002 7/18/2002 7/25/2002 8/l/2002 8/1/2002 8/9/2002 8/26/2002 8/26/2002 8/27/2002 9/5/2002 9/9/2002 9/20/2002 9/27/2002 10/7/2002 10/7/2002 10/8/2002 10/9/2002 10/13/2002 10/26/2002 10/28/2002 No. of Visitors 10 8

3 10 8

I 4

3 6

20 19 19 3

2 3

10 2

3 15 20 4

81 2

Adventures in Learning START group Summer Experience in Science and Engineering for Youth Adventures in Learning WINS-Wondering Individual Networks Keith Kaufman-Morse Bros.

FBI tour FBI tour and Lt. Martz Francis Marshall OSU CH 123 OSU CH 123 OSU CH 123 Terry Brock, Paul Stansbury, Dan Stromm John and Miriam Rauch from Nu-Trek Mr. and Mrs. Bob Nelson, Art Johnson Graduate Orientation Barry Klein and Wade Richards XRI Testing: Kirk Tams, Glen McGillvery and Hank Rowe WNSA Advisory Coimmittee NE/RHP 114 ABET Dad's Weekend Odyssey Class Name of Group Work VI-33

-ft Table VI.F.1 (continued)

Summary of Visitors to the Radiation Center Date No. of Visitors Name of Group 10/29/2002 2

Alex Cheyne and Keith Kirk 10/31/2002 15 LBCC Science, Technology and Society 10/31/2002 15 LBCC Science, Technology and Society 11/5/2002 25 Engineering students from ENGR 111 11/5/2002 25 Engineering students from ENGR 111 11/5/2002 25 Engineering students from ENGR 111 11/5/2002 25 Engineering students from ENGR 111 11/6/2002 2

Gene Schrekece and Ward Wicker 11/7/2002 25 Engineering students from ENGR 11-1 11/7/2002 20 Odyssey Class 11/7/2002 25 Engineering students from ENGR 111 11/7/2002 25 Engineering students from ENGR 111 11/15/2002 15 LBCC Science, Technology and Society 12/5/2002 1

Seungjin Kim 12/9/2002 1

Brian Woods 12/9/2002 2

Jenepher Woods and Tracy Klein 12/16/2002 1

Francisco Moraga 12/26/2002 2

Jacob Litis - OSU student & Amanda Free - high school student 12/27/2002 12 Boy Scouts of America Troop 8 1/7/2003 2

Seminar Speakers 1/9/2003 7

OSU CH 462 1/10/2003 20 Madison High School Seniors Work VI-34

Table VI.F.1 (continued)

Summary of Visitors to the Radiation Center Date No. of Visitors Name of Group 1/13/2003 8

Nuclear Engineering and Radiation Health Physics 115 1/16/2003 7

OSU CH 462 1/17/2003 1

A.J. Hodson 1/21/2003 1

Phillip Williams 1/31/2003 1

Wesley Frey 2/4/2003 12 Good Samaratin Hospital Emergency Room Nursing Staff 2/4/2003 1

Alena Paulenova 2/10/2003 1

Doug Henderson 2/21/2003 4

Mr. and Mrs. Shuette & Melanie Marshall 2/25/2003 25 OSU CH 225H 2/25/2003 25 McKay HS 2/26/2003 25 LBCC General Science 154 2/27/2003 23 OSU CH 225H 2/28/2003 1

Prospective UG - Richard Wingfield 3/4/2003 25 OSU CH 205 3/4/2003 25 OSU CH 205 3/5/2003 25 OSU CH 205 3/5/2003 25 OSU CH 205 3/5/2003 25 Thurston High School Students 3/6/2003 25 OSU CH 205 3/6/2003 25 OSU CH 205 3/11/2003 25 OSU CH 205 3/11/2003 1

Eric Henry Work VI-35

-tt Table VI.F.1 (continued) 1 Summary of Visitors to the Radiation Center Date No. of Visitors Name of Group l~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~.

3/12/2003 25 OSU CH 205 3/13/2003 25 OSU CH 205 4/8/2003 20 SMILE students 4/22/2003 24 Physics Class 4/22/2003 1

John Henshaw 4/25/2003 20 LBCC 5/2/2003 15 OSU Mom's Club 5/3/2003 30 Mom's Weekend 5/7/2003 1

Robert A. Fjeld 5/8/2003 12 Science & Math Educators 5/8/2003 2

EPA guests 5/8/2003 1

Prospective Graduate Student - Joshua Axelrod 5/9/2003 1

Prospective Graduate Student - Alex Misner 5/12/2003 7

Douglas High School, Roseburg, OR 5/14/2003 15 Yarnhill Carlton High School 5/14/2003 14 Marist High School 5/14/2003 14 Marist High School 5/16/2003 10 Physics Class 5/16/2003 4

