ML25280A138
| ML25280A138 | |
| Person / Time | |
|---|---|
| Site: | Oregon State University (R-106) |
| Issue date: | 10/01/2025 |
| From: | Reese S Oregon State University |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| Download: ML25280A138 (1) | |
Text
a Oregon State V University U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Radiation Center Oregon State University 100 Radiation Center Corvallis, Oregon 97331 P 541-737-2341 F 541-737-0480 radiationcenter.oregonstate.edu October 1, 2025
Reference:
Oregon State University TRIGA Reactor (OSTR)
Docket No. 50-243, license No. R-106 In accordance with section 6.7.1 of the OSTR Technical Specifications, we are hereby submitting the attached Oregon State University Radiation Center and OSTR Annual Report for the period July 1, 2024, through June 30, 2025.
The Annual Report continues the pattern established over many years by including information about the entire Radiation Center rather than concentrating primarily on the reactor. Because this report addresses a number of different interests, it is rather lengthy, but we have incorporated a short executive summary which highlights the Center's activities and accomplishments over the past year.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on:,o/, /z.ozr Sincerely,
~
Steven R. Reese Director Attachment CC:
Dr. I rem Turner, OSU Dr. Trevor Howard, OSU w/o attachment Maxwell Woods, ODOE w/o attachment
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- RADIATION CENTER anaTRIGA REACTOR ANNUAL REPORT JULY 1, 2024 - JUNE 30, 2025 a Or~gon_State
'V' Uruvers1ty
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- Submitted by:
Steve R. Reese, Director Radiation Center Oregon State University Corvallis, Oregon 97331-5903 Telephone: (541) 737-2341 Fax: (541) 737-0480 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. Battelle Energy Alliance, LLC; Subcontract Award No. 00074510.
C. Oregon Department of Energy, OOE Rule No. 345-030-010.
CONTENTS Part I-Overview Executive Summary..................................................................................................................................... 4 lntroduction.................................................................................................................................................... 4 Overview of the Radiation Center.......................................................................................................... 5 Part II-People Radiation Center Staff................................................................................................................................. 6 Reactor Operations Committee.............................................................................................................. 6 Faculty............................................................................................................................................................... 7 Part Ill-Facilities Research Reactor.......................................................................................................................................... 8 Analytical Equipment.................................................................................................................................. 9 Radioisotope Irradiation Sources............................................................................................................ 9 Laboratories and Classrooms................................................................................................................. 10 Instrument Repair and Calibration Facility........................................................................................ l O Part IV-Reactor Operating Statistics.................................................................................................................................... 14 Experiments Performed........................................................................................................................... 14 Unplanned Shutdowns............................................................................................................................. 15 Activities Pursuant to 10 CFR 50.59...................................................................................................... 15 Surveillance and Maintenance.............................................................................................................. 15 Part V-Radiation Protection lntroduction.................................................................................................................................................. 26 Environmental Releases........................................................................................................................... 26 Personnel Doses.......................................................................................................................................... 27 Facility Survey Data.................................................................................................................................... 28 Environmental Survey Data.................................................................................................................... 28 Radioactive Material Shipments........................................................................................................... 29 References..................................................................................................................................................... 29 Part VI-Work Summary....................................................................................................................................................... 46 Teaching......................................................................................................................................................... 46 Research and Service................................................................................................................................ 46 Part VII-Words Documents Published or Accepted..................................................................................................... 76 Presentations................................................................................................................................................ 84 Students......................................................................................................................................................... 86
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- TABLES Table Title Page 111.1 Gammacell 220 60Co lrradiator Use....................................................................................................... 11 111.2 Student Enrollment in Courses Taught or Partially Taught at the Radiation Center................................. 12 IV.1 Present OSTR Operating Statistics......................................................................................................... 17 IV.2 OSTR Use Time in Terms of Specific Use Categories............................................................................... 18 IV.3 OSTR Multiple Use Time....................................................................................................................... 18 IV.4 Use of OSTR Reactor Experiments......................................................................................................... 19 IV.S Unplanned Reactor Shutdowns and SCRAMS....................................................................................... 19 V.1 Radiation Protection Program Requirements and Frequencies.............................................................. 30 V.2 Monthly Summary of Liquid Effluent Released to the Sanitary Sewer.................................................... 31 V.3 Annual Summary of Liquid Waste Generated and Transferred............................................................... 32 V.4 Monthly TRIGA Reactor Gaseous Waste Discharges and Analysis........................................................... 32 V.5 Annual Summary of Solid Waste Generated and Transferred................................................................. 33 V.6 Annual Summary of Personnel Radiation Doses Received..................................................................... 34 V.7 Total Dose Equivalent Recorded on Area Dosimeters Located within the TRIGA Reactor Facility............. 35 V.8 Total Dose Equivalent Recorded on Area Dosimeters Located within the Radiation Center.................... 36 V.9 Annual Summary of Radiation and Contamination Levels Observed within the Reactor Facility and Radiation Center during Routine Radiation Surveys............................................................................ 38 V. lo Total Dose Equivalent at the TRIGA Reactor Facility Fence..................................................................... 39 V.1 1 Total Dose Equivalent at the Off-Site Gamma Radiation Monitoring Stations........................................40 V.12 Annual Average Concentration of the Total Net Beta Radioactivity (minus 3H) for Environmental Soil, Water, and Vegetation Samples.................................................................................................... 41 V.13 Annual Summary of Radioactive Material Shipments Originating from the TRIGA Reactor Facility's NRC License R-106...................................................................................................................................... 42 V.14 Annual Summary of Radioactive Material Shipments Originating from the Radiation Center's State of Oregon License ORE 90005.................................................................................................................. 43 V.15 Annual Summary of Radioactive Material Shipments Exported under NRC General License 10 CFR 110.23..................................................................................................................................... 43 Vl.1 Institutions, Agencies, and Groups which Utilized the Radiation Center................................................ 48 Vl.2 Listing of Major Research and Service Projects Performed or in Progress at the Radiation Center and their Funding Agencies....................................................................................................................... 53 Vl.3 Summary ofRadiological Instrumentation Calibrated to Support OSU Departments............................. 75 Vl.4 Summary of Radiological Instrumentation Calibrated to Support Other Agencies................................. 75 FIGURES Table Title Page IV.l Monthly Surveillance and Maintenance (Sample Form)....................................................................... 20 IV.2 Quarterly Surveillance and Maintenance (Sample Form)..................................................................... 21 IV.3 Semi-Annual Surveillance and Maintenance (Sample Form)................................................................ 22 IV.4 Annual Surveillance and Maintenance (Sample Form)......................................................................... 23 V.1 Monitoring Stations for the OSU TRIGA Reactor...................................................................................45 Vl.1 Summary of the Types of Radiological Instrumentation Calibrated to Support the OSU TRIGA Reactor and Radiation Center....................................................................................................................... 75
OVERVIEW'"
Executive Summary The data from this reporting year shows that the use of the Radiation Center and the Oregon State TRIGA ~ reactor (OSTR) has returned to pre-CO YID levels across nearly eve,y metric.
Of the work pe,fonned, seventy-four percent (78%) of the OSTR research hours were in support of off-campus research projects reflecting the use of the OSTR nationally and internationally. Radiation Center users published or submitted 120 articles this year and made 45 presentations on work that involved the OSTR or Radiation Center. The number of samples irradiated in the reactor during this reporting period was 2,152. Funded OSTR use hours comprised 83% of the research use. The Radiation Center supported 34 different courses during the academic year, with the OSTR being uti I ized in 11 of those courses.
Personnel at the Radiation Center conducted I 03 tours of the facility, accommodating 839 visitors. The visitors included elementary, middle school, high school, and college students; relatives and friends; faculty; current and prospective clients; national laboratory and industrial scientists and engineers; and state, federal, and international officials. The Radiation Center is a significant positive anraction on campus because visitors leave with a good impression of the facility and of Oregon State University.
The Radiation Center's projects database continues to provide a useful way of tracking the many different aspects of work at the facility. The number of projects supported this year was 197. Reactor related projects comprised 72% of all projects. The total research dollars in some way supported by the Radiation Center, as reported by our researchers, was $12.5 million. The actual total is likely higher. This year, the Radiation Center provided service to 78 different organizations/institutions of which 46% were from other states and 32% of which were from outside the U.S. and Canada. So,~
while the Center's primary mission is local, it is also a facility with a national and international clientele.
The Radiation Center's website provides an easy way for potential users to evaluate the Center's facilities and capabilities as well as to apply for a project and check use charges. The address is http://radiationcenter.oregonstate.edu.
Introduction The current annual report of the Oregon State University Radiation Center and TRJGA
- Reactor follows the usual fom1at by including information relating to the entire Radiation Center rather than just the reactor. However, the infom1ation is still presented in such a manner that data on the reactor may be examined separately, if desired. It should be noted that all annual data given in this report covers the period from July I, 2024 through June 30, 2025. Cumulative reactor operating data in this report relates only to the LEU fueled core. This covers the period beginning July 1, 2008 to the present date. For a summary of data on the reactor's two other cores, the reader is referred to previous annual reports.
In addition to providing general infonnation about the activities of the Radiation Center, this report is designed to meet the reporting requirements of the U.S. Nuclear Regulatory Commission and the Oregon Department of Energy. Because of this, the report is divided into several distinct parts so that the reader may easily find the sections of interest.
=- OVERVIEW I.
- Overview of the Radiation Center The Radiation Center is a unique facility which serves the entire OSU campus, all other institutions within the Oregon University System, and many other universities and organizations throughout the nation and the world. The Center also regularly provides special services to state and federal agencies, particularly agencies dealing with law enforcement, energy, health, and environmental quality, and renders assistance to Oregon industry. In addition, the Radiation Center provides permanent office and laboratory space for the OSU School of Nuclear Science and Engineering, the OSU lnstitute of Nuclear Science and Engineering, and for the OSU nuclear chemistry, radiation chemistry, geochemistry, and radiochemistry programs.
There is no other university facility with the combined capabilities of the OSU Radiation Center in the western half of the United States.
Located in the Radiation Center are many items of specialized equipment and unique teaching and research facilities.
They include a TRI GA" Mark II research nuclear reactor; a liOCo gamma irradiator; a large number of state-of-the art computer-based gamma radiation spectrometers and associated high purity germanium detectors; and a variety of instruments for radiation measurements and monitoring.
Specialized faci lities for radiation work include teaching and research laboratories with instrumentation and related equipment for performing neutron activation analysis and radiotracer studies; laboratories for plant experiments involving radioactivity; a facility for repair and calibration of radiation protection instrumentation; and facilities for packaging radioactive materials for shipment to national and international destinations.
Also housed in the Radiation Center is the Advanced Thermal Hydraulics Research Laboratory (ATHRL) which is used for state-of-the-art two-phase flow experiments.
Within ATI-IRL is located the NuScale integral Systems Test-2 (NIST-2) facility, a nuclear power plant test facility that is instrumental in the design certification of the NuScale small modular reactor. The NIST-2 facility is constructed of all stainless-steel components and is capable of operation at full system pressure (1500 psia) and full system temperature (600°F).
All components are 1/3 scale height and 1/254.7 volume scale. The current testing program is examining methods for natural circulation startup, helical steam generator heat transfer perfonnance, a wide range of design basis, and beyond design basis, accident conditions.
The Advanced Nuclear Systems Engineering Laboratory (ANSEL) is the home to two major them1al-hydraulic test facilities: the High Temperature Test Facility (HTTF) and the Hydro-mechanical Fuel Test Facility (HMFTF). The HTIF is a 1/4 scale model of the Modular High Temperature Gas Reactor. The vessel has a ceramic lined upper head and shroud capable of operation at 850°C (well mixed helium).
The design will allow for a maximum operating pressure of I.0MPa and a maximW11 core ceramic temperature of J 600°C.
The nominal working fluid will be helium with a core power of approximately 600 kW (note that electrical heaters are used to simulate the core power). The test facility also includes a scaled reactor cavity cooling system, a circulator, and a heat sink in order to complete the cycle. The I-ITTF can be used to simulate a wide range of accident scenarios in gas reactors to include the depressurized conduction cooldown and pressurized conduction cooldown events. The HMFTF is a testing facility which will be used to produce a database of hydro-mechanical information to supplement the qualification of the prototypic ultrahigh density U-Mo Low Enriched Uranium fuel which will be implemented into the U.S. High Perfonnance Research Reactors upon their conversion to low enriched fuel. This data in tum will be used to verify cun-ent theoretical hydro-and thermo-mechanical codes being used during safety analyses. The maximum operational pressure of the HMFTF is 600 psig with a maximum operational temperature of 450°F.
The Radiation Center staff regularly provides direct support and assistance to OSU teaching and research programs.
Areas of expertise commonly involved in such efforts include nuclear engineering, nuclear and radiation chemistry, neutron activation analysis, radiation effects on biological systems, radiation dosimetry, environmental radioactivity, production of short-lived radioisotopes, radiation shielding, nuclear instmmentation, emergency response, transportation of radioactive materials, instrument calibration, radiation health physics, radioactive waste disposal, and other related areas.
ln addition to formal academic and research support, the Center's staff provides a wide variety of other services including public tours, instructional programs, and professional consuJtation associated witJ1 the feasibility, design, safety, and execution of experiments using radiation and radioactive materials.
PEOPLE This section contains a listi11g of all people who were residents of the Radiation Center or who worked a significant amount of time at the Center during this reporting period.
It should be noted that not all of the faculty and students who used the Radiation Center for their teaching and research are listed.
Summary infonnation on the number of people involved is given in Table VI. I while individual names and projects are listed in Table VI.2.