4 Mechanical Engr students 5/16/2003 15 Physics Class 5/17/2003 10 Physics Class 5/20/2003 35 Richland High School, Washington 5/21/2003 12 Physics Class i

LI I

.I LI I'

1 1I I

1I LI LI 1I 1I 1I lI Work VI-36

Table VI.F.1 (continued)

Summary of Visitors to the Radiation Center Date 5/23/2003 6/5/2003 6/5/2003 6/13/2003 6/24/2003 6/26/2003 6/26/2003 6/26/2003 No. of Visitors 37 2

20 2

4 20 2

3 Name of Group GS 152 Kay Altman Toledo High School - SMILE Progrm Perspective Students Mike Stringham's family High School Educators (Physics, Science)

Mr. & Mrs. John Hightower Corvallis Fire Department Total Tours: 99 Total Visitors: 1287 Work VI-37

Part VII Words

Part VII WORDS A.

Documents Published or Accepted

Aardk. Mededel. 2002. Thermal history of palaeozoic rocks in the Meuse Valley between Charleville-Mezieres and Namur (France, Belgium) assessed from zircon fission track data.

12:93-95

Ackert, R. B. Singer, H. Guillou, M. Kaplan, and M. Kurz. 2003. Long-term cosmogenic 3H production rates from 40Ar/ 9Ar and K-Ar dated patagonian lava flows at 47 S. Earth and Planetary Science Letters 210:114-136.

Armstrong, P.A., T.A. Ehlers, D.S. Chapman, KA. Farley, and P.J.J. Kamp. 2003.

Exhumation of the Central Wasatch Mountains, 1: Patterns and timing deduced from Low-temperature Thermochronometry data. Journal of Geophysical Research v. 108.

Balestrieri M.L., M. Bernet, M.T. Brandon, V. Picotti P. Reiners and M. Zattin. 2003.

Pliocene and Pleistocene exhumation and uplift of two key areas of the Northern Apennines.

Quaternary International 101-102C:67-73.

Brix, M.R., B. Stockhert. E. Seidel, T. Theye, S.N. Thomson and M. Kuster. 2002.

Thermobarometric data from a fossil partial annealing zone in high-pressure - low temperature rocks of eastern and central Crete, Greece. Tectonophysics 349:309-326.

Brihigel, A., I. Dunki W. Frisch, J. Kuhlemann and K. Balogh. In press. Geochemistry and geochronology of gneiss pebbles from foreland molasse conglomerates: geodynamic and paleogeographic implications for the Oligo-Miocene evolution of the Eastern Alps. Journal of Geology.

Clark, J.D., Y. Beyene, G. WoldeGabriel, W. Hart, P. Renne, H. Gilbert, A. Defleur, G. Suwa, K. Shigehiro, K. Ludwig, J.-R. Boisserie, B. Asfaw and T. White. 2003.

Stratigraphic, chronological and behavioural contexts of Pleistocene Homo sapiens from Middle Awash, Ethiopia. Nature 423:747-752.

Couliee, E., Quidelleur, X., Gillot, P.Y, Courtillot, V., Lefeevre, J.C. and S. Chiesa, 2003.

Combined 40Ar/39Ar and K-Ar dating of Ethiopian and Yemenite Traps volcanism. Earth Planet. Sci. Lett. 206:477-492.

Indicates OSTR use.

Words VII - 1

LL

Courtillot, V. and P. Renne. 2003. On the ages of flood basalt events (Sur Page des trapps basaltiques). Comptes Rendus Geoscience 335:113-140.

Davidson, C., K. Davis, G. Bailey, C. Tape, J. Singleton and B. Singer. 2003. Age, origin, I

and significance of brittle faulting and pseudotachylysle along the coast shear zone, Prince Rupert, British Columbia. Geology 31:43-46.

I

De Min, A., E.M. Piccirillo, A. Marzoli, G. Bellieni, P.R. Renne, M. Ernesto and L.S.

Marques. 2002. The Central Atlantic Magmatic Province in Brazil: Petrogenesis, 40Ar/39Ar I

Ages, Paleomagnetism and Geodynamic Implications, in The Central Atlantic Magmatic Province: Insights from Fragments of Pangea (W.E. Hames, G.M. McHone, P.R. Renne, and C. Ruppel, Eds.) Geophysical Monograph Series 136. American Geophysical Union,

10. 1029/136GM06.

Dunkl, I. and W. Frisch. 2002. Fission track and structural evidence on Late Cenozoic exhumation along the Alpine and West Carpathian margins of the Pannonian basin. In: S.A.P.

L Cloething, F. Horvaath, G. Bada and A.C. Lankreijer (eds.). Neotectonics and surface processes: the Pannonian Basin and Alpine/Carpathian System. EGU Stephan Mueller Special Publication Series 3:135-147.

1 Dunkl, I., W. Frisch and G. Grundmann. In press. Zircon fission track thermochronology of the southeastern part of the Tauern Window and the adjacent Austroalpine margin. Eclogae Geol. Helv.

Dusel-Bacon, C., M. Lanphere, W. Sharp, P. Layer and V. Hansen. 2002. Mesozoic I

thermal history and timing of structural events for the Yukon-Tanana Upland, east-central Alaska: 40Ar/39Ar data from metamorphic and plutonic rocks. Canadian Journal of Earth Sciences 39:1013-1051.

Fleischer, R.L. 2002. Serendipitous radiation monitors. American Scientist 90(4):324-331.

Gorring, M. B. Singer, J. Gowera, and S. Kay. 2003. Plio-pleistocene basalts from the Meseta del Laso, Buernois Aires, Argentina: evidence for asthemosphare-lithosphere 1

interactions during slab window magmatism. Chemical Geology 193:215-235.

Grasemann, B. and I. Dunkl. In press. Modeling of the thermal structure during footwall uplift:

constraints on the geometry of normal faulting (Rechnitz metamorphic core complex, Eastern Alps). Mitteilungen der Geologischen Gesellschaft in O6sterreich.

Hackley, P.C., and R.P. Tollo. Geologic map of basement rocks in a portion of the Old Rag Mountain 7.5-minute Quadrangle, Virginia: Virginia Division of Mineral Resources; scale 1:24,000. Accepted for publication as a digital map.

Indicates OSTR use.

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Kizmbr, M., I. Dunkl, W. Frisch, J. Kuhlemann. and P. OzsvArt. 2003. The Palaeogene forearc basin of the Eastern Alps and the Western Carpathians: subduction erosion and basin evolution. Journal of GeoL Soc. 160:413-428.

Knight, K., P. Renne, A. Halkett.and N. White. 2003. 4OAr/39Ar dating of the Rajahmundry Traps, Eastern India and their relationship to the Deccan Traps. Earth and Planet Science Letters. 208:85-99.

Kuhlemann, J., W. Frisch, B. Sz6kely, I. Dunkl and M. Kizm6r. 2002. Post-collisional sediment budget history of the Alps: tectonic versus climatic control. Int. J. Earth Sciences 91:

818-837.

Leisy D.J., T.D. Lewis, J.A. Leong and G.F. Rohrmann. 2003. Transduction of cultured fish cells with recombinant baculoviruses. Journal of Gen Virol. 84:1173-8

Marra, F., C. Freda, P. Scarlato, J. Taddeucci D.B. Karner, P.R. Renne, M. Gaeta, D.M.

Palladino, R. Trigila, G. Cavarretta. 2003. 40Ar/39Ar Geochronology and Compositional Features of Young Volcanic Rocks from the Alban Hills Volcanic District (Rome, Italy):

Evidence of Rejuvenation Volcanism. Bulletin of Volcanology 65:227-247.

MacDonald, J., R.L. Fleischer, S. Fujita and M. Hoshi. 2003. Hiroshima neutron fluence:

Use of glazes on porcelain from near ground zero. Health Physics 84(4): 1-5

Medaris, L.G., B.S. Singer, R.H. Bott, A. Naymark, G.M. Johnson and R.C. Schott. 2003.

Late paleoproterozoic climate, tectonics, and metamorphism in the Southern Lake Superior Regin and Proto-North America: Evidence from Baraboo Interval Quartzites. Journal of Geology v.111.

Min, K., K Farley, P. Renne and K. Marti 2003. Single grain (U-Th)/He ages from phosphates in Acapulco meteorite and implications for thermal history. Earth and Planet Science Letters 209:323-336.

Nomade, S., Y. Chen, A. Pouclet, G. FRraud, H. Theveniaut, B. Daouda, M. Vidal. and C. Rigolet. 2003. The Guiana and the West African Shield Palaeoproterozoic grouping: new palaeomagnetic data for French Guiana and the Ivory Coast. Geophysical Journal International 154:1-18.

Nomade, S., G. F6raud, Y. Chen and A. Pouclet. 2002. Thermal and tectonic evolution of the paleoproterozoic Transamazonian orogen as deduced from 4OAr/39Ar and AMS along the Oyapok river (French Guyana). Precambrian Research 114:35-53.

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Nomade, S., A. Pouclet and Y. Chen. 2002. The French Guyana doleritic dykes:

geochemical evidence of three populations and new data for the Jurassic Central Atlantic Magmatic Province. Journal of Geodynamics 34:595-614.