Radiation Center Staff Steven Reese, Director Nicole Thompson, Office Manager Erica Alvey Aguilera, Receptionjst Zane Tucker, Reactor Administrator/Assistant Director, Senior Reactor Operator Celia Oney, Reactor Supervisor, Senior Reactor Operator Anthony Coke, Senior Reactor Operator Scott Menn, Senior Health Physicist Adam Stricke,~ Health Physicist Leah 1lfinc, Neutron Activation Analysis Manager Steve Smith, Development Engineer, Senior Reactor Operator Dan Sturdevant, Custodian Matthew Berry, Business Manager Christopher Thompson, Director Info-Technology Bhavya Singh, Network Administrator Oden Armstrong, Reactor Operator (Student)
Annie Givens, Reactor Operator (Stl1dent)
Jan Kessler, Reactor Operator (Student)
Drake Martin, Reactor Operator (Student)
Gregory McCoy, Reactor Operator (Student)
Nathaniel McNichols, Reactor Operator (Student)
Robert Riley, Reactor Operator (Student)
Paul Sprague, Reactor Operator (Student)
Samuel Stein, Reactor Operator (Student)
Quinton Williams, Reactor Operator (Student)
Silas Barton, Health Physics Monitor (Student)
Anastasia Kaurova, Health Physics Monitor (Student)
Erin McGee, Health Physics Monitor (Student)
Alexander Spurling, Health Physics Monitor (Student)
Reactor Operations Committee Samuel Briggs OSU School of Nuclear Science and Engineering Abi Tavakoli Farsoni OSU School of Nuclear Science and Engineering Dan Harlan OSU Radiation Safety Trevor How"rd OSU School of Nuclear Science and Engineering Jere Jenkins Texas A&M University Scott Menn OSU Radiation Center Celia Oney (1101 voting)
OSU Radiation Center Steven Reese (1101 voting)
OSU Radiation Center Julie Tucker OSU Mechanical, Industrial, and Manufacturing Engineering Zane Tucker OSU Radiation Center Haori Yang OSU School of Nuclear Science and Engineering
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- Faculty Samuel Briggs Associate Professor, Nuclear Science and Engineering Alexander Chemey Assistant Professor, Nuclear Science and Engineering Tianyi Chen Assistant Professor, Nuclear Science and Engineering Abi Tavakoli Farsoni Associate Professor, Nuclear Science and Engineering Mark Galvin Associate Professor (Senior Research), Nuclear Science and Engineering lzabela Gutowska Assistant Professor, Nuclear Science and Engineering David Ham,by Professor Emeritus, Nuclear Science and Engineering Kathryn Higley Distinguished Professor, Nuclear Science and Engineering l
Trevor Howard Assistant Professor, Nuclear Science and Engineering Walter Loveland Professor Emeritus, Chemistry Wade Marcum Senior Associate Dean, College of Engineering Professor, Nuclear Science and Engineering Devin McGlamery Postdoctoral Scholar, Nuclear Science and Engineering Scott Menn Senior Health Physicist, Radiation Center Guillaume Mignot Assistant Professor (Senior Research), Nuclear Science and Engineering Leah Mine Professor, Anthropology Professor (Senior Research), Radiation Center Alena Paulenova Professor Emeritus, Nuclear Science and Engineering Leila Ranjbar Director Online Programs, Nuclear Science and Engineering Senior Instructor, Nuclear Science and Engineering Steven Reese Director, Radiation Center Associate Professor, Nuclear Science and Engineering Gurpreet Singh Facilities Engineer 2, Nuclear Science and Engineering Zane Tucker Reactor Administrator/Assistant Director, Radiation Center Aaron Weiss Senior Faculty Research Assistant, Nuclear Science and Engineering Brian Woods School Head and Professor, Nuclear Science and Engineering Qiao Wu Professor, Nuclear Science and Engineering Haori Yang Associate Professor, Nuclear Science and Engineering
FACILITIES Research Reactor The Oregon State University TRlGA Reactor" {OSTR) is a water-cooled, swimming pool type research reactor which uses uranium/zirconium hydride fuel elements in a circular grid array. The reactor core is surrounded by a ring of graphite which serves to reflect neutrons back into the core. The core is situated near the bottom of a 22-fool 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 al a maximum steady state power of 1.1 MW and can also be pulsed up to a peak power of about 2500 MW.
The OSTR has a number of different irradiation facilities including a pneumatic transfer tube, a rotating rack, a thermal column, four beam ports, five sample holding (dummy) fuel elements for special in-core irradiations, an in-core irradiation tube, and a cadmium-lined in-core irradiation tube for experiments requiring a high energy neutron flux.
The pneumatic transfer facility (called a Rabbit) enables samples to be inserted and removed from the core in four to five seconds. Consequently, this facility is normally used for neutron activation analysis involving short-lived radionuclides. On the other hand, the rotating rack is used for much longer irradiation of samples (e.g., hours). The rack consists of a circular array of 40 tubular positions each 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 of samples. Over 99% of the neutrons in the thermal colum n are thermal neutrons. Graphite blocks arc removed fi-om the thermal column to enable samples to be positioned inside for irradiation.
The beam ports are tubular penetrations in the reactor's main concrete shield which enable neutron and gamma radiation to stream from the core when a beam port's shield plugs are removed. The neutron radiography facility utilized the tangential beam port (beam port #3) to produce ASTM £545 category I radiography capability. The other beam ports are available for a variety of experiments.
If samples irradiated require a large neutron tluence, especially from higher energy neutrons, they may be placed in the in-core irradiation tube ([CIT), located in one of several in-core laltice positions.
The cadmium-lined io-core irradiation tube (CLICIT) enables samples to be irradiated in a high 0ux region near the center of the core. The cadmium lining in the faci lity eliminates thermal neutrons and thus permits sample exposure to higher energy neutrons only. The cadmium-lined end of this air-filled aluminum irradiation tube is inserted into an inner grid position of the reactor core which would normally be occupied by a fuel element. It is the same as the ICIT except for the presence of the cadmium lining.
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- FACILITIES Instructional Uses of the OSTR Instructional use of the reactor is twofold. First, it is historically used for classes in Nuclear Engineering, Radiation Health Physics, and Chemistry at both the graduate and undergraduate levels to demonstrate numerous principles which have been presented in the classroom. Basic neutron behavior is the same in small reactors as it is in large power reactors. Many demonstrations and instructional experiments can be performed using the OSTR which cannot be carried out with a commercial power reactor. Sho1ter-term demonstration experiments are also perfonned for many undergraduate students in Physics, Cl1emistry, and Biology classes, as well as for visitors from other universities and colleges, from high schools, and from public groups.
The second instmctionaJ application of the OSTR involves educating reactor operators, operations managers, and health physicists. The OSTR is in a unique position to provide such education since curricula must include hands-on experience at an operating reactor and in associated laboratories. The many types of educational programs that the Radiation Center provides are more fully described in Part VI of this report.
During this reporting period, the OSTR accommodated a number of different OSU academic classes and other academic programs. In addition, portions of classes from other Oregon universities were also supported by the OSTR.
Research Uses of the OSTR The OSTR is a unique and valuable tool for a wide variety of research applications and serves as an excellent source of neutrons and/or gamma radiation. The most commonly used experimental technique requiring reactor use is instrnmental neutron activation analysis (JNAA). This is a particularly sensitive method of elemental analysis which is described in more detail in Pait VI.
The OSTR's irradiation facilities provide a wide range of neutron flux levels and neutron flux qualities which are sufficient to meet the needs of most researchers. This is true not only for INAA, but also for other experimental purposes such as the 39 Ar/40 Ar ratio and fission track methods of age dating samples.
Analytical Equipment The Radiation Center has a large variety of radiation detection instrumentation. This equipment is upgraded as necessary, especially the gamma ray spectrometers with their associated computers and gemrnnium detectors. Additional equipment for classroom use and an extensive inventory of portable radiation detection instrw11entation are also available.
Radiation Center nuclear instmmentation 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 of the analytical instruments. Use ofRadiation Center equipment extends beyond that located at the Center, and instrumentation may be made available on a loan basis to OSU researchers in other departments.
Radioisotope Irradiation Sources The Radiation Center is equipped with a Gammacell 220 60Co irradiator which is capable of delivering high doses of gamma radiation over a range of dose rates to a variety of materials.
Typically, the irradiator is used by researchers wishing to perfonn mutation and other biological effects studies; studies in the area of radiation chem is try; dosimeter testing; sterilization of food materials, soi Is, 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 variety of smaller (,()Co, 1J1Cs, 226Ra, plutonium-beryllium, and other isotopic sealed sources of various radioactivity levels which are available for use as inadiation sources.
During this reporting period, there was a diverse group of projects using the 6°Co irradiator. These projects included the irradiation of a variety of biological and botanical materials.
In addition, the irradiator was used for sterilization of several media and the evaluation of the radiation effects on different materials. Table UT. l provides use data for the Gammacell 220 irradiator.
FACILITIES Laboratories and Classrooms The Radiation Center is equipped with a number of different radioactive material laboratories designed to accommodate research projects and classes offered by various OSU academic departments or off-campus groups.
Instructional facilities available at the Center include a laboratory especially equipped for teaching radiochemistry and a nuclear instrwnentation teaching laboratory equipped with modular sets of counting equipment which can be configured to accommodate a variety of experiments involving the measurement of many types of radiation. The Center also has two student computer rooms.
ln addition to these dedicated instructional facilities, many other research laboratories and pieces of specialized equipment are regularly used for teachjng. In particular, classes are routinely given access to gamma spectrometry equipment located in Center laboratories. A number of classes also regularly use the OSTR and the Reactor Bay as an integral part of their instnictional coursework.
There are two classrooms in the Radiation Center which are capable of holding about 35 and 18 students. In addition, there are two smaller conference rooms and a library suitable for graduate classes and thesis examinations. As a service to the student body, the Radiation Center also provides an office area for the student chapters of the American Nuclear Society and the Health Physics Society.
All of the laboratories and classrooms are used extensively during the academic year. A listing of courses accommodated at the Radiation Center during this reporting period along with their enrollments is given in Table lll.2.
Instrument Repair and Calibration Facility The Radiation Center has a facility for the repair and calibration of essentially all types ofradiation monitoring instrumentation. This includes instruments for the detection and measurement of alpha, 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 repair and calibration facility is used regularly throughout the year and is absolutely essential to the continued operation of the many different programs carried out at the Center. In addition, the absence of any comparable facility in the state has led to a greatly expanded instrument calibration program for the Center including calibration of essentially all radiation detection instrw11ents 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 Department of Energy, the Oregon Public Utilities Conm1ission, the Oregon Health and Sciences University, the Army Corps of Engineers, and the U.S. Environmental Protection Agency.
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- FACILITIES Purpose of Irradiation Biological Studies Botanical Studies Dosimeter Analysis Material Evaluation Other Sterilization Totals Table 111.1 Gammacell 220 6°Co lrradiator Use Dose Range Samples (rads) mold, human cells 2.5xl02 to l.0xl05 cuttings, seeds, stolon 2.5xl 03 to l.0xl04 dosimeter materials 5.0x I 05 to 5.0x I 06 propylene glycol, carbon nanotubcs, chemicals, plastic 2.0x I 06 to I.Ox I 08 material electronic components, l.1 x I 08 to l.2x I 08 crystals wood, clay minerals, fish food, ground flower, medical 1.5x 106 to 3.0xl06 devices, nanofibers, PI IA, scaffolds, soil Number of Use Time lrradia-tions (hours) 24
- 5. 18 11 0.30 32 355.53 12 2,227.78 2
1,140.13 57 668.75 138 4,397.67
FACILITIES COURSE#
NSE 236*
NSE 401/501/601 NSE 405/505/605 NSE 406/506/606 NSE 407/507 NSE 435/535 NSE 446/546 NSE 455/555**
NSE 457/557**
NSE 467/567 NSE 474 NSE 475 SE 481
- NSE 499 NSE 499/599 NSE 503/603*
NSE 531 NSE 536*
NSE 565 Table 111.2 Student Enrollment in Courses Taught or Partially Taught at the Radiation Center UMBER OF STUDENTS CREDITS COURSE TITLE Summer Fall Winter Spring 2024 2024 2025 2025 4
Nuclear Radiation Detection and Instrumentation 46 1-16 Research 5
20 17 14 1-16 Reading and Conference I
2 1-16 Projects 6
I I
Seminar/Occupational Experiences 15 4
Radiation Shielding and External Dosimetry 37 4
Microstructure Characterization of Structural and 9
Energy Materials 3
Reactor Operator Training I 20 2
Nuclear Reactor Laboratory 34 4
Nuclear Reactor Thermal Hydraulics 38 4
Nuclear Systems Design l 32 4
Nuclear Systems Design II 32 4
Radiation Protection 37 3
ST/Actinides 14
.}
ST/Radiation Damage in Metals 13 1-16 Thesis/Dissertation 24 44 41 40 3
Radiophysics 12 4
Advanced Radiation Detection and Measurement 13 3
Applied Themrnl Hydraulics 9
FACILITIES Table 111.2 (continued)
Student Enrollment in Courses Taught or Partially Taught at the Radiation Center UMBER OF STUDENTS COURSE#
CREDITS COURSE TITLE NSE 599 3
ST/Computational Credibility NSE 667 3
Advanced Thermal Hydraulics I*
Courses from Other OSU Departments:
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- COURSE #
ANTII 425*
CH 462*
ECE 530*
ME 552*
SUS 103*
ST Special Topics CREDITS COURSE TITLE 4
Ceramic Analysis in Archaeology
.)
Experimental Chemistry ll 4
Contemporary Energy Applications 4
Measurements in Fluid Mechanics and Heat Transfer 4
Introduction to Climate Change OSTR used occasionally for demonstration and/or experiments.
- OSTR used heavily Summer Fall Winter Spring 2024 2024 2025 2025 8
10 Summer Fall Winter Spring 2024 2024 2025 2025 4
26 l l 13 44
REACTOR Operating Statistics During the operating period between July 1, 2024 and June 30, 2025, the reactor produced 1,371 MWH of thenual power during its 1,474 critical hours.
Experiments Performed At the end of the reporting period there were five approved reactor experiments available for use in reactor-related programs. They are:
A-I Nonna! TRIGA Operation (no sample irradiation)
B-3 Irradiation of Materials in the Standard OSTR Irradiation Facilities 8-29 Reactivity Worth of Fuel B-31 TRIGA Flux Mapping B-36 Irradiation of Fissionable Materials in the OSTR Of these available experiments, four were used during the reporting period. Table IV.4 provides information related to the frequency of use and the general purpose or their use.
Inactive Experiments Presently, 39 experiments are in the inactive file. This consists of experiments which have been performed in the past and may be reactivated. Many of these experiments are now performed under the more general experiments listed in the previous section. The following list identifies these 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 TRJGA A-5 Copper Wire Irradiation A-6 In-core Irradiation of Lif Crystals A-7 Lnvestigation ofTRIGA's Reactor Bath Water Temperature Coefficient and High Power Level Power Fluctuation B-1 Activation Analysis of Stone Meteorites, Other Meteorites, and Terrestrial Rocks 8-2 Measurements of Cd Ratios of Mn, In, and Au in Thermal Column 8-4 Flux Mapping 8-5 In-core lrradiation of Foils for Neutron Spectral Measurements B-6 Measurements of Neutron Spectra in External Irradiation Facilities 8-7 Measurements of Gamma Doses in External Irradiation Facilities 8-8 Isotope Production 8-9 Neutron Radiography 8-l O Neutron Diffraction B-11 Irradiation of Materials Involving Specific Quantities of Uranium and Thorium in Standard OSTR Irradiation Facilities (Discontinued Feb. 28, 20 l 8) 8-12 Exploratory Experiments (Discontinued Feb. 28, 2018) 8-13 This experiment number was changed to A-7 8-14 Detection of Chemically Bound Neutrons 8-15 This experiment number was changed to C-1 8-16 Production and Preparation of '8F B-17 Fission Fragment Gamma Ray Angular Correlations 8-18 A Study of Delayed Status (n, y) Produced Nuclei 8-19 Instrument Timing via Light Triggering 8-20 Sinusoidal Pile Oscillator 8-21 Beam Port #3 Neutron Radiography Facility 8-22 Water Flow Measurements Through TRIGA Core 8-23 Studies Using TRlGA Thermal Column (Discontinued Feb. 28, 2018)
B-24 General Neutron Radiography B-25 Neutron Flux Monitors 8-26 Fast Neutron Spectrum Generator 8-27 Neutron Flux Determination Adjacent to the OSTR Core
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REACTOR B-28 Gamma Scan of Sodium (TED) Capsule 8 -30 NAA of Jet, Diesel, and Furnace Fuels 8-32 Argon Production Facility B-33 Irradiation of Combustible Liquids in LS (Discontinued Feb. 28, 2018) 8-34 Irradiation of Enriched Uranium in the Neutron Radiography Facility (Discontinued Feb. 28, 2018)
B-35 Irradiation of Fissile Materials in the Prompt Gamma Neutron Activation Analysis (PGNAA)
Facility (Discontinued Feb. 28, 2018)
C-1 Pu-O2 Transient Experiment Unplanned Shutdowns There were eight unplanned reactor shutdowns during the current reporting period. Table IV.5 details these events.