Pederson, J., KI Karlstrom, W. Sharp and W. McIntosh. 2002. Differential incision of the Grand Canyon related to Quaternary faulting - constraints from U-series and Ar/Ar dating.

I Geological Society of America 30(8):739-742.

Pinti, D.L., X. Quidelleur, P. Lahitte, C. Aznar, S. Chiesa, P.Y. Gillot. 2003. The Piaa nico I

tephra: an early-Middle Pleistocene record of intraplate volcanism in the Mediterranean. Terra Nova 15:176-186.

Quidelleur, X., J. Carlut, V. Soler, J.-P. Valet and P.-Y. Gillot. 2003. The age and duration of the Matuyama-Brunhes transition from new K-Ar data from La Palma (Canary Islands) and revisited 40Ar/39Ar ages. Earth Planet. Science Letters 208:149-163.

Quidelleur X., J. Carlut, P.-Y. Gillot and V. Soler. 2002. Evolution of the geomagnetic field prior to the Matuyama-Brunhes transition: Identification of a 820 ka old excursion at La Palma.

Geophys. J. Int., 151, F6-F10.

Ravenhurst, C.E., M.K. Roden-Tice and D.S. Miller. In Press. Thermal annealing of fission tracks in fluorapatite, chlorapatite, manganoanapatite and Durango apatite: Experimental results. Accepted for Canadian Journal of Earth Sciences.

Rauch J. and M. Rauch. 2003. Ga/As and higher Z PCDs for flash x-ray diagnostics. Final Report, March 22, 2003, Contract DTRAOI0-02-P-0239, NU-TREK, Inc., Poway, CA.

Prepared for Defense Threat Reduction Agency, Fort Belvoir, VA.

Renne, P. 2002. Flood Basalts - Bigger and Badder. Science 296:1812-1813.

Ring, U., S.N. Thomson and M. Brocker. 2003. Fast extension but little exhumation: The Vari detachment in the Cyclades, Greece. Geological Magazine 140:245-252.

Roden-Tice, M.K 2002. 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, p. A2-1 - A2-13.

Singer, B.S. and L.L. Brown. 2002. The Santa Ross Event: 4Ar/39Ar and paleomagnetic results from the Valley Rhyolite near Jarniillo Creek, Jemez Mountains, New Mexico. Earth and Planetary Science Letters 97:51-65.

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Singer, B.S., H.R. Relie, K.A. Hoffinan, A. Bittle, H. Guillou, L. Lau, and J.C. Carracedo.

2002. Ar/Ar ages of transitionally magnetized lavas on LaPalma, Canary Islands, and the geomagnetic instability timescale. Journal of Geophysical Research, v. 107.

Sz6kely, B., J. Reinecker, I. Dunkl, W. Frisch and J. Kuhlemann. 2002. Neotectonic movements and their geomorphic response as reflected in surface parameters and stress patterns in the Eastern Alps. In: S.A.P.L. Cloething, F. Horviath, G. Bada and A.C.

Lankreijer (eds.): Neotectonics and surface processes: the Pannonian Basin and Alpine/Carpathian System. EGU Stephan Mueller Special Publication Series 3:149-166.

Teixeira, W., J. Pinese, M. lacumin, V. Girardi E. Piccirillo, H. Echeveste, A. Ribot, R. Fernandez, P. Renne and L. Heaman. 2002. Caic-alkaline and tholejitic dyke swarms of Tandilia, Rio De La Plata Craton, Argentina: U-Pb, Sm-Nd, and Rb-Sr 4OAr/39Ar data provide new clues for intraplate rifting shortly after the Trans-Amazonian orogeny.

Precambrian Research 119:329-353.

Tesfaye, K., V. Courtillot, I. Manighetti L. Audin, P. Lahitte, X. Quidelleur, P.-Y. Gillot, Y. Gallet, J. Carlut and T. Haile. 2003. New paleomagnetic and geochronological results from Ethiopian Afar: Block rotations linked to overlap and propagation, and determination of a 2 Ma reference pole for stable Africa. Journal of Geophys. Res. 108:2102.

Thomson, S.N. 2002. Late Cenozoic geomorphic and tectonic evolution of the Patagonian Andes between latitudes 42S and 46S: an appraisal based on fission-track results from the transpressional intra-arc Liquifie-Ofqui fault zone. Geological Society of America, Bulletin.

114:1159-1173.

Thomson, S.N. and F. Herve. 2002. New time constraints for metamorphism at the ancestral Pacific Gondwana margin of southern Chile (42S-525S). Revista Geol6gica de Chile.

29:255-271.

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. Accepted at Precambrian Research.

Tollo, R.P., E.A. Borduas and P.C. Hackley. Geology of basement rocks in the Thornton Gap, Old Rag Mountain and Fletcher quadrangles, Virginia: Virginia Division of Mineral Resources Report. Accepted for publication as a Geologic Report.

Tollo, R.P., E.A. Borduas, A.A. Antignano, IV and C.C. Claflin. Geologic map of basement rocks in a portion of the Fletcher 7.5 -minute Quadrangle, Virginia: Virginia Division of Mineral Resources; scale 1:24,000. Accepted for publication as a digital map.

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Toilo, R.P., E. Pogue, S.E. Nyman, and P.C. Hackley. Geologic map of basement rocks in a portion of the Thornton Gap 7.5-minute Quadrangle, Virginia: Virginia Division of Mineral Resources; scale 1:24,000. Accepted for publication as a digital map.

Trauth, M.H., A. Deino, A. Bergner and M.R. Strecker. 2003. East African climate change and orbital forcing during the last 175 kyr BP. Earth and Planet Science Letters 206:297-313.

Weinstein, J.S.,, R.V. Fodor and G.R. Bauer. In press. Koolan shield basalt as xenoliths entrained during rejuvenated-stage eruptions: perspectives on magma mixing. Bulletin of Volcanology.

West, D. P., Jr. and M.K Roden-Tice. 2003. Late Cretaceous reactivation of the Norumbega fault zone, Maine: Evidence from apatite fission track ages. Geology 31:649-652.

Zattin M. 2003. Apatite fission-track analysis and thermochronology of sedimentary successions. Atti Ticinensi di Scienze della Terra 9:33-42.

Zattin M., V. Picotti and G.G. Zuffa. 2002. Fission-track reconstruction of the front of the northern Apennine thrust wedge and overlying Ligurian unit. American Journal of Sciences 302:346-379.

Zattin M., C. Stefani and S. Martin. In press. Detrital fission-track analysis and petrography as keys of alpine exhumation: the example of the Veneto foreland (Southern Alps, Italy).

Journal of Sedimentary Research.

Zattin, M. and G.G. Zuffa. In press. Unravelling source rocks of orogenic wedge and foredeep Late Eocene-Miocene arenites of northern Apennines and southern Alps. Bollettino Societa Geologica Italiana.

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B.

Documents Submitted for Pubhcation

Audin L., X. Quidelleur, E. Coulie6, V. Courtillot, S. Gilder, I. Manighetti P.-Y. Gillot, P. Tapponnier, and K. Tesfaye. 2003. Paleomagnetic constraints and timing of deformation associated with the onland propagation of the Aden ridge into Southeastern Afar during the last 8 Myr. Submitted to Geophys. J. Int..

Balogh, K. and I. Dunkl. Submitted. Chronology of Alpine metamorphism and exhumation of the Austroalpine basement in the Sopron Mts. (Eastern Alps, Hungary) - Thermochronology or mineral growth? Mineralogy and Petrology.

Bernet M., M.T. Brandon, J.I. Garver, M.I. Balestrieri, B. Ventura and M. Submitted.

Exhuming the Alps through time: clues from detrital zorcon fission-track ages. Geological Society of America Bulletin, accettato per la pubblicazione.

Brown, L.L., B.S. Singer and M. Gorring. 2003. Paleosecular variation in the southern hemisphere: Paleomagnatic and geochronologic results from Mesta del Lago Buenos Aires, Patagonia, Argentina. G-cubed.

Coe, R.S., B.S. Singer, M.S. Pringle and X. Zhao. 2003. Matuyama-Brynhes reversal and kamileatsum event on Maui: Paleomagnetic directions and 40Ar/39Ar ages. Earth and Planetary Science Letters (Submitted)

Dunkl, I., R.K. Beck, J. Kuhlemann, W. Frisch and K.-H. Pfeffer. Submitted. Persistence of Aggtelek karst plateau through the Tertiary - zircon fission track age-provenance of doline-filling red clay (NE Hungary). Terra Nova.

Elmaleh, A., J.-P Valet, X. Quidelleur, H. Bouquerel, T. Tesson, E. Mulyadi and A.D. Wirakusumah. 2003. Paleosecular variation in Java and Bawean Islands (Indonesia) during the Brunhes chron. Submitted to Earth Planetary Science Letters.

Hoffman, K.A. and B.S. Singer. 2003. A record of the Big Lost geomagnetic event in Tahitian lavas: evidence for recurring transitional field configurations of the last 3 Ma. Nature

Jicha, B.R., B. Singer, J.G. Brophy, J.H. Fournella, G.M. Johnson, B.L. Beurd, T.J. Lapen, and N.J. Mahlan. 2003. Variable impact of the subducted slab on Aleutian Island arc magma sources: evidence from Sr, Nd, Pb, and Hf isotopes and trace element abundances. Journal of Petrology.