Activities Pursuant to 10 CFR 50.59 There was one safety evaluation perfonned in support of the reactor this year. It was:
25-01 Minor Updates to Experiments A-1, B-31, and B-36 Amended Experiment A-1 to remove a reference to square wave operations. Amended B-31 to add powders to the allowed materials for Aux measurement. Amended B-36 to replace a reference to the PGNAA with BP 1.
There were IO new screens perfom1ed in support of the reactor this year. They were:
24-08 Revisions to OSTROPs 4, IO, and 22 Minor revisions to the procedures for reactor operations, experimental facilities, and emergency power system.
24-09 Skimmer Replacement Replaced the skimmer in the primary tank with a new model and updated disassembly instructions in OSTROP 7.
24-10 Revisions to Emergency Response Implementing Procedures (ERIPs)
Updated names to reflect staffing changes plus other minor updates.
24-1 1 Revisions to OSTRO P 16 Minor revisions to the procedure for annual surveillance and maintenance.
25-01 Revisions to RCHPPs 1 and 5 Minor revisions to the procedures for the OSU radiation protection program and for receipt of radioactive materials.
25-02 Revisions to OSTROPs 2, 4, 13, and 26 Minor revisions to the procedures for the startup checklist, reactor operations, monthly surveillance and maintenance, and background investigations.
25-03 Addition of Neutron Shielding to the NRF Added borated polyethylene shielding in front of the NRF shutter with a removable stepped plug in front of the shutter opening.
25-04 Revisions to RCHPPs 15 and 37 Minor revisions to the procedures for the environmental TLD program and dosimetry.
25-05 OSTROP 10 Update for NRF Shielding Updated the experimental facilities procedure to reflect the additional NRF shielding added under Screen 25-03.
25-06 Revisions to RCHPP 6 Minor revisions to the procedure for shipping radioactive materials.
Surveillance and Maintenance Non-Routine Maintenance July 2024 Made repairs to door controls for Neutron Radiography Facility.
Cleaned the cooling tower water level sensor.
August 2024 Replaced fuse in cooling tower fan variable frequency drive (VFD).
Replaced pool skimmer in reactor tank.
Cleaned cooling tower and greased the cooling fan bearings.
Septembe1* 2024 Replaced demineralizer resi11.
REACTOR October 2024 Replaced the detector for Area Radiation Monitor #2.
Replaced the oxidation-reduction potential (ORP) pump on the secondary water chemical addition system.
Replaced the rod position indicator for the shim rod.
November 2024 December 2024 Replaced belt on ventilation supply fan.
January 2025 Installed radio repeaters throughout the building to improve reception for two-way radios.
February 2025 Repositioned NRF shutter slightly while investigating dose rates in the facility.
March 2025 April 2025 Added additional borated polyethylene neutron shielding over the NRF shutter.
Replaced the electromagnet for the regulating rod.
May 2025 Replaced the rod position indicator for the regulating rod.
June 2025
1* * * * * * * * * * *,: * * * * * * * *
- REACTOR Table IV.1 Present OSTR Operating Statistics Operational Data For LEU Core Annual Values (2024/2025)
MWH of Energy Produced 1,371 MWD of Energy Produced 57.1 Grams 2350 Used 76 Number ofFuel Elements Added to(+) or Removed(-)
0 from the Core Number of Pulses 39 Hours Reactor Critical 1,474 Hours at Full Power ( 1 MW) 1,361 Number of Startup and Shutdown Checks 250 Number oflrradiation Requests Processed 300 Number of Samples Irradiated 2,243 Cumulative Values 21,334 888.9 1,215 91 509 22,706 21,099 3,857 4,122 32,830
REACTOR Table IV.2 OSTR Use Time in Terms of Specific Use Categories OSTR Use Category Annual Values Cumulative Values (hours)
(hours)
Teaching (departmental and others) 63 13,986 OSU Research 581 27,266 Off Campus Research 2,309 67,821 Facility Time 85 8,043 Total Reactor Use Time 3,038 117,116 Table IV.3 OSTR Multiple Use Time Number of Users Annual Values (hours)
Cumulative Values (hours)
Two 473 13,170 Three 230 7,514 Four 119 4,073 Five 42 1,783 Six 22 606 Seven I
183 Eight or more 4
33 Total Multiple Use Time 891 27,362
r* * *
- REACTOR Experiment umber A-I B-3 B-29 B-3 I B-36 Total Type of Event Manual Shutdown Manual SCRAM Manual Shutdown Manual SCRAM Manual Shutdown l
Table IV.4 Use of OSTR Reactor Experiments Research Teaching Facility Use Total 0
5 6
11 259 6
19 284 0
0 0
0 0
0 3
.)
2 0
0 2
261 11 28 300 Table IV.5 Unplanned Reactor Shutdowns and SCRAMS Number of Cause of Event Occurrences I
Cooling tower fan failure I
Loss of off-site electrical power 2
Low secondary flow
.)
Reg rod drop I
Reg rod drop
Figure IV.1 Monthly Surveillance and Maintenance (Sample Form)
OSTROP 13, Rev. LEU-12 Surveillance & Maintenance for the Month of in the year 20 SURVEILLANCE & MAJNTENANCE TARGET DATE DATE REMARKS
[SHADE INDICATES LICENSE REQUIREMENT]
LIMJTS AS FOUND DATE NOTTO BE COMPLETED EXCEEDED*
~ -
MAXIMUM IIIGH:
1-:-!C'HES REACTOR TANK HIGH AND LOW WATER 1
LEVEL ALARMS MOVEMENT LOW:
11\CHES
+/-3 INCHES ANN:
2 REACTOR TANK TEMPERAT URE ALARM FUNCTIONAL Tested @ __
CHECK 3.A CHANNEL TEST OF STACK CAM GAS CI IANNEL 8.5E4+/-
Ann.?
_cpm Ann.
8500 cpm 3.B CHANNEL TEST OF STACK CAM PARTICULATE 8.5E4+/-
Ann.?
Ann.
CHANNEL 8500 cpm
_cpm 3.C CHANNEL TEST OF REACTOR TOP CAM 8.5E4+/-
Ann.?
Ann.
PARTICULATE CHANNEL 8500 cpm
_cpm 4
MEASUREMENT OF REACTOR PRIMARY
<5 µmho\cm WATER CONDUCTJVITY 5
CHANGE LAZY SUSAN FILTER FILTER NIA CHANGED 6
REACTOR TOP CAM OIL LEVEL CHECK OSTROP 13.8 NEED OIL? __
NIA 7
STACK CAM OILLEVELCHECK OSTROP 13.9 NEED OIL?
NIA 8
EMERGENCY DIESEL GENERATOR CHECKS
> 50% I Oil ok?
RABBIT SYSTEM RUN TIME Total hours/Hours I
NIA on current brushes IO OIL TRANSIENT ROD BRONZE BEARJNG WD-40 NIA II CRANE INSPECTION Hooks I I Joist NIA Rope 12 WATER MONITOR CHECK RCHPP 8 App. F.4 NIA 13 EMERGENCY LIGHT TESTING 30 seconds?
- Date not to be exceeded is only applicable to shaded items. It is equal lo the time completed last month plus six weeks.
Figure IV.2 Quarterly Surveillance and Maintenance (Sample Form)
OSTROP 14, Rev. LEU-8 Surveillance & Maintenance for the 1st / 2nd I 3rd I 4th Quarter of 20 SURVEILLANCE & MAINTENANCE LIMITS AS FOUND TARGET DATE NOT TO DATE REMARKS&
[SHADE INDICATES LICENSE REQUIREMENT)
DATE BE EXCEEDED*
COMPLETED fNITIALS I
REACTOR OPERATION COMMITTEE (ROC) AUDIT QUARTERLY**
2 fNTERNALAUDIT OF OSTROPs QUARTERLY 3
PERIODIC ROC MEETING QUARTERLY**
4 ERP INSPECTIONS QUARTERLY 5
ROTATING RACK CHECK FOR UNKNOWN SAMPLES EMPTY 6
WATER MONITOR ALARM CHECK FUNCTIONAL 7.A CHECK FILTER TAPE SPEED ON STACK MONITOR 1"/HR+/- 0.2 7.8 CHECK FILTER TAPE SPEED ON CAM MONITOR l"/HR+/- 0.2 8
INCORPORATE 50.59s INTO DOCUMENTATION QUARTERLY 9
EMERGENCY CALL LIST QUARTERLY ARM SYSTEM ALARM CHECKS ARM I
2 3S 3E 4 5 7 8
9 10 11 12 AUD 10 FUNCTIONAL LJGHT PANEL ANN II OPERATOR LOG QUARTERLY
- Date not to be exceeded is only applicable to shaded items. It is equal to the time completed last quarter plus four months.
- ROC meetings are generally performed when school is in session, thus 3rd quarter may not have a meeting.
Figure IV.3 Semi-Annual Surveillance and Maintenance (Sample Form)
OSTROP 15, Rev. LEU-12 Surveillance & Maintenance for the 1st / 2nd Half 20 SURVEILLANCE & MAINTENANCE TARGET DATE NOT DATE REMARKS&
[SHADE INDICATES LICENSE REQUIREMENT]
LIMITS AS FOUND DATE TOBE COMPLETED INITIALS EXCEEDED" NO WITHDRAW NEUTRON SOURCE COUNT RATE INTERLOCK 2=5 cps TRANSIENT ROD AIR INTERLOCK NO PULSE CHANNEL TESTS PULSE MODE ROD MOVEMENT INTERLOCK NO MOVEMENT I
OF REACTOR INTERLOCKS MAXIMUM PULSE REACTIVITY INSERTION LIMIT
- 5 $2.25 TWO ROD WITHDRAWAL PROHIBIT I ONLY PULSE PROIIIBIT ABOVE I kW 2=1 kW PREVIOUS PULSE DATA FOR COMPARISON:
~0%
PULSE# --
PULSE#
2 TEST PULSE CIIANGE MW MW 3
CLEANING & LUBRICATION OF TRANSIENT ROD CARRIER INTERNAL BARREL 4
LUBRICATION OF BALL-NUT DRIVE ON TRANSIENT ROD CARRIER 5
LUBRICATION OF THE ROTATING RACK BEARJNGS WD-40 6
CONSOLE Cl JECK LIST OSTROP IS.VI 7
STANDARD CONTROL ROD MOTOR CHECKS LO-17 BODINE OIL HIGH 8
FUNCTIONAL CHECK OF HOLDUP TANK WATER LEVEL ALARMS OSTROP 15.IX FULL BRUSH INSPECJTON SAMPLE INSERTION OBSERVED 9
INSPECTION OF THE PNEUMATIC TRANSFER SYSTEM INSERTION/
AND WITHDRAWAL WITHDRAWAL TIME CHECK TIME
- Date not to be exceeded is only applicable to shaded items. It is equal to the date last time plus 7.5 months.
Figure IV.4 Annual Surveillance and Maintenance (Sample Form)
OSTROP 16, Rev. LEU-15 Annual Surveillance and Maintenance for 20 SURVEILLANCE AND MAINTENANCE AS TARGET DATE NOT DATE REMARKS&
[SHADE INDICATES LICENSE REQUIREMENT]
LIMITS FOUND DATE TOBE COMPLETED INlTIALS EXCEEDED*
BlENNlAL INSPECTION OF FFCRs I
OSTROP 12.0 TRANS 2
STANDARD CONTROL ROD DRIVE INSPECTON OSTROP 16.2 3
CONTROL ROD CALIBRATION OSTROP9 TRANS SAFE SHIM REG CONTROL ROD SCRAM
- 2 sec 4
WITHDRAWAL INSERT1ON &
W/D
<50 sec SCRAM TIMES INSERT
- 50 sec FUEL ELEMENT INSPECTION FOR SELECTED 2'. 20% FE's inspected.
5 ELEMENTS No damage, deterioration or swell.
6 REACTOR POWER CALIBRATION OSTROP8 7
CALIBRATION OF REACTOR TANK WATER OSTROP 16.8 TEMPERATURE METERS CONTINUOUS Particulate Monitor 8
AIR MONITOR RCHPPl8 CALIBRATION Gas Monitor 9
CAM OIL/GREASE MAINTENANCE STACK MONITOR Particulate Monitor RCHPPs 10 CALIBRATION 18 & 26 Gas Monitor l l STACK MONITOR OIL/GREASE MAINTENANCE 12 AREA RADIATION MONITOR CALIBRATION RCHPPl8
- Date not be exceeded is only applicable to shaded items. It is equal to the date completed last year plus IS months.
For biennial license requirements, it is equal to the date comoleted last time olus 2 1/2 vears.
Figure IV.4 {continued)
Annual Surveillance and Maintenance (Sample Form)
OSTROP 16, Rev. LEU-15 Annual Surveillance and Maintenance for 20 SURVEILLANCE AND MAINTENANCE AS TARGET DATE NOT DATE REMARKS LIMITS TOBE
[SHADE INDICATES UCENSE REQUIREMENT]
FOUND DATE EXCEEDED*
COMPLETED
& INITIALS 13 CORE EXCESS
- 5$7.55 DAMPERS I5T FLOOR 14 REACTOR BAY VENTILATION SYSTEM SHUTDOWN TEST CLOSE IN <60 SECONDS 4171FLOOR 15 CRANE INSPECTION 16 SNM PHYSICAL INVENTORY NIA NIA OCTOBER
~.~--
e-17 !MATERIAL BALANCE REPORTS NIA NIA NOVEMBER CFO TRAINlNG GOOD SAM TRAINING ERP REVIEW MEMO ERP DRILL CPR CERT FOR:
EMERGENCY CPR CERT FOR:
18
RESPONSE
FIRST AID CERT FOR:
PLAN FIRST AID CERT FOR:
EVACUATION DRfLL AUTO EVAC ANNOUNCEMENT TEST ERP EQUIPMENT INVENTORY BIENNIAL SUPPORT AGREEMENTS PSPREVIEW MEMO PSPDRILL PHYSICAL PART 37 PLAN REVIEW 19 SECURITY PART 37 PLAN DRILL PLAN DPS TRAINING LOCK/SAFE COMBO CHANGES AUTHORIZATION LIST UPDATE
- Date not be exceeded is only applicable to shaded items. It is equal to the date completed last year plus 15 months.
For biennial license requirements, it is equal to the date completed last time plus 2 1/2 years.
Figure IV.4 (continued)
Annual Surveillance and Maintenance (Sample Form)
OSTROP 16, Rev. LEU-15 Annual Surveillance and Maintenance for 20 SURVEILLANCE AND MAINTENANCE AS TARGET DATE NOT DATE REMARKS
[SHADE INDICATES LICENSE REQUIREMENT]
LIMITS FOUND DATE TOBE COMPLETED
& fNlTIALS EXCEEDED*
20 ANNUAL REPORT NOV I OCT!
NOVI 21 ANNUAL INVENTORY OF SCANNED RECORDS ANNUAL 22 KEY INVENTORY ANNUAL 23 REACTOR TANK AND CORE COMPONENT NO WHITE SPOTS INSPECTION 24 EMERGENCY LIGHT LOAD TEST 25 BEAM PORT # ! IRRADIATION FACILITY INTERLOCKS 26 NEUTRON RADIOGRAPHY FACILTIY INTERLOCKS PRIMARY
- 5 5 µmhos 27 WATER CONDUCTIVITY BULK SHIELD TANK
- 5 5 µmhos 28 EXPERIMENTS REVIEW MEMO 29 REACTOR OPERATOR LICENSE CONDITIONS
- Date not be exceeded is only applicable to shaded items. It is equal to the date completed last year plus I 5 months.
For biennial license requirements, it is equal to the date completed last time plus 2 1/2 years.
RADIATION PROTECTION Introduction The purpose of the radiation protection program is to ensure the safe use of radiation and radioactive material in the Radiation Center's teaching, research, and service activities, and in a similar manner to the fulfillment of all regulatory requirements of the State of Oregon, the U.S. Nuclear Regulatory Commission, and other regulatory agencies.
The comprehensive nature of the program is shown in Table Y. I which lists the program's major radiation protection requirements and the performance frequency for each item.
The radiation protection program is implemented by a staff consisting of a Senior I lea Ith Physicist, a Health Physicist, and several part-time Health Physics Monitors (see Pait II).
Assistance is also provided by the reactor operations group, the neutron activation analysis group, the Scientific Instrument Technician, and the Radiation Center Director.
The data contained in the following sections have been prepared to comply with the current requirements of Nuclear Regulatory Commission (NRC) Facility License No. R-106 (Docket No. 50-243) and the Technical Specifications contained in that license. The material has also been prepared in compliance with Oregon Department of Energy Rule No.
345-030-0 IO which requires an annual report of environmental effects due to research reactor operations.
Within the scope of Oregon State University's radiation protection program, it is standard operating policy to maintain all releases of radioactivity to the unrestricted environment and all exposures to radiation and radioactive materials at levels which arc consistently "as low as reasonably achievable" (ALARA).
Environmental Releases The annual reporting requirements in the OSTR Technical Specifications state that the licensee (OSU) shall include "a summary of the nature and amount of radioactive effiuents released or discharged to the environs beyond the effective control of the 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 arc discussed briefly below. Data regarding these effluents arc also summarized in detail in the designated tables.
Liquid Effluents Released Liquid Effluents Oregon State University has implemented a policy to reduce the volwne of radioactive liquid cffiuents to an absolute minimum. For example, water used during the ion exchanger
1: * * * * * * *
- I* * * * * * * * * * * * * *
- RADIATION PROTECTION 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.
Liquid effluent are analyzed for radioactivity content at the time it is released to the collection point. For this reporting period, the Radiation Center and reactor made two liquid effluent releases to the sanitary sewer. All Radiation Center and reactor facility liquid effluent data pertaining to this release are contained in Table V.2.
Liquid Waste Generated and Transferred Liquid waste generated from glassware and laboratory experiments is transferred by the campus Radiation Safety Office to its waste processing facility. The annual summary of liquid waste generated and transferred is contained in Table V3.
Airborne Effluents Released Airborne effluents are discussed in tern1s of the gaseous component and the particulate component.
Gaseous Ejftuents Gaseous effluents from the reactor facility are monitored by the reactor stack effluent monitor. Monjtoring is continuous (i.e., prior to, during, and after reactor operations). It is normal for the reactor facility stack effluent monitor to begin operation as one of the first systems in the morning and to cease operation as one of the last systems at the end of the day. All gaseous effluent data for this reporting period are summarized in Table V.4.
Particulate effluents from the reactor facility are also monitored by the reactor facility stack effluent monitor.
Particulate E.lftuents Evaluation of the detectable particulate radioactivity in the stack effluent confinned its origin as naturally-occurring radon daughter products within a range of approximately 3x I 0-11
~tCi/ml to I x IQ*9 µCi/ml. This particulate radioactivity is predominantly 214Pb and 214Bi which is not associated with reactor operations.
There was no release of particulate effluents with a half life greater than eight days, and therefore, the reporting of the average concentration of radioactive particulates with half Lives greater than eight days is not applicable.
Solid Waste Released Data for the radioactive material in the solid waste generated and transferred during this reporting period are summarized in Table V.5 for both the reactor facility and the Radiation Center. Solid radioactive waste is routinely transferred to OSU Radiation Safety. Until this waste is disposed ofby the Radiation Safety Office, it is held along with other campus radioactive waste on the University's State of Oregon radioactive materials license.
Solid radioactive waste is disposed ofby OSU Radiation Safety by transfer to the University's radioactive waste disposal vendor.
Personnel Doses The OSTR annual reporting requirements specify that the licensee shall present a summary of the radiation exposure received by facility personnel and visitors. The swnmary includes all Radiation Center perso1mel who may have received exposure to radiation. These personnel have been categorized into six groups: facility operating personnel, key facility research personnel, facilities services maintenance personnel, students in laboratory classes, campus police and security personnel, and visitors.
Facility operating personnel include the reactor operations and health physics staff. The dosimeters used to monitor these individuals include quarterly TLD badges, quarterly track-etch/albedo neutron dosimeters, montl1ly TLD (finger) extremity dosimeters, pocket ion chambers, and electronic dosimetry.
Key facility research personnel consist ofRadiation Center staff, faculty, and graduate students who perform research usino the reactor reactor-activated materials, or other research facilities present at the Center. The individual dosimetry requirements for these persom1el will vary with the type of research being conducted, but they will generally include quarterly TLD film badge and TLD (finger) extremity dosimeters. If the possibility of neutron exposure exists, researchers are also monitored with a track-etch/albedo neutron dosimeter.
Facilities Services maintenance personnel are nom1ally issued a gamma sensitive electronic dosimeter as their basic monjtoring device.
RADIATION PROTECTION Students attending laboratory classes are issued quarterly Xl3(y) TLD badges, TLD (finger) exlremity dosimeters, and track-etch/albedo or other neutron dosimeters, as appropriate.
Students or small groups of students who attend a one-time lab demonstration and do not handle radioactive materials are usually issued a gamma sensitive electronic dosimeter. These resuJts are not included with the laboratory class students.
OSU police and security personnel are issued a quaiterly Xl3(y) TLD badge to be used during their patrols of the Radiation Center and reactor facilily.
Visitors, depending on the locations visited, may be issued gamma sensitive electronic dosimeters. OSU Radiation Center policy does not nomrnlly allow people in the visitor category to become actively involved in the use or handling of radioactive materials.
An annual summary of the radiation doses received by each of the above six groups is shown in Table V.6. There were no personnel radiation exposures in excess of the limits in I 0 CFR 20 or State of Oregon regulations during the reporting period.
Facility Survey Data The OSTR Technical Specifications require an annual summary of the radiation levels and levels of contamination observed during routine surveys performed at the facility. The Center's comprehensive area radiation monitoring program encompasses the Radiation Center as well as the OSTR, and therefore, monitoring results for both facilities are reported.
Area Ra,lialion 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. 1n 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 total dose equivalenL recorded on the various reactor facility dosimeters is listed in Table V.7 and the total dose equivalent recorded on the Radiation Center area dosimeters is listed in Table V.8. Generally, the characters following the Monitor Radiation Center (MRC) designator show the room number or location.
Routine R"diation {Ind Co11t11111i11{1fio11 Surveys The Center's program for routine radiation and contamination surveys consists of daily, weekly, and monthly measurements throughout the TRJGA reactor facility and Radiation Center.
The frequency of these surveys is based on the nature of the radiation work being carried out at a particular location or on other factors which indicate that surveillance over a specific area at a defined frequency is desirable.
The primary purpose of the routine radiation and contamination survey program is to assure regularly scheduled surveillance over selected work areas in the reactor facility and in the Radiation Center in order to provide current and characteristic data on the status ofradiological conditions. A second objective of the program is to assure frequent on-the-spot personal observations (along with recorded data) whjch will provide advance warning of needed corrections and thereby help to ensure the safe use and handling of radiation sources and radioactive materials. A third objective, which is really derived from successful execution of the first two objectives, is to gather and document information which will help to ensure that all phases of the operational and radiation protection programs are meeting the goal of keeping radiation doses to personnel and releases of radioactivity to the environment "as low as reasonably achievable" (ALARA).
The annual summary of radiation and contamination levels measured during routine facility surveys for the applicable reporting period is given in Table V.9.
Environmental Survey Data The annual reporting requirements of the OSTR Technical Specifications include "an annual summary of environmental surveys perforn1ed outside the facility."
Gamma Radiation Monitoring On-site Monitoring Monitors used in the on-site gamma environmental radiation monitoring program at the Radiation Center consist of the reactor facility stack effluent monitor described in Section V and nine environmental monitoring stations.
During this reporting period, each fence enviromnental station utilized an LiF TLD monitoring packet supplied and processed by Mirion Technologies, Inc., Irvine, California. Each packet contained three LiF TLDs and was exchanged quarterly for a total of 108 samples during the reporting period (9 stations x
r= * * * * * * * * * * * * * * * * * * * * * * * * * *
- 1: * * * * * * * *
- RADIATION PROTECTION 3 TLDs per station x 4 qua11ers). The total number ofTLD samples for the reporting period was 108. A summary of the TLD data is also shown in Table V 10.
From Table V. l O it is concluded that the doses recorded by the dosimeters on the TRIGA facility fence can be attributed to nat11ral back-ground radiation which is about 110 mrem per year for Oregon (Refs. I, 2).
Off-site Monitoring The off-site gamma environmental radiation monitoring program consists of twenty monitoring stations surrounding the Radiation Center (see Figure V l) and six stations located within a 5 mile radius of the Radiation Center.
Each monitoring station is located about four feet above the ground (MRCTE 21 and MRCTE 22 are mounted on the roof oflhe EPA Laboratory and National Forage Seed Laboratory, 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 station per quarter x 4 quarters per year). The total number ofTLD samples for the reporting period was 240. A sLm1mary ofTLD data for the off-site monitoring stations is given in Table V 11.
After a review of the data in Table Y.11, it is concluded that, like the dosimeters on the TRlGA facility fence, all of the doses recorded by the off-site dosimeters can be attributed to natural background radiation which is about 110 mrcm per year for Oregon (Refs. I, 2).
Soil, Water, and Vegetation Surveys The soil, water, and vegetation monitoring program consists of the collection and analysis ofa limited number of samples in each category on an annual basis. The program monitors highly unlikely radioactive material releases from either the TR1GA reactor facility or the OSU Radiation Center and also helps indicate the general trend of the radioactivity concentration in each of the various substances sampled. See Figure Y. I for the locations of the sampling stations for grass (G), soil (S), water (W) and rainwater (RW) samples. Most locations are within a 1,000 foot radius of the reactor facility and the Radiation Center. In general, samples are collected over a local area having a radius of about ten feet at the positions indicated in Figure V.1.
There are a total of22 sampling locations: four soil locations, four water locations (when water is available), and fourteen vegetation locations.
The annual concentration of total net beta radioactivity (minus tritium) for samples collected at each environmental soil, water, and vegetation sampling location (sampling station) is listed in Table V. 12. 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 concentrations were calculated using sample results which exceeded the lower limit of detection (LLD),
except that sample results which were less than or equal to the LLD were averaged in at the corresponding LLD coneenlration.
As used in this report, the LLD has been defined as U1e amount or concentration of radioactive material (in terms of pCi per unit volume or unit mass) in a representative sample which has a 95% probability of being detected.
Identification of specific radionuclides is not routinely carried out as part of this monitoring program, but would be conducted if unusual radioactivity levels above natural backgrOlmd were detected. However, from Table Y.12 it can be seen that the levels of radioactivity detected were consistent with nal11rally occurring radioactivity and comparable to values reported in previous years.
Radioactive Material Shipments A summary of the radioactive material shipments originating from the TRIGA reactor facility, RC license R-106, is shown in Table V.13. A similar swnmary for shipments originating from the Radiation Center's State of Oregon radioactive materials license ORE 90005 is shown in Table V. 14. A summary of radioactive material shipments exported under Nuclear Regulatory Commission general license IO CFR 110.23 is shown in Table V.15.
References I.
U.S. Environmental Protection Agency, "Estimates ofionizing Radiation Doses in the United States, l 960-2000," ORP/CSD 72-1. Office of Radiation Programs, Rockville, Maryland (1972).
- 2.
U.S. Environmental Protection Agency, "Radiological Quality of the Environment in the United States, l 977," EPA 520/1-77-009, Office of Radiation Programs: Washington. D.C. 20460 (1977).
RADIATION PROTECTION Table V.1 Radiation Protection Program Requirements and Frequencies Frequency Radiation Protection Requirement Daily/Weekly/Monthly Perform routine area radiation/contamination monitoring.
Collect and analyze TR1GA primary, secondary, and make-up water Monthly Exchange personnel dosimeters and review exposure reports Jnspcct laboratories Calculate previous month's gaseous eflluent 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 Perfonn and record special radiation surveys Perform thyroid and urinalysis bioassays Conduct orientations and trainings Issue radiation work permits and provide health physics coverage for maintenance operations Prepare, exchange, and process environmental TLD packs Conduct orientations for classes using radioactive materials Quarterly Collect and analyze samples from reactor stack effiuent line Exchange personnel dosimeters and inside area monitoring dosimeters and review exposure reports Semi-Annual Leak test and inventory sealed sources Conduct lloor survey of corridors and reactor bay Calibrate portable radiation monitoring instruments and personnel pocket ion chambers Calibrate reactor stack effiuent monitor, continuous air monitors, remote area radiation monitors, and air samplers Measure face air velocity in laboratory hoods and exchange dust-stop filters and HEPA Annual filters as necessary Inventory and inspect Radiation Center emergency equipment Conduct facility radiation survey of the 60Co irradiators Conduct personnel dosimeter training Update decommissioning logbook Collect and process environmental soil, water, and vegetation samples
- 1*
Table V.2 Monthly Summary of Liquid Effluent Released to the Sanitary Sewer11l Specific Activity for Average Percent of Total Quantity of Applicable Total Each Detectable Concentration Date of Quantity of Detectable Radionuclide in Each Detectable of Released Monthly Average Discharge Radionuclide Concentration for (Month and Radioactivity Radionuclide the Waste where the Released in the Radioactive Released Released in the Waste Release Concentration Material at the Year)
(Curies) was >1 x 10-7 Waste Point of Release Radioactive
( µCi mt*')
(Curies)
( µCi mt*1)
Material
(%)(2) 10/31/2024 3.6 lxJ0*6 Th-232 3.61xl 0*6 7.08x I 0*8 24 05/26/2025 9.67xJ0*5 H-3, Th-232 2.60x I 0*6 H-3 9.50x I o-s H-3, 2.60x I 0*6 H-3, 2.60xJ0*2 H-3, l.84xJ0*6 Th-232 5.0lxJ0*8 Th-232 16.7 Th-232 TOTAL l.00xto*4 H-3, Th-232 2.60x10-(j H-3 9.50xI0*5 H-3, 2.60xl0*6 H-3, 2.60xto*2 H-3, 5.45x10.{j Th-232 1.2txto*7 Th-232 40.7 Th-232 The OSU operational policy is to subtract only detector background from the water analysis data and not background radioactivity in the Corvallis city water.
Based on values listed in IO CFR 20, Appendix B to 20.100 I - I 0.240 I, Table 3, which arc applicable to sewer disposal.
Total Volume of Liquid Effluent Released Including Diluent (gal) 13,465 9,724 23,189
- 0
)>
C -
~
0 z
-0
- 0
~
m
(')
--f -0 z
RADIATION PROTECTION Table V.3 Annual Summary of Liquid Waste Generated and Transferred Volume of Liquid Detectable Total Quantity of Dates of Waste Pickup Origin of Liquid (I) for Transfer to the Radionuclides Radioactivity in the Waste Waste Packaged Waste Processing (gallons) in the Waste Waste (Curies)
Facility TRIGA 40 H-3 I.Ox I 0*6 08/16/2024 Radiation Center 2.3 H-3, C-14, Th-232 3.87xl o-s 08/16/2024, 12/30/2024 Laboratories TOTAL 42.3 See above 3.97xJO*S
( I)
OSTR and Radiation Center liquid waste is picked up by the Radiation Safety Office for transfer to its waste processing facility for final packaging.