Rauch, J.E., M. Gersten-Rauch and A. Burger. 2003. Parallel biased GaAs photoconductivedetector. Proceedings of SPIE, 3-8 August 2003, San Diego, CA, Conference on Hard X-Ray and Gamma-Ray Detector Physics V. (Submitted and approved.)

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Thiede, R.C., B. Bookhagen, J.R. Arrowsmith, E.R., Sobel, and M.R. Strecker. In review.

Climate and erosion control areas of rapid exhumation along the Southern Himalayan front.

Earth and Planetary Science Letters.

Tolio, 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 Geologic Society of America Memoir entitled "Proterozoic Tectonic Evolution of the Grenville Orogen in North America edited by R. Tollo, L. Corriveau, J. McLelland and M. Bartholomew; publication expected by June 2004.

Willner, A.P., F. HervM, S.N. Thomson and H.-J. Massonne. 2003. Juxtaposition of different HP/LT metamorphic units during subduction erosion in a Mesozoic accretionary complex (Diego de Alnagro Island / Southern Chile; 51301S). Journal of Metamorphic Petrology, submitted.

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C.

Documents in Preparation

Brown, L.L., J.R. Pickens, B.S. Singer and B.R. Jicha. In prep. Paleomagnetic and geochronolosic record of the Matuyama Brunhes geomagnetic reversal at Tstara San Pedro, Volcano, Chile.

Fafndez, V., M.R. Brix, F. Herv6, S.N. Thomson, B. Stockhert and W. Loske. In prep.

Fission track thermochronology of the western Antarctic Peninsula and the South Shetland Islands: a progress report on new zircon data; Fellin, M.G., V. Picotti and M. Zattin. In prep. Neogene to Quaternary thermo-tectonic evolution of North-Eastern Corsica (France).

Krane, K.S. and C.J. Stapels. In prep. Neutron capture by l66mHo and the decay of' 67Ho.

McCarter, R.L., R.V. Fodor, and F. Trusdell. In prep. Perspectivesss on basaltic magma eryslelletic and differentiation: lava lake samples from Mannaloa volcano summit, Hawaii.

Bulletin of Volcanology.

Singer, B.S., R.S. Coe, KA. Hoffman, L.L. Brown, B.R. Jicha, M.S. Pringle, and A.

Chauvin. In prep. Duration and structure of Matuyama-Brunhes geomagnetic polarity reversal from 40Ar/39Ar dated lava flows.

Taylor, A. and P.A. Armstrong. In prep. Evaluation of the long-term segmentation of the Wasatch Fault footwall using (U-Th)fHe Thermochronometry, to be submitted to Geology in August, 2003.

Thomson, S.N. and U. Ring. 2003. Applying low temperature thermochronology to investigate the postulated Simav detachment at the northern boundary of the Menderes Massif, western Turkey.

D.

Thesis and Student Project Reports

Ascrizz4 A. 2003. Petrology and tectonic significance of mesoproterozoic biotite granitic gneiss, Madison Area, Blue Ridge Province, Virginia. B.S. George Washington College, Washington, DC.

Duncan, C. 2003. Measurement of neutron activation in palladium isotop 102. Oregon State University, Department of Physics, Corvallis, Oregon.

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Faundez, V.

2003. Fission track thermochronology of the western Antarctic Peninsula and the South Shetland Islands, Universidad de Chile.

Fellin M.G. 2003. Neogene to Quaternary thermo-tectonic evolution of North-Eastern L

Corsica (France). University of Bologna, Department of Earth Sciences, Bologna, Italy.

Freitag, R. 2002. Structure and Geodynamics of Eastern Central Kamchatka (DFG).

GFZ/Uni Potsdam, Germany.

Jicha, B. 2002. Variable impact of the subducted slab on Aleutian Island arc magma sources:

evidence from Sr, Nd, Pb, and Hf isotopes. University of Wisconsin-Madison, Department of Geology and Geophysics, Madison, Wisconsin.

MacDonald, J. 2002. Fission and alpha track techniques for measuring uranium and thorium concentrations in core samples from Ballston and Queechy Lake to derive sedimentation rates based on near surface decay of radon daughters. Union College, Department of Geology, Schenecktady, NY.

I Most, T. 2003. Geodynamic evolution of the Eastern Pelagonian Zone in northwestern Greece and the Republic of Macedonia.Implications from U/Pb, Rb/Sr, K/Ar, 4OAr/39Ar geochronology and fission track thermochronology. Uni. Ttiibingen, Aachen, Germany.

Most, P. 2003. Geodynamic evolution of the Eastern Pelagonian Zone in northwestern Greece and the Republic of Macedonia.Implications from U/Pb, Rb/Sr, K/Ar, 40Ar/39Ar geochronology and fission track thermochronology. Uni. Tufibingen, Aachen, Germany.