Table V.4 Monthly TRIGA Reactor Gaseous Waste Discharges and Analysis Estimated Fraction of the Technical Total Total Atmospheric Diluted Specification Month Estimated Estimated Quantity Concentration of Annual Average Activity of Argon-41 Argon-41 at Point of Argon-41 Released (Curies)
Released<1> (Curies)
Release Concentration Limit(%)
(µCi/cc)
July 1.65 1.65 1.28xl 0*1 3.21 August 1.77 1.77 l.38x10*1 3.45 September 1.39 1.39 1.12xJ 0*1 2.80 October 3.39 3.39 2.64x10*'
6.60 November 3.27 3-27 2.63x10*1 6.57 December 1.84 l.84 I.43x 10*1 3.59 January 2.34 2.34 l.82x10*1 4.55 February 3.25 3.25 2.80x JO*I 7.00 March 3.40 3.40 2.64xI0*1 6.61 April 3.55 3.55 2.85xl 0*'
7.12 May 3.35 3.35 2.6] X JO*I 6.5 I June 2.82 2.82 2.27x10*7 5.66 TOTAL (2023-2024) 32.03 32.03 2.12xl0*1<2>
5.30<2>
(l) Routine gamma spectroscopy analysis of the gaseous radioactivity in the OSTR stack discharge indicated the only detectable radionuclide was argon-41.
(2) Annual average
RADIATION PROTECTION Table V.5 Annual Summary of Solid Waste Generated and Transferred Volume of Detectable Total Quantity Dates of Waste Pickup Origin of Solid Waste Radionuclides of Radioactivity for Transfer to the OSU Solid Waste Packaged<1>
in the Waste in Solid Waste Waste Processing (Cubic Feet)
(Curies)
Facility TRIGA Sc-46, Cr-51, Mn-54, Se-75, Co-58, 08/16/2024, 12/30/2024, Reactor 20 Co-60, Fe-59, Zn-65, Sb-124, Eu-152, 3.087x10-3 Facility Hf-181 04/15/2025 Radiation Co-60, Nat U, DU, U-235, Pu-239, 08/16/2024, 12/30/2024, Center 32 H-3, Eu-152, Eu-154, Am-241, Cs-I 34, 2.4lxl0-5 Laboratories Pu-241, Cf-249, Np-23 7 04/15/2025 TOTAL 52 See above 3.llxt0-3
( I) OSTR and Radiation Center lab waste is picked up by OSU Radiation Safety for transfer to its waste processing facility for final packag-ing.
RADIATION PROTECTION Table V.6 Annual Summary of Personnel Radiation Doses Received Average Annual Greatest Individual Total Person-mrem Dosec*J Dosec*J for the Groupc*J Personnel Group Whole Body Extremities Whole Body Extremities Whole Body Extremities (mrem)
(mrem)
(mrem)
(mrem)
(mrem)
(mrem)
Facility Operating 150 21 1 364 833 1,053 1,689 Personnel Key Facility Research 0
100 0
168 0
604 Personnel Facilities Services Maintenance 0
NIA 0
NIA 0
NIA Personnel Laboratory Class 11 34 144 244 704 1,197 and Students Campus Police and 0
NIA 0
NIA 0
NIA Security Personnel Visitors 1
NIA 4.7 NIA 76.5 NIA (I) "N/ A" indicates that there was no extremity monitoring conducted or required for the group.
I I* * * *
- 1* * * * * * * * *
- 1: * * * * * * * * * * * * * * * * * * * * * * * * *
- RADIATION PROTECTION Table V.7 Total Dose Equivalent Recorded on Area Dosimeters Located within the TRIGA Reactor Facility Total Dose Equivalent<1x2>
Monitor TRIG A Reactor Recorded LD.
Facility Location Xfl(y)
Neutron (See Figure V.1)
(mrem)
(mrem)
MRCTNE Dl04: North Badge East Wall 187 ND MRCTSE D l 04: South Badge East Wall 137 ND MRCTSW D 104: South Badge West Wall 420 ND MRCTNW D l 04: North Badge West Wall 256 ND MRCTWN Dl04: West Badge North Wall 261 ND MRCTEN DI 04: East Badge North Wall 251 ND MRCTES DI 04: East Badge South Wall 2,250 ND MRCTWS DI 04: West Badge South Wall 730 ND MRCTTOP DI 04: Reactor Top Badge 1,207 ND MRCTHXS DI 04A: South Badge HX Room 507 ND MRCTHXW D 104A: West Badge HX Room 334 ND MRCD-302 D302: Reactor Control Room 441 27 MRCD-302A D302A: Reactor Supervisor's Office 162 ND MRCBPl Dl04: Beam Port Number l 189 22 MRCBP2 Dl04: Beam PortNumber2 205 ND MRCBP3 D 104: Beam Port Number 3 1,310 ND MRCBP4 D 104: Beam Port Number 4 1,183 ND (I) The total recorded dose equivalent values do not include natural background contribution and reflect the summation of the results of four quarterly beta-gamma dosimeters or four quarterly fast neutron dosimeters for each location. A total dose equivalent of"ND" indicates that each of the dosimeters during the reporting period was less than the vendor's gamma dose reporting threshold of I 0 mrem or that each of the fast neutron dosimeters was less than the vendor's threshold of I O mrem. "NI 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.
RADIATION PROTECTION Monitor l.D.
MRCAI00 MRCBRF MRCA120 MRCAl20A MRCA126 MRCCO-60 MRCA130 MRCAl32 MRCAl38 MRCBI00 MRCBLI4 MRCB 119-1 MRCBII9-2 MRCBI 19A MRCBl20 MRCBl22-2 MRCB l22-3 MRCBl24-1 MRCBl24-2 MRCBl24-6 MRCB128 MRCB136 MRCCl00 MRCC106A MRCC106B Table V.8 Total Dose Equivalent Recorded on Area Dosimeters Located within the Radiation Center Total Recorded Radiation Center Dose Equivalent<'>
Facility Location X ll(y )
Neutron (See Figure V.l)
(mrem)
(mrem)
A I 00: Receptionist's Office 0
ND Al02H: Front Personnel Dosimetry Storage Rack 0
ND A 120: Stock Room 71 ND A 120A: NAA Temporary Storage 181 ND A 126: Radioisotope Research Laboratory 105 ND A 128: 60Co Irradiator Room 572 ND A 130: Shielded Exposure Room 0
ND A 132: TLD Equipment Room 11 ND A 138: Health Physics Laboratory 0
ND BI 00: Gamma Analyzer Room (Storage Cave) 585 ND B 114: Lab (226Ra Storage Facility) 0 ND Bl 19: Source Storage Room 131 ND B 119: Source Storage Room 371 ND Bl 19A: Sealed Source Storage Room 14,509 3,027 B 120: Instrument Calibration Facility 0
ND B 122: Radioisotope Hood 0
ND B 122: Radioisotope Research Laboratory 0
ND B124: Radioisotope Research Laboratory (Hood) 0 ND BI 24: Radioisotope Research Laboratory 0
ND B 124: Radioisotope Research Laboratory 0
ND B 128: Instrument Repair Shop 0
ND B 136: Gamma Analyzer Room 0
ND Cl 00: Radiation Center Director's Office 0
ND Cl06A: Office 0
ND Cl06B: Custodian Supply Storage 0
ND
( 1) The total recorded dose equivalent values do not include natural background contribution and, reflect the summation of the results of four quarterly beta-gamma dosimeters or four quarterly fast neutron dosimeters for each location. A total dose equivalent of"ND" indicates that each of the dosimeters during the reporting period was less than the vendor's gamma dose reporting threshold of IO mrem or that each of the fast neutron dosimeters was less than the vendor's threshold of IO mrem.
"NIA" indicates that there was no neutron monitor at that location.
I* * * * * * * * * * * * * * * * * * * * *
- RADIATION PROTECTION Monitor I.D.
MRCCI06-H MRCCJ18 MRCC120 MRCFI00 MRCFI02 MRCB125N MRCNl25S MRCCl24 MRCC130 MRCDl00 MRCD102 MRCDI02-H MRCDI06-H MRCD200 MRCD202 MRCBRR MRCD204 MRCATHRL MRCD300 MRCAl44 B132X B132 8 104 Table V.8 (continued)
Total Dose Equivalent Recorded on Area Dosimeters Located within the Radiation Center Total Recorded Radiation Center Dose Equivalent<1, Facility Location (See Figure V.1)
Xll(y)
Neutron (mrem)
(mrem)
Cl 06H: East Loading Dock 0
ND C 118: Radiochemistry Laboratory 0
ND Cl 20: Student Counting Laboratory 0
ND FI 00: APEX Facility 0
ND F I02: APEX Control Room 0
ND Bl 25: Gamma Analyzer Room (Storage Cave) 0 ND B 125: Gamma Analyzer Room 0
ND C124: Classroom 0
ND C 130: Radioisotope Laboratory (Hood) 0 ND DI 00: Reactor Support Laboratory 0
ND DI 02: Pneumatic Transfer Terminal Laboratory 291 ND D 102H: 1st Floor Corridor at D 102 57 ND DI 06H: I st Floor Corridor at D 106 483 ND D200: Reactor Administrator's Office 98 ND D202: Senior Health Physicist's Office 193 ND D200H: Rear Persom1el Dosimetry Storage Rack 0
ND D204: Health Physicist Office 281 ND F I04:ATHRL 0
ND D300: 3rd Floor Conference Room 168 33 Al 44: Radioisotope Research Laboratory 0
ND BI 32X: X-ray Diffraction 0
ND B 132: Radioisotope Research Laboratory (Hood) 0 ND Bl04: SEM/FIB Laboratory 0
ND
( I ) The total recorded dose equivalent values do not include natural background contribution and, reflect the summation of the results of four quarterly beta-gamma dosimeters or four quarterly fast neutron dosimeters for each location. A total dose equivalent ofND" indicates that each of the dosimeters during the reporting period was less than the vendor's gamma dose reporting threshold of IO mrem or that each of the fast neutron dosimeters was less than the vendor's threshold of IO mrem.
"N/A" indicates that there was no neutron monitor at that location.
RADIATION PROTECTION Table V.9 Annual Summary of Radiation and Contamination Levels Observed within the Reactor Facility and Radiation Center during Routine Radiation Surveys Accessible Location (See Figure V.1)
TRIGA Reactor Facility:
Reactor Top (D 104)
Reactor 2nd Deck Area (DI 04)
Reactor Bay SW (D104)
Reactor Bay NW (D104)
Reactor Bay NE (D104)
Reactor Bay SE (D104)
Class Experiments (D l 04, D302)
Demineralizer Tank & Make Up Water System (D104A)
Particulate Filter--Outside Shielding (D 104A)
Radiation Center:
NAACounting Rooms (Al46, 8100)
Health Physics Laboratory (A138) 60Co Irradiator Room and Calibration Rooms (A 128, B 120, Al 30)
Radiation Research Labs (A126, A136, B108, Bl 14, B122, B124, CI26, C130, C132A)
Radioactive Source Storage (B 119, B 119A, A 120A, A132A)
Student Chemistry Laboratory (Cl 18)
Student Counting Laboratory (Cl20)
Operations Counting Room (B 125, B 136)
Pneumatic Transfer Laboratory (D 102)
RX Support Room (Dl00)
Whole Body Radiation Levels (mrem/hr)
Average I Maximum 3.86 110 6.97 60
<1 16
<l 46
< I 74
< I 3.7
< l
<I
< I 8
< I 1.2
< l
<l
<l
< l
<l 3.8
< l I
1.05 29
<]
<l
<1
<1
<]
< I
<1 80
< l
<l Contamination Levels<*l (dpm/cm2)
Average l Maximum
<500
<500
<500
<500
<500
<500
<500
<500
<500
<500
<500
<500
<500
<500
<500
<500
<500
<500
<500
<500
<500
<500
<500
<500
<500
<500
<500
<500
<500
<500
<500
<500
<500
<500
<500
<500
<500
<500
( 1) <500 dpm/ 100 cm2 = Less than the lower limit of detection for the portable survey instrument used.
- :e RADIATION PROTECTION I* * * * * * * * * * * * * * * * * * *
- I* * * * * *
- Table V.10 Total Dose Equivalent at the TRIGA Reactor Facility Fence Fence Total Recorded Dose Equivalent Environmental Monitoring Station (including background)
Based on Mirion TLDs<1-2>
(see Figure V.l)
(mrem)
MRCFE-1 86 +/- 01 MRCFE-2 81 +/- 03 MRCFE-3 81 +/- 02 MRCFE-4 88 +/- 02 MRCFE-5 84 +/- 02 MRCFE-6 90 +/- 01 MRCFE-7 85 +/- 02 MRCFE-8 84+/- 02 MRCFE-9 85 +/- 02 (I) Average Corvallis area natural background using Mirion TLDs totals 80 +/- 5 mrem for the same period.
(2) +/- values represent the standard deviation of the total value at the 95% confidence level.
-7
RADIATION PROTECTION Table V.11 Total Dose Equivalent at the Off-Site Gamma Radiation Monitoring Stations Off-Site Radiation Total Recorded Dose Equivalent Monitoring Station (including background)
Based on Mirion TLDs<1.2>
(See Figure V.1)
(mrem)
MRCTE-2 83 +/- 02 MRCTE-3 83 +/- 02 MRCTE-4 81 +/- 02 MRCTE-5 95 +/- 03 MRCTE-6 83 +/- 02 MRCTE-7 84 +/- 05 MRCTE-8 98 +/- 02 MRCTE-9 87 +/- 03 MRCTE-10 76 +/- 02 MRCTE-12 93 +/- 04 MRCTE-13 87 +/- 03 MRCTE-14 81 +/- 02 MRCTE-15 76 +/- 03 MRCTE-16 86 +/- 08 MRCTE-17 79 +/- 01 MRCTE-18 82 +/- 03 MRCTE-19 77 +/- 02 MRCTE-20 79 +/- 03 MRCTE-21 71 +/- 02 MRCTE-22 77 +/- 02 (I ) Average Corvallis area natural background using Mirion TLDs totals 80 +/- 5 mrem for the same period.
(2) +/- values represent the standard deviation of the total value at the 95% confidence level.
RADIATION PROTECTION Sample Location (See Fig. V.1) 1-W 4-W 11-W 19-RW 3-S 5-S 20-S 21-S 2-G 6-G 7-G 8-G 9-G 10-G 12-G 13-G 14-G 15-G 16-G 17-G 18-G 22-G TableV.12 Annual Average Concentration of the Total Net Beta Radioactivity (minus 3H) for Environmental Soil, Water, and Vegetation Samples Sample Annual Average Concentration Reporting of the Tota] Net Beta (Minus 3H)
LLD Type Radioactivity<*>
Units Water
<LLD 5.70x l -
8
µCi m1-I Water
<LLD 5.70x l0-8
µCi m1-l Water
<LLD 5.70x10-8
µCi m1-l Water
<LLD 5.70xl0-8
µCi m1-l Soil 3.46xl0-5+/- l.07x l0.5 2.3lxl0-5
~tCi g-1 of dry soil Soil
<LLD 2.53xl0.