Warkus, F. 2002. Investigation of the relation between forland basin development and unroofing history of the Patagonien Andes (SFB267, subproject D4B). Uni Potsdam, 1

Germany.

E.

Presentations Aldega L., G. Cello, S. Corrado, J. Cuadros, P. Di Leo, C. Giampaolo, C. Invernizzi, C. Martino, S. Mazzol, M. Schiattarella, M. Zattin, and G.G. Zuffa. 2003. Tectono-sedimentary evolution of the Southern Apennines (Italy): thermal constraints and modeling.

Workshop on The record of thermal history in sedimentary succession, Pavia, 5-6 June 2003, Atti Ticinensi di Scienze della Terra 9:135-140.

Aldega L., S. Corrado, J. Cuadros, P. Di Leo, C. Giampaolo, C. Invernizzi, S. Lo Mastro, L. Mattioni, S. Mazzoli, M. Schiattarella, M. Zattin and G.G. Zuffa. 2002. Thermal constraints

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Words VII-IO

to the reconstruction of the Neogene-Quaternary evolution of the Lucanian sector of the Southern Apennines fold-and-thrust belt. 81 0 Riunione estiva delta Societi Geologica Italiana, Torino, 10-12 September 2002, 9-10.

Bistacchi M., M. Massironi and M. Zattin. 2002. Cooling rate approach to the study of exhumation processes. 81° Riunione estiva della SocietA Geologica Italiana, Torino, 10-12 September 2002, 48-49.

DiGiulio, A., R. Fantoni and M. Zattin. 2003. Thermal history of sedimentary successions:

how they can be studied and why? Workshop on The record of thermal history in sedimentary succession: Pavia, 4-5 June 2003. Atti Ticinensi di Scienze delta Terra 9:3-6

Ege, H., E. Sobel, E. Scheuber, P. Silva and V. Jacobshagen. 2002. Exhumation history of the Central Andean fold-thrust belt (S. Bolivia) by apatite fission track dating. International workshop on fission track analisis: Theory and Applications, Cidiz, Spain, Geotemas 4:65-68.

Fellin M.G., V. Picotti M. Zattin and G.G. Zuffa. 2002. Brittle structures in north-eastern Corsica: evidence for compressional and extensional deformations during Neogene.

81 Riunione estiva delia Societi Geologica Italiana, Torino, 10-12 September 2002, 152-153.

Fellin G., M. Zattin and V. Picotti. 2003. Tectono-thermal evolution of Miocene basin in North-Eastern Corsica (France). Workshop on The record of thermal history in sedimentary succession, Pavia, 5-6 June 2003, Atti Ticinensi di Scienze della Terra 9:105-108.

Fodor, R.V., J.S. Weinstein, and G.R. Bauer. Koolan shield basalt as xenoliths entrained during rejuvenated-stage eruptions: perspectives on magma mixing. Presented at Cordilleran Section Meeting of Geological Society of America, April 1-3, 2003, Puerto Vallarta, Mexico.

Giulio A., R. Fantoni, and M. Zattin. 2003. Thermal history of sedimentary successions: how can be studied and why? Workshop on The record of thermal history in sedimentary succession", Pavia, 5-6 June 2003, Atti Ticinensi di Scienze delta Terra 9:3-6.

Roden-Tice, M. K., D.P. West, Jr., S.T. Tice and P.W. Reiners. 2002. Cretaceous thermochronologic discontinuities along the Vermont-New Hampshire border, Norumbega Fault system, ME and in the Adirondack Mountains, NY: Evidence for Late Mesozoic faulting and differential erosion. Geological Society of America Abstracts with Programs, v. 34, p. 42.

Presented at the National meeting of the Geological Society of America in Denver, CO on October 27-30, 2002.

Roden-Tice, M.K. and S.J. Tice. 2003. Thermochronologic evidence for Early-Late Cretaceous exhumation of the Adirondack Mountains, New York and western New England.

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The Vermont Geological Society, Winter Meeting, February 8, 2003, Norwich University.

Published in The Green Mountain Geologist 30: 10.

Senglaub, Y., R. Littke and M.R. Brix. 2003. Thermal evolution of the southwestern Lower l

Saxony Basin, 1V round table of the special research program SPP 1135 of the German Science Foundation "Dynamics of sedimentary systems under varying stress conditions by example of the Central European Basin System", Schloss Eringerfeld, Germany, November 28-29, 2003 1

Sobel, E. R., and M.R. Strecker. 2002. Contrasting exhumation histories from vertical profiles in the Calchaquies and Aconquija ranges, northwest Argentina. International workshop on fission track anAlisis: Theory and Applications, Cadiz, Spain, Geotemas 4:139-142.