5
µCi g-1 of dry soil Soil
<LLD 1.74x 10*
5
µCi g-1 of dry soil Soil
<LLD
- 2. l 9x I 0-5
~LCi g-I of dry soil Grass
<LLD 3.44x!0-5
µCi g-I of dry ash Grass
<LLD 3.12x 10-5
µCi g-I of dry ash Grass 1.98x 10-4 +/- 2.85x 10-5 5.30xJ0*5
µCi g-1 of dry ash Grass 1.2 ) X 10 4 +/- 2.80X 10-5 5.76x J0-5
~tCi g-1 of dry ash Grass 3.32xl0-5 +/- l.45xl0-5 3.23x 10-5
µCi g-I of dry ash Grass 1.1 lxi0 4 +/- 2.0 lxl0-5 3.96xI0*5
µC i g-I of dry ash Grass 2.24x l0 4 +/- 2.7lxl0-5 4.82x10*5
µCi g-I of dry ash Grass 2.29xl0 4 +/- 2.98xl0*
5 5.4lxJ0-5
µCi g-1 of dry ash Grass I.06x l0 4 +/- 2.32x l-5
- 4. 73x 10-5
µCi g-l of dry ash Grass l.43x 10 4 +/- 2.82x 10*
5 5.64xJ0-5
~tCi g-I of dry ash Grass 9.69x 10-5 +/- 1.94x l 0-5 3.90x I 0-5
~tCi g-1 of dry ash Grass 2.45xIO-'+/- 2.85x!0-5 5.00xl0*5
µCi g-l of dry ash Grass l.14xl0 4 +/- l.99xl0-5 3.90xt0-5
µCi g-l of dry ash Grass l.30xl0 4 +/- 2.30xl-5 4.49xI0-5
µCi g-l of dry ash (1) +/- values represent the standard deviation of the value at the 95% confidence level.
RADIATION PROTECTION Table V.13 Annual Summary of Radioactive Material Shipments Originating from the TRIGA Reactor Facility's NRC License R-106 Number of Shipments Shipped To Total Activity Exempt Limited Yellow Yellow (TBq)
Quantity II Ill Arizona State University 2.39x 10-<i I
1 I
0 Tucson AZ USA Auburn University 5.98x J0*6 0
l I
0 Auburn. AL USA Berkeley Geochronology Center 7.47xl0*8 3
0 0
0 Berkeley, CA USA C.O.R.D. University of Wisconsin-Madison l.26x 10*7 0
l 0
0 Madison WI USA Columbia University 3.06x 10*6 2
0 0
Palisades NY USA
.)
Idaho National Laboratory l.82x I 0*2 0
0 5
2 Idaho Falls ID USA Indiana University 3.42xl 0*8 2
0 0
0 Bloominirton IN USA Lawrence Livem1ore National Lab 4.00xI0*3 0
0 l
0 Livermore. CA USA Lehigh University 5.7 lx 10*1 0
2 0
0 Bethlehem. PA USA ManTech 9.5lxl0*8 2
0 0
0 Sunol CA USA Materion Corporation 2.08xl0*2 0
0 0
Elmore OH USA
.)
Materion Natural Resources l.29xl0*1 0
0 0
24 Delta UT USA New Mexico Geochronology Research Lab I. I 2x I Q*5 I
I 4
0 Socorro NM USA Oregon State University 7.87x J0*7 2
2 0
0 Corvallis OR USA Pacific No11hwest National Lab 4.88x I 0*3 9
0 0
0 Richland. WA USA Rutgers University l.20x!0*8 I
0 0
0 Piscataway NJ USA Stanford University 9.72x I 0*8 l
0 0
0 Stanford CA USA University of Alaska 2.27xt0*6 I
2 0
0 Fairbanks AK USA University of Arizona 4.74xl0*7 4
0 0
0 Tucson AZ USA University of Florida 2.58xl0-<i 0
0 2
0 Gainesville FL USA University of Nevada, Las Vegas 3.59xJQ*7 0
2 0
0 Las Vegas NV USA University of Wisconsin-Madison 2.83xl Q-<i 0
0 I
0 Madison WI USA USGS CA l.07xJO-<>
2 2
0 0
Menlo Park CA USA USGS CO l.45xl0-<>
2 I
0 0
Denver CO USA TOTAL 1.76x10*1 33 18 15 29 Total 3
2 3
I 5
7 2
I 2
2 3
24 6
4 9
I I
3 4
2 2
I 4
3 95
1 :e RADIATION PROTECTION 1: * * * * * * * * * * * * * * *
- 1: * * * * * * * * * * * * * * *
- Table V.14 Annual Summary of Radioactive Material Shipments Originating from the Radiation Center's State of Oregon License ORE 90005 Total Activity Number of Shipments Shipped To Limited (TBq)
Exempt Quantity White I Yellow II TOTAL 0
0 0
0 0
Table V.15 Annual Summary of Radioactive Material Shipments Exported under NRC General License 10 CFR 110.23 Number of Shipments Shipped To Total Activity Exempt Limited Yellow (TBq)
Quantity lI Albert-Ludwigs-Universitaet I.03x 10*8 I
0 0
Freiburg, GERMANY China Earthquake Administration l.87x!0*8 I
0 0
Beijing, CHINA Curtin University ofTeehnology l.47xI 0*5 0
I I
Bentley, Western Australia, AUSTRALIA Dalhousie University l.64xJ0*8 I
0 0
Halifax, Nova Scotia, CANADA Geological Survey of Japan I.22x 10*8 I
0 0
lbaraki, JAPAN Institute of Tibetan Plateau Research 3.16x 10*7 I
0 0
Beijing, CHINA ISTO 2.78x I0*8 I
0 0
Orleans, FRANCE Korean Basic Science Institute l.00xl 0*1 3
0 0
Cheongju-si, Chungcheongbuk-do, KOREA Lanzhou University 2.07x J0*7 2
0 0
Lanzhou, Gansu, CHINA Total 0
Total I
I 2
I I
I I
3 2
RADIATION PROTECTION Table V.15 (continued )
Annual Summary of Radioactive Material Shipments Exported under NRC General License 10 CFR 110.23 Number of Shipments Shipped To Total Activity Exempt Limited Yellow (TBq)
Quantity II LSCE-CNRS 2.95x 10*1 Gif-Sur-Yvette, FRANCE 2
0 0
Northwest University l.97x I 0*8 XiAn, CHINA I
0 0
Polish Academy of Sciences 2.05x 10*8 Krakow, POLAND I
0 0
QUAD-Lab, Natural I listory Museum of Denmark 2.3lx l0*7 Copenhagen, DENMARK I
0 0
Scottish Universities Research & Reactor Centre 3.76x 10*6 East Kilbride, SCOTLAND 3
2 0
Universidade de Sao Paulo Sao Paulo, BRAZIL 8.79xJ0*8 2
0 0
Univcrsitat Potsdam I.05x 10*7 Potsdam, GERMANY 2
0 0
University of Grenoble Alps 7.44xl0*10 Grenoble, FRANCE I
0 0
University of Geneva 8.13xJ0*8 Geneva, SWITZERLAND 2
0 0
University of hmsbruck 8.40x I 0*10 Innsbruck, AUSTRIA 2
0 0
University of Manitoba 4.52x I 0-6 Winnipeg, CANADA I
.)
0 University of Melbourne 2.22xJ0-6 Parkville, Victoria, AUSTRALIA 0
4 0
University of Padova 3.l3xl0*9 Padova, ITALY I
0 0
University of Salzburg l.23x I 0*9 Salzburg, AUSTRALIA I
0 0
Vrije Universiteit 4.52x I 0*8 Amsterdam, THE NETHERLANDS I
0 0
Wadi a Institute of Himalayan Geology 9.25x 10*9 Dehradun, Uttarakhand, INDIA I
0 0
Zhejiang University l.36x I 0*8 Hangzhou, CIIINA I
0 0
TOTAL 2.68xl0*5 34 10 I
Total 2
I I
I 5
2 2
I 2
2 4
4 I
I I
I I
45
- =* RADIATION PROTECTION 1* * * * * *
- 1: * * * * * * *
- Figure V.1 Monitoring Stations for the OSU TRIGA Reactor CllDiD{
aR-1 CNt'U$U11UTY n
CAIOCA TU>n.u10N Tl c:uDC4 TU>STA.TIOK G
QI.SS S
IIOIL W WA.'ID.
aw tA.J!CWA.ff:ll Nan: TIUISLOCUmS NIUSi:ovtll o,nDt~CIMD.IJ
'UISoaa\'A.tUSAmOl:r
Summary The Radiation Center offers a wide variety of resources for teaching, research, and service related to radiation and radioactive materials. Some of these are discussed in detail in other parts of this report. The purpose of this section is to summarize the teaching, research, and service efforts carried out during the current reporting period.
Teaching An important responsibility ofthe Radiation Center and the reactor is to support OSU's academic programs.
lmplementation of this support occurs through direct involvement of the Center's staff and facilities in the teaching programs of various departlnents and through participation in University research programs. Table TTJ.2 plus the "Training and Instruction" section (see next page) provide detailed infonnation on the use of the Radiation Center and reactor for instruction and training.
Research and Service Almost all Radiation Center research and service work is tracked by means of a project database. When a request for facility use is received, a project number is assigned and the project is added to the database. The database includes such information as the project number, data about the person and institution requesting the work, infom1ation 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 fllllding source.
Table VJ. I provides a summary of institutions which used the Radiation Center during this reporting period. This table also includes additional information about the number of academic personnel involved, the number of projects, and the number of uses logged for each organization.
The major table in this section is Table VI.2. This table provides a listing of the research and service projects carried out during this reporting period and lists infom1atio11 relating to the personnel and institution involved, the type of project, and the funding agency. Projects which used the reactor are indicated by an asterisk. In addition to identifying specific pr~jects carried out during the current reporting period, Part VT also highlights major Radiation Center capabilities in research and service. These unique Center functions are described in the following text.
Neutron Activlltion Anlllysis Neutrnn activation analysis (NAA) stands at U1e forefront of techniques for the quantitative multi-element analysis of major, minor, trace, and rare elements. The principle involved in NAA consists of first irradiating a sample with neutrons in a nuclear reactor such as the 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 energy arc usually indicative of a specific radionuclide's presence. Computerized data reduction of the gamma ray spectra then yields the concentrations of the various elements in samples being studied. With sequential instrumental NAA, it is possible to measure quantitatively about 35 elements in small samples (5 to I 00 mg), and for activable elements, the lower limit of detection is on the order of parts per million or parts per billion depending on the element.
The Radiation Center's NAA laboratory has analyzed the major, minor, and trace element content of tens of thousands of samples covering essentially the complete spectrw11 of material types and involving virtually every scientific and technical field.
While some researchers perfom1 their own sample counting on their own or on Radiation Center equipment, the Radiation Center provides a complete NAA service for researchers and others who may require it. This includes sample preparation, sequential irradiation and counting, and data reduction and analysis.
lrradilltio11s As described throughout this report, a major capability of the Radiation Center involves the in-adiation of a large variety of substances with gamma rays and neutrons. Detailed data on these irradiations and their use are included in Part III as well as in the "Research & Service" text of this section.
Rlldiologiclll Emergency Response Services The Radiation Center bas an emergency response team capable of responding to all types of radiological accidents. This team directly
=
- WORK 1: * * * * * * * * * * * * * * * * * * * * * * * * *
- supports the City of Corvallis and Benton County emergency response organizations and medical facilities. The team can also provide assistance at the scene of any radiological incident anywhere in the state of Oregon on bebal f of the Oregon Radiation Protection Services and the Oregon Department of Energy.
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 in Corvallis.
DuriJ1g the ctment reporting period, the Radiation Center emergency response team conducted several training sessions and exercises, but was not required to respond to any actual incidents.
Training am/ Instruction In addition to the academic laboratory classes and courses discussed in Parts 1ll and VJ, and in addition to the routine training needed to meet the requirements of the OSTR Emergency Response Plan, Physical Security Plan, and operator requalification program, the Radiation Center is also used for special training programs. Radiation Center staff are well experienced in conducting these special programs and regularly offer training in areas such as research reactor operations, research reactor management, research reactor radiation protection, radiological emergency response, reactor behavior ( for nuclear power plant operators), neutron activation analysis, nuclear chemistry, and nuclear safety analysis.
Special training programs generally fall into one of several categories: visiting faculty and research scientists; international Atomic Energy Agency fellows; special short-term courses; or individual reactor operator or health physics training programs. During this reporting period, there were a large nwnber of such people as shown in the People section.
As has been the practice since 1985, Radiation Center personnel annually present a HAZMAT Response Team Radiological Course. This year a course was held at Oregon State University, and also, another course was held in La Grande, Oregon on the hazards and shipping regulations of UF6 and TRU packages.
Radiation Protection Services The primary purpose of the radiation protection program at the Radiation Center is to support the instruction and research conducted at the Center. However, due to the high quality of the program and the level of expertise and equipment available, the Radiation Center is also able to provide health physics services in support ofOSU Radiation Safety and to assist other state and federal agencies. The Radiation Center does not compete with private industry, but it supplies health physics services which are not readily available elsewhere. ln the case of support provided to state agencies, this definitely helps to optimize the utilization of state resources.
The Radiation Center is capable of providing health physics services in any of the areas which are discussed in Part V.
These include personnel monitoring, radiation swveys, sealed source leak testing, packaging and shipment of radioactive materials, calibration and repair of radiation monitoring instruments (discussed in detail in Part VI),
radioactive waste disposal, radioactive material hood flow surveys, and radiation safety analysis and audits.
The Radiation Center also provides services and technical support as a radiation laboratory to the State of Oregon Radiation Protection Services (RPS) in the event of a radiological emergency within the state of Oregon. In this role, the Radiation Center will provide gamma ray spectrometric analysis of water, soil, milk, food products, vegetation, and air samples collected by RPS radiological response field teams. As part of the ongoing preparation for this emergency support, the Radiation Center participates in inter-.institution drills.
Radiological Instrument Repair and Calibration While repair of nuclear instrumentation is a practical necessity, routine calibration of these instruments is a licensing and regulatory requirement which must be met. As a result, the Radiation Center operates a radiation instrument repair and calibration facility which can accommodate a wide variety of equipment.
The Center's scientific instrument repair facility performs maintenance and repair on all types of radiation detectors and other nuclear instrumentation. Since the Radiation Center's own programs regularly utilize a wide range of nuclear instruments, components for most common repairs are often on hand and repair time is therefore minimized.
In addition to the instrument repafr capability, t11e Radiation Center has a facility for calibrating essentially all types of radiation monitoring instruments. Tbis includes typical portable monitoring instrumentation for the detection and measurement of alpha, beta, gamma, and neutron radiation,
WORK as well as instruments designed for low-level environmental monitoring. Higher range instruments for use in radiation accident situations can also be calibrated in most cases.
Instrument calibrations are performed using radiation sources certified by the National Institute of Standards and Technology (NIST) or traceable to NIST Figure VI.I is a summary of the instruments which were calibrated in support of the Radiation Center's instructional and research programs and the OSTR Emergency Plan. Table YI.3 shows instruments calibrated for other OSU depart-ments while Table VT.4 shows instruments calibrated for non-OSU agencies.
Consultation Radiation Center staff are available to provide consultation services in any of the areas discussed in this Annual Report, but in particular, on the subjects of research reactor operations and use, radiation protection, neutron activation analysis, radiation shielding, radiological emergency response, and radiotracer methods.
Records are not normally kept of such consultations, as they often take the form of telephone conversations with researchers encountering problems or planning the design of experiments.