Sobel, E. R., and M.R. Strecker. 2003. Uplift, exhumation, and precipitation: Tectonic and climatic control of Late Cenozoic landscape evolution in the northern Sierras Pampeanas, Argentina. Penrose workshop on Tectonics, Climate and Landscape Evolution, Taiwan.

Thiede, R.C., B. Bookhagen, E. SobeL, M.R Strecker, B. Grasemann and C. Janda. 2002.

Plio-Pleistocene exhumation of the Main Central Trust footwall based on new apatite fission track in AGU Fall meeting, San Francisco, p. F1303.

Thomson, S.N. 2003. Does glaciation act to limit the topography of active mountain belts?

Evidence from the Patagonian Andes. EGS-AGU-EUG Joint Assembly, Nice, France.

Thomson, S.N. 2003. Late Cenozoic development of the Patagonian Andes: a reappraisal.

l 18 Geowissenschaftliches Lateinamerika-Kolloquium, Freiberg, Germany.

Thomson, S.N. and F. Herv6. 2002. An extensive new fission-track thermochronological database from the coastal Patagonian Andes (47S To 53S): a record of Cenozoic denudation and magmatism. 5th International Symposium on Andean Geodynamics, Toulouse, France, Extended Abstracts, p. 637-640.

Thomson, S.N., M.T. Brandon and P. W. Reiners. 2003. Topographic development and syn-i convergent extension of the northern Apennine (Italy) orogenic wedge assessed using low-temperature thermochronology. Earth Science into the 3. Millennium: Methods, Materials, Mechanisms, Bochum, Germany.

Thomson, S.N., M. Zattin, P.W. Reiners and M.T. Brandon. 2003. Cross-comparison of the apatite fission-track and (U-Th)/He thermochronologic systems in post-depositionally reheated sedimentary rocks. 2003 GSA Annual Meeting, Seattle, USA.

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Willner, A.P., F. Herv6, S.N. Thomson and H.-J. Massonne. 2003. Juxtaposition of different HP/LT metamorphic units during subduction erosion in a Mesozoic accretionary complex (Diego de Almagro Island / Southern Chile; 51'301S). 18 Geowissenschaftliches Lateinamerika-Kolloquium, Freiberg, Germany.

Witlner, A.P., S.N. Thomson, J.A. Wartho, J. Wijbrans and F. Herv6. 2003. History of convective mass flow and exhumation of an Upper Paleozoic paired metamorphic belt in Central Chile (34 -365S). Earth Science into the 3. Millennium: Methods, Materials, Mechanisms, Bochum, Germany.

Zattin, M., S.N. Thomson, P.W. Reiners, M.L. Balestrieri and M.T. Brandon. 2003.

Investigating Neogene exhumation of the northern Apennines by combining fission-track and (U-Th)/He dating in areas of high relief. 2003 GSA Annual Meeting, Seattle, USA.

Zattin, M., C. Stefani and S. Martin. 2002. Detrital fission-track analysis and petrography as keys of alpine exhumation: the example of the Veneto Foreland. 81 Riunione estiva delta Societa Geologica Italiana, Torino, 10-12 September 2002, 336-337.

Zattin M., A. Cuman, R. Fantoni, S. Martin, P. Scotti and C. Stefani. 2002.

Thermochronological evolution of the Southern Alps along the TRANSALP profile. Transalp Conference, Trieste, 10-12 February 2003, Memorie di Scienze Geologiche 54:127-130 Zattin M., A. Cuman, R. Fantoni, S. Martin, P. Scotti and C. Stefani. 2003.

Thermochronological evolution of the Eastern Southern Alps from vitrinite reflectance and fission-track data. Workshop on The record of thermal history in sedimentary succession, Pavia, 5-6 June 2003, Atti Ticinensi di Scienze delta Terra 9:92-95.

Zattin, M., A. De Poli, R. Fantoni, V. Picotti S. Rogledi and P. Scotti. 2003.

Thermochronology of the Marnoso-arenacea Fm (Northern Apennines). Workshop on The record of thermal history in sedimentary succession, Pavia, 5-6 June 2003, Atti Ticinensi di Scienze della Terra 9:112-115.

Zeh, A., S.N. Thomson and H. Bratz. 2002. Upper Carboniferous/Permian and late Cretaceous structural-thermal evolution in the NW Thuringian Forest, Germany field observations and geochronology. 9th TSK, Erlangen, Germany, p. 90-91.

Zuffa, G.G. and M. Zattin. 2002. Arenite composition and low-temperature geochronometers in paleogeographic reconstructions of orogenic belts. 81' Riunione estiva delta Societa Geologica Italiana, Torino, 10-12 September 2002, 338-339

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