Many faculty members housed in the Radiation Center have ongoing professional consulting functions with various organizations in addition to sitting on numerous committees in advisory capacities.
Table Vl.1 Institutions, Agencies, and Groups which Utilized the Radiation Center Institutions, Agencies, and Groups
- Albert-Ludwigs-Universitaet Freiburg, GERMANY
- Atomos Space Broomfield, CO USA
- Berkeley Geochronology Center Berkeley, CA USA BWX Technologies Lynchburg, VA USA COM Smith Edison, NJ USA CleanMark Labels Portland, OR USA
- Columbia University Palisades, NY USA
- Environmental and Molecular Toxicology Corvallis, OR USA Florida State University Tallahassee, FL USA Number Number of Number of Times of of Uses Projects Faculty Involvement of Center Facilities 0
0 5
3 2
0 4
0 3
0 0
32 0
5 2
2 3
0 6
=
- WORK 1e * * * * * *
- 1* * * * * * * * * * * * * *
- Table Vl.1 (continued)
Institutions, Agencies, and Groups which Utilized the Radiation Center Institutions, Agencies, and Groups Number of Number of Times of Projects Faculty Involvement Gemoftheamericas.com I
- Geological Survey of Japan/AIST l
0 Tsukuba, Ibaraki, JAPAN
- Georgia Institute of Technology I
0 Atlanta, GA USA Hemingway Designs, LLC 1
- Idaho National Laboratory 2
- Indiana University 1
0 Bloomington, IN USA
- Institute of Geology, China Earthquake Administration I
0 Beijing, CHINA
- INSU-CNRS - Universite d'Orleans 1
I Orleans, FRANCE
- Korea Basic Science Institute I
l Cheongwon-gun, Chungcheongbuk-do, SOUTH KOREA
- Lanzhou Center of Oil and Gas Resources, CAS Lanzhou, CHINA 1
l
- Lanzhou University 1
0 Lanzhou City, Gansu Province CHINA
- Lanzhou University Lanzhou, CHINA I
0
- Lawrence Livermore National Laboratory I
0 Livermore, CA USA
- Lehigh University l
- LSCE-CNRS I
0 Gif-Sur-Yvette Ccdex, FRANCE
- ManTech - Vallecitos Laboratories - AEM 1
0 Sunol, CA USA
- Materion Brush Jnc.
I 0
Elmore, OH USA
- Materion Natural Resources I
- New Mexico Institute of Mining & Technology I
0 Socorro, NM USA
- Northwest University I
0 Xi' An, CHINA Number of Uses of Center Facilities I
1 27 I
6 2
2 1
3 I
I I
2 2
2 2
4 12 7
I
WORK Table Vl.1 (continued)
Institutions, Agencies, and Groups which Utilized the Radiation Center Institutions, Agencies, and Groups Number of Number of Times of Projects Faculty Involvement Oregon Health Sciences University I
- Oregon State University<1>
- Oregon State University - Educational Tours I
- Oregon State University Radiation Center I
- Pacific Northwest National Laboratory I
0 Richland, WA USA Phylos Bioscience 1
- Polish Academy of Sciences 1
0 Krakow, POLAND
- Quaternary Dating Laboratory I
0 K.0benhavn K, DENMARK Radiation Protection Services I
0 Portland, OR USA Rocket Lab 0
Albuquerque, NM USA I
- Rutgers University I
0 Piscataway, NJ USA
- Scottish Universities Environmental Research Centre I
0 East Kilbride, UK Self - Individual l
- Stanford University l
l Stanford, CA USA Terra Nova Nurseries, Inc.
I 0
- U.S. Geological Survey 2
0 Denver, CO USA
- U.S. Geological Survey 2
0 Menlo Park, CA USA
- U.S. Geological Survey 2
0 Moffett Field, CA USA
- Universita' Degli Studi di Padova I
2 Padova, ITALY
- Universitat Potsdam l
0 Potsdam, GERMANY Number of Uses of Center Facilities 2
67(2) 11 18 9
I I
2 8
1 I
6 l
l 4
8 8
8 1
I
I. * * * *
- 1* * * * * * * * * * * * * * * * * * * * *
- WORK Table Vl.1 (continued)
Institutions, Agencies, and Groups which Utilized the Radiation Center Number of Number of Times of Institutions, Agencies, and Groups Projects Faculty Involvement
- Universite Grenoble Alpes I
I Grenoble, Isere FRANCE University of Alaska Anchorage I
I Anchorage, AK USA
- University of Alaska Fairbanks I
0 Fairbanks, AK USA
- University o f Arizona 2
3 Tucson, AZ USA
- University o f Florida I
l Gainesville, FL USA
- University of Geneva I
I Geneva, SWITZERLAND University of Illinois Urbana-Champaign l
I Urbana, IL USA
- University oflnnsbruck I
I Innsbruck, AUSTRIA
- University of Manitoba I
I Winnipeg, Manitoba CANADA
- University of Melbourne l
l Melbourne, Victoria AUSTRALIA
- University of Michigan I
I Ann Arbor, MI USA
- University ofNevada, Las Vegas 2
- University of Potsdam I
0 Potsdam, GERMANY
- University of Rome I
I Rome, ITALY
- University of Salzburg I
I Salzburg, AUSTRIA
- University of Sao Paulo I
0 Sao Paulo, BRAZIL University of Texas at Austin 1
- University of Wisconsin I
I Madison, WI USA US National Parks Service I
0 Crater Lake, OR USA VivoTex I
- Vrije Universiteit l
1 Amsterdam, TIIE NETIIERLANDS l
Number of Uses of Center Facilities I
4 3
5 2
l 2
4 4
12 3
I 10 I
I 6
2 3
I I
WORK Table Vl.1 (continued)
Institutions, Agencies, and Groups which Utilized the Radiation Center Institutions, Agencies, and Groups Number of Number of Times of Projects Faculty Involvement
- Washington State University 2
I Pullman, WA USA
- Western Australian Argon Isotope Facility I
0 Perth, Western Australia, AUSTRALIA Western States Physics I
0 Stevenson, WA USA
- Zhejiang University I
0 I langzhou, Cl JINA Totals 94 89 Project which involves the OSTR.
Number of Uses of Center*
Facilities 4
6 I
I 386 (I)
(2)
Use by Oregon Stale University docs not include any teaching activities or classes accommodated by the Radiation Center.
This number does not include ongoing projects being performed by residents of the Radiation Center such as the APEX project, others in the School of uclear Science and Engineering, Radiation Health Physics program, Department of Chemistry, or projects conducted by Dr. Walt Loveland which involve daily use of the Radiation Center facilities.
Project Users 444 Koppers 815 Presley 920 Becker 932 Dumitru 1074 Kuiper 1191 Vasconcelos 1465 Singer Teaching and 1504 Tours 1514 Sobel 1523 Zattin 1555 Fitzgerald Table Vl.2 Listing of Major Research and Service Projects Performed or in Progress at the Radiation Center and their Funding Agencies Organization Name Project Title Description Oregon State Production of Ar-39 from K-39 to measure Ar/ Ar Dating of Oceanographic Samples radiometric ages on basaltic rocks from ocean University basins.
Oregon State Sterilization of Wood Samples Sterilization or wood samples to 2.5 Mrads in Co-University 60 irradiator for fungal evaluations.
Berkeley Production of Ar-39 from K-39 to determine ages Ar/Ar Age Dating Geochronology Center in various anthropologic and geologic materials.
Fission track dating or the mineral apatite extracted from rock samples. This is a well-established method for constraining the time-temperature histories experienced by rocks over geologic time, to evaluate the geologic history Stanford University Fission Tracking Dating of parts of the Earth, and the geologic processes involved. Thermal neutron irradiations are used to measure the concentration ortrace natural uranium present in apatite (typically I to 200 parts per million), a parameter necessary for age (time) calculations.
Vrije Universiteit Ar/Ar Dating of Rocks and Minerals Ar/Ar dating of rocks and minerals.
University of Production or Ar-39 from K-39 to detem1ine ages Ar/Ar Age Dating Queensland in various anthropologic and geologic materials.
University of Ar/Ar Dating of Lavas Irradiation of geological materials such as volcanic Wisconsin rocks from sea floor, etc. for Ar-40/Ar-39 dating.
Oregon State Covers irradiations necessary to support University -
Academic Tours Educational Tours academics, classes, student research, and tours.
Univcrsitat Potsdam Apatite Fission Track Analysis Age detennination of apatites by fission track analysis.
Universita degli Studi Fission Track Analysis of Apatites Fission track analysis of apatites.
diPadova Irradiation to induce U-235 fission for fission track thermal history dating, especially for hydrocarbon Syracuse University Fission Track Them1ochronology exploration. The main thrust is towards tectonics, in particular the uplifl and fonnation of mountain ranges.
Funding OSU Oceanography Department OSU Forest Products Berkeley Geochronology Center Stanford University Geology Department Vrije Universiteit, Amsterdam Earth Sciences, University of Queensland University or Wisconsin NIA Universitat Potsdam NIA Syracuse University
- E 0
- 0 A
Table Vl.2 (continued)
Listing of Major Research and Service Projects Performed or in Progress
~
at the Radiation Center and their Funding Agencies
- o A
Project Users Organization Name Project Title Description Funding University of Nevada, Irradiation of rocks and minerals for Ar/Ar dating Univerity of Nevada, 1568 Zanetti Las Vegas Ar/Ar Dating of Rocks and Minerals to determine eruption ages, emplacement histories, Las Vegas and provenance studies.
Albcrt-Ludwigs-Fission Track Dating of the Mid-Dating of the shoulder uplift along the Mid-German Science 1595 Rahn Universitaet European Rhine Graben Shoulder European Rhine graben shoulders by the fission Foundation track technique.
1617 Spikings University of Geneva Ar/Ar Geochronology and Fission Track Argon dating of Chilean granites.
University of Dating Geneva 1623 Blythe Occidental College Fission Track Analysis Fission track Thennochronology of geological Occidental College samples.
Reactor Oregon State Operations Support of the Reactor and Operations use of the reactor in support of reactor 1660 University Radiation NIA Operations Staff Center Facilities Testing and facilities testing.
1745 Girdner U.S. National Parks C 14 Measurements LSC analysis of samples for C 14 measurements.
U.S. National Parks Service Service 1767 Korlipara Terra Nova Nurseries, Genera Modifications Using Gamma Use of gamma and fast neutron irradiations for Terra Nova Inc.
Irradiation genetic studies in genera.
I Nurseries, Inc.
1768 B ri11 gn,a n Materion Brush Inc.
Antimony Source Production Production of Sb-124 sources.
Materion Brush Inc.
1777 Storey Quaternary Dating Quaternary Dating Production of Ar-39 from K-39 to determine Quaternary Dating Laboratory radiometric ages of geological materials.
Laboratory This project subjects chitosan polymer in 40 and 70% DD/\ fomrnlations to 9 and 18 Kgy, boundary 1778 Chucn How Genis, Inc.
Gamma Exposure of Chitosan Polymer doses for commercial sterilization for the purpose Genis, Inc.
of detem1ining changes in the molecular weight and product formulation properties.
1785 Mine Oregon State Univesity l AA of Maya Ceramics Trace-element analysis of ancient Maya ceramics from Pull trouser Swamp, Belize.
1818 Smith Materion Natural Antimony Source Production (Utah)
Source production for use in mining assaying.
Materion Natural Resources Resources Fission track them1ochronometry of the 1831 Thomson University of Arizona Fission Track Patagonian Andes and the Northern Apennines, Yale University Italy.
1847 Higley Oregon State Ultra-Trace Uptake Studies for NAA of ultra-trace clements in plant samples for NERHPCRESP University Allometric Studies application in allometric studies.
Grant 1855 Anczkiewicz Polish Academy of Fission Track Services Verification of AFT data for illite-mechte data.
Polish Academy of Sciences Sciences 1860 Mine Oregon State INAA of Archaeological Ceramics Trace-element analysis of archaeological ceramics. NIA University
- 1*
Table Vl.2 (continued)
~
Listing of Major Research and Service Projects Performed or in Progress o
at the Radiation Center and their Funding Agencies
~
Project Users Organization Name Project Title Description Funding University of Production of Ar-39 from K-40 to determine University of 1864 Gans California at Santa Ar/ Ar Sample Dating radiometric ages of geologic samples.
California at Santa Barbara Barbara Apatite fission track to reveal the exhumation 1865 Carrapa University of Arizona Fission Track Irradiations history ofrocks from the TD-WY-UY postion University of of the Sevier fold and thrust belt, Nepal, and Arizona Argentina.
1882 Bray Wayne State INAA of Archaeological Ceramics from Trace-element analysis oflnca-period ceramics for Wayne State University South America provenance determination.
University The current project is designed lo identify the Oregon State LD50 rate of gamma irradiation so that large 1884 Contreras University Mutation Breeding of Woody Plants seed lots may be irradiated in order to develop OSU Horticulture novel phenotypes that exhibit reduced fertility or sterility.
1886 Coutand Dalhousie University Fission Track Irradiation Fission track irradiations of apatite samples.
Dalhousie University 1887 Farsoni Oregon State Xenon Gas Production Production of xenon gas.
OSUNERHP University The goal of this project is to determine the effects of hydrolysis and radiolysis on the extraction ability of a diamide and chlorinated cobalt 1889 Paulenova Oregon State Hydrolysis and Radiolysis of Synergistic dicarbollide (CCD). CCD and the diamide are Oregon State University Extractants synergistic extractants and will be together in Univeristy NSE solution for hydrolysis and radiolysis experiments.
Effects will be measured with IR spectroscopy and extraction distribution ratios.
1898 Fayon University of Fission Track Services Use of fission tracks to determine location of University of Minnesota 235U, 232Th in natural rocks and minerals.
Minnesota 1905 Fellin ETH Zurich Fission Track Analysis Use of fission tracks to determine location of Geologisches 235U, 232Th in natural rocks and mi_nerals.
Institut, ETH Zurich Scottish Universities Scottish Universities 1914 Barfod Environmental Ar/Ar Geochronology Ar/Ar age dating.
Research and Research Centre Reactor Centre 1927 Seward Victoria University of Fission Track Dating Fission track dating of apatite samples.
Victoria University Wellin_gton of Wellin2.ton 1939 Wang Lanzhou University Lanzhou University Fission Track Fission track dating.
Lanzhou University 1957 Phillips University of Radiometric Age Dating of Geologic Ar/ Ar age dating.
University of Melbourne Samples Melbourne 1965 Webb University of Vermont Ar/Ar Age Dating Irradiation with fast neutrons to produce Ar-39 University of from K-39 for Ar/Ar geochronolo!!V.
Table Vl.2 (continued)
Listing of Major Research and Service Projects Performed or in Progress
~
at the Radiation Center and their Funding Agencies
- o "
Project Users Organization Name Project Title Description Funding Use of fission tracks to detennine last heating School of 1975 Wildman University of Glasgow Samuel Jaanne Geographical and event of apatites.
Earth Sciences Radiation Protection State of Oregon 1980 Carpenter Services Sample Counting Sample counting.
Radiation Protection Services 1995 Camacho University of Manitoba Ar/Ar Dating Production of Ar-39 from K-39 to detennine University of radiometric ages of geological materials.
Manitoba 2001 Derrick Branch Engineering Densitometer Leak Test Wipe counts for leak test of densitometer sources.
Branch Engineering 2004 Sudo University of Potsdam Ar/Ar Geochronological Studies Ar/Ar dating of natural rocks and minerals for geological studies.
2007 van Soest Arizona State Argon-Argon Geochronology Fast neutron irradiation of mineral and rock Arizona State University samples for 40Ar/39Ar dating purposes.
University 2010 Helena Hollanda University of Sao Ar/Ar Geological Dating Ar/Ar geologic dating of materials.
University of Sao Paulo Paulo 2017 Jourdan Western Australian Age Dating of Geological Material Ar/Ar geochronology.
Curtin Unjversity Argon Isotope Facility 2023 Beaumont Lawrence Livermore Ar/Ar Dating Production of neutron induced 39Ar from 39K for Lawrence Livermore National Laboratory Ar/ Ar dating.
National Laboratory 2028 Mine Oregon State lNAA of Ceramics from the Ancient Provenance determination of ceramics from the OSU Anthropology University Near East Ancient Near East via trace-element analysis.
2029 Kim Korea Basic Science Ar/Ar Geochronology Ar/ Ar analysis for age dating of geological Korea Basic Science Institute samples.
Institute University of Milano-Use of fission tracks fron U-235 to detennine age Universita degli 2031 Malusa Fission Track Dating Studi di Milano-Bicocca ofrocks.
Bicocca 2034 Presley Oregon State Sterilization of Wood Products Sterilization of wood to 2.0 Mrad for fungal OSU Forest Products University experiments.
Lanzhou Center of Oil Lanzhou Center 2035 Wang and Gas Resources, Fission Track Fission track dating of rock samples.
of Oil and Gas CAS Resources, CAS
Project Users 2039 Gombart 2048 Christensen 2060 lshizuka 2061 Weiss 2064 Schaefer 2067 Reese 2069 Scaillct Table Vl.2 (continued)
Listing of Major Research and Service Projects Performed or in Progress at the Radiation Center and their Funding Agencies Organization ame Project Title Description Prevention of Infections Associated with Combat-Related Injuries by Local Sustained Co-Delivery of Vitamin D3 and Other Immune-Boosting Compounds Award Mechanism. We are Oregon State Prevention oflnfcctions Associated preparing nanofiber wound dressings that contain University with Combat-Related Injuries by Local compounds that will be released over time to Sustained Co-Delivery induce the immune response in wounds to help prevent infection and speed wound healing. The nanofibcrs must be irradiated so that they are sterile. These experiments will be perfom1cd in cell culture and in animal models.
Oregon State CNAA ofJV Fluids INAA to detennine trace metals in TPN and University additives.
Geological Survey of Ar/Ar geochronology of volcanic and igneous Ar/ Ar Geochronology rocks associated with subduction initiation of Japan/AIST oceanic island arc.
Oregon State Neutron Radiography Imaging of investigation into the applicability of neutron University Concrete radiography for evaluating concrete curing processes.
We will be perfonning bench scale microcosm CDM Smith Abiotic Dechlorination of Chlorinated studies to measure the abiotic dechlorination in Solvents in Soil Matrices different soil matrices. Gamma irradiation will be used to sterilize the samples.
Oregon State Neutron Radiography of Long-Term Use ofneutron radiography and tomography University Concrete Curing imaging in long-tem1 studies of concrete curing used in civil construction.
INSU-CNRS-Ar/Ar Dating of Geologic Samples Ar/ Ar analysis for age dating of geologic samples Universite d'Orleans (solid rock chips and minerals).
Funding OSU College of Pharmacy Geological Survey of Japan COM Smith Oregon State University CCE INSU-CNRS-Universite d'Orleans
- E 0
- 0 A
Table Vl.2 (continued)
Listing of Major Research and Service Projects Performed or in Progress
~
at the Radiation Center and their Funding Agencies
- o A
Project Users Organization Name Project Title Description Funding The purpose of this experiment is to deten11ine what color a nearly colorless Tourmaline will turn with dosages of 5, JO, and 20 Mr of Gamma irradiation. Two Pakistan Beryl crystals are also part of this experiment to see the color change as well as 2 pieces of Four Peaks Amethyst that may Gamma Irradiation Induced Change of have been faded by sunlight. For the Tourmaline, Colorado Gem and color possibilities are brown, yellow, and pink Colorado Gem and 2070 Lowell Mineral Co.
Color in Tourmaline from a Pegmalite in lo red. The commercial value of colorless gem Mineral Co.
the Oban Massif, igeria Tounnaline is very low, but other colors of gem Tounnaline, especially pink and red results, would stimulate mining of this material in Nigeria. 20 Mr is usually a dosage that will saturate the visible color, and lower dosages may be preferable if the Gamma rays cause a new color other than pink or red which is the desirable result.
2084 Spirkowyc Charlotte Pipe and ABS Antimony Testing Testing for trace antimony in ABS compounds via Charlotte Pipe and Foundry Co.
fNAA according to ASTM E3063.
Foundry Co.
2085 He Lanzhou University Apatite Fission Track Use of fission track analysis lo detennine U Lanzhou University content in the sedimentation ofXining Basin.
2092 Jianqiang Northwest University Fission Track Dating of Qaidam Basin Fission track dating of Qaidam Basin, China to determine its age.
Project is designed lo irradiate liquid donor bovine serum contained in vinyl bags to a minimum level 2097 Boyt Boyt Veterinary Lab Donor Bovine Serum Irradiation of25 kGy to inactivate any adventitious agents Boyt Veterinary Lab that may be present in 0.2 um sterile filtered product.
Institute of Geology, Studying the thermal history of the northeast Tibet China Earthquake 2098 Pang China Earthquake Fission-Track Dating Plateau by the fission-track dating method.
Administration Administration 2101 Yang Zhejiang University Fission-Track Thermochronometry Fission-track analysis for dating geological Zhejiang University materials.
2111 Turrin Rutgers Ar/Ar Geochronology Lunar/solar system chronolo!!V.
NASA 2115 Scao LSCE-CNRS Age Dating of Geologic Materials Ari Ar analysis for age dating of geologic LSCE-CNRS materials.
Project Users 2116 Nyman 2120 Li 2121 Jia 2122 Jia 2135 Pomella 2136 Higley Table Vl.2 (continued)
Listing of Major Research and Service Projects Performed or in Progress at the Radiation Center and their Funding Agencies Organization Name Project Title Description We would like to determine if the oligomerization of uranyl peroxide can be driven by radiation in solution. We will prepare solutions of Determine if the Oligomerization of lithium uranyl triperoxide monomers and apply Department of Uranyl Peroxide can be Driven by different radiation doses (time of radiation) until Chemistry Radiation change is observed by visual inspection and spectroscopic characterization. We estimate three samples, irradiated for one day, and TBD for the other two samples. Irradiation of all will start simultaneously.
Using the in situ TEM ion irradiation facility at Argonne National Laboratory, we already observed He ions (simulating alpha-particles) induced annealing effects on 80 MeV ion tracks Institute of Tibetan (simulating fission tracks) in apatite. For the next Plateau Research, Alpha-Particle Induced Annealing step, we are planning to use chemical etching to Chinese Academy of Effects on Fission Tracks in Apatite further confirm the alpha-annealing effects on Sciences real fission tracks. Neutron-induced fission tracks are essential to the etching experiments because neutron-induced fission tracks, as compared to naturally occurring fission tracks, have no thermal history (or thermal annealing effects).
Beijing Research Fission Track Analysis to Determine U Institute of Uranium Content in South China Fission track dating of areas of South China.
Geology Beijing Research Ar-Ar Analysis for Age Dating of Ar-Ar analysis for age dating of geologic materials Institute of Uranium Geology Geologic Materials (solid rock grains and minerals).
University of Apatite Fission Track Apatite fission track, standards for zeta calibration.
l1msbruck Oregon State INAA of Mining Site Soils Soil analysis by INAA for Uranium/Thorium University concentration assessment.
Funding Department of Chemistry Chinese Academy of Sciences Beijing Research institute of Uranium Geology University of Innsbruck
Pr-oject Users 2138 Hames 2142 Ricci 2144 Hemming 2145 Morgan 2146 Calvert 2149 Vanderstelt 2 150 McAleer 2153 Quinn 2157 Fawcett Table Vl.2 (continued)
Listing of Major Research and Service Projects Performed or in Progress at the Radiation Center and their Funding Agencies Organization Name Project Title Description This project will result in new geological age determinations by the 40Ar/39Ar method for potassiwn-bearing silicate minerals (including 40Ar/39Ar Dating of Mineral Samples hornblende, muscovite, biotite, and orthoclase),
Auburn University from Orogenic Belts and Mineral along with basalt whole rock samples, in Deposits the Auburn Noble Isotope Mass Analysis Laboratory (ANIMAL). This project is for scientific investigation of Earth's history and has aoolications to mining industries.
Fast neutTon irradiation of geological samples New Mexico Irradiation of Samples for 40Ar/39Ar to primarily transmute 39K to 39Ar for the Institute of Mining &
Geochronology for NM Tech purposes of rock and mineral dating. Samples are Technology for academic geological investigations requiring knowledge of age and/or thermal history.
We analyze a variety of geological samples for Columbia University Ar Geochronology for the Earth their 40Ar/39Ar ages, including samples for Sciences (AGES) external collaborators and for internal grant-suooorted research.
U.S. Geological Neutron irradiation requested for 40Ar/39Ar Survey 40 Ar/39Ar Geochronology geochronology. Will use 39K (n,p) 39Ar reaction to determine ages on rocks and minerals.
Menlo Park Geochronology uses 40Ar/39Ar techniques to date materials for geologic hazards, U.S. Geological 40 Ar/39Ar Geochronology mapping, tectonic, and mineral resource projects.
Survey The method requires fast-neutron irradiation of separates from volcanic, plutonic, sedimentary, and metamorphic rocks to convert 39K to 39Ar.
Nray Services, Inc.
Titanium Turbine Blade Radiography Examination of titanium turbine blades via neutron radiography.
Irradiation of potassium-bearing minerals that will U.S. Geological U.S. Geological Survey-Reston Ar/Ar be dated by the Ar/Ar method at the USGS Reston Survey Geochronology Laboratory Argon Geochronology Laboratory. The samples are from diverse localities and of diverse age.
Solidia Technologies Neutron Radiography to [mage Carbon Using neutron radiography to look at pressurized Dioxide in Concrete CO2 in concrete that is curing.
University of MN2019a Neutron irradiation of geologic material for noble Manchester gas analysis and dating.
Funding Auburn University NM Bureau of Geology Columbia Univeristy USGS Argon Geochronology Menlo Park Geochronology Nray Services, Inc.
U.S. Geologigcal Survey Solidia Technologies University of Manchester
~
0
- 0
~
Project Users 2160 Schaen 2161 Turina 2162 Jump 2163 Sathuvalli 2165 Caffrey 2166 Kampfer 2167 Reese Table Vl.2 (continued)
Listing of Major Research and Service Projects Performed or in Progress at the Radiation Center and their Funding Agencies Organization Name Project Title Description Department of University of Arizona 40Ar/39Ar Irradiation rock and mineral samples for Geosciences, University of Arizona Geochronology 40Ar/39Ar dating.
NAA of clays to determine radioactivity level Museo Egizio NAAofClays for future neutron radiography work. This will determine/estimate how long the samples will need to be held prior to free release.
Oregon State Role of Microbiota in the Effects of To address the role ofmicrobiota in fatty liver Polyunsaturated Fatty Acids (PUFA) on University Liver disease and in beneficial effect of PUFA on liver.
The main idea is to introduce gamma rays to tissue cultures of three potato varieties in a bid to induce mutations to the plants. There are certain qualities/characteristics we hope will be mutated, and so, upon inducement with gamma radiation, Department of Gamma Irradiation of Potatoes we will evaluate the plants (if they survive the Horticulture mutation) for those qualities. The first stage is to ascertain the optimum radiation dosage for the three varieties under evaluation. A second stage will come up where the potatoes will be evaluated based on information from the first, i.e. the optimum radiation dosage.
A set of five polymers (EPDM, PTFE, PCTFE, PFA, PAI) used in common spaceflight NASA Marshall Space applications are to be exposed to the mixed Flight Center Nuclear Propulsion Polymer Tests neutron/gamma field of the OSTR in order to evaluate changes in material properties. The current test includes a total of 60 'microdogbone' ASTM D638 Type V tensile specimens.
Materion Corp.
Trace-Element Analysis of Be Powder fNAA to determine U content of Be powder.
Oregon State Neutron Radiography of Artifacts, Use of neutron radiography to examine University Articles, and Instruments archaeological artifacts, samples of interest, and instrumentation.
Funding University of Arizona Oregon State University Oregon State University Horticulture NASA Materion Corp.
Table Vl.2 (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 We are trying to isolate the effects that biofilm growth and fouling has on sorption kinetics, breakthrough, and desorption in packed columns Oregon State The Effects ofBiofilms in CLM Testing of two different proprietary adsorbents. By looking Oregon State 2168 Radniecki ofSorbents for Removal of Cu, Zn, and at the data for triplicate columns with and without University CBEE PFAS's from Stormwater biofilms enriched from the OGSIR facility in University CBEE Avery Park, we hope to isolate the effects that naturally occuring biofilms have on sorption removal of PFASs, zinc, and copper in stormwater.
2169 Field Environmental and PFAS Compounds in the Environment INAA to determine total fluorine content in OSU Toxicology Molecular Toxicology consumer products and the environment.
Testing electrical conductivity changes of Thermoelectric Cooler Conductivity materials while monitoring temperatures of device 2170 Howe Howe Industries Experiment and ambient conditions. Power will be stepped Howe Industries at various levels to determine these parameter changes.
We would like to get these seeds irradiated for Department of Plant inducing gamma irradiation-induced chromosomal University of Gamma Induced Chromosomal Breaks breaks in CS and MOY-wheats. Lt will allow 2171 Tiwari Science and Landscape in CS and MOY Wheats us to map targeted candidate genes in low Maryland, College Architecture recombination regions and will help in overall Park wheat improvement.
The project is looking at positive and negative consequences of using persistent herbicides for invasive species management at high latitudes.
The irradiated soils will be used to develop 2172 Graziano University of Alaska, Control of lnvasive Plants at High soil herbicide isotherms for aminopyralid and University of Alaska Anchorage Latitudes with Persistent Herbicides clopyralid. The soils originate from two field sites (Fairbanks and Palmer) where these herbicides were applied. We will determine if the isotherms help predict the persistence of these herbicides at the field sites.
2173 Lee University of Oregon fNAA of Ancient Korean Ceramics Trace-element analyses of Neolithic and Bronze University of Age ceramics from Korea.
Oregon The scope of this project is to run tests and Fusion Energy calibrate our fast neutron detector through the Fusion Energy 2174 Horvath Solutions Fast Neutron Detection D(T,n)alpha reactions and calibration by F 18 Solutions, Inc.
decay from O 16+ T reactions to be measured on an OSU HPGe detector.
Project Users 2175 Gess 2176 Phelps 2177 Phelps 2178 Weiss 2179 Weiss 2180 Meqbel 2181 Singh 2182 Reese 2183 Sprain Table Vl.2 (continued)
Listing of Major Research and Service Projects Performed or in Progress at the Radiation Center and their Funding Agencies Organization Name Project Title Description Oregon State Neutron Radiography of Two Phase Use of neutron radiography to evaluate two phase University MIME Flow flow conditions during TREAT irradiations.
Adhezion Biomedical is interested in the effect of Gamma on various applicator parts and materials.
The purpose of this feasibility run is to provide ampoules from three different product lines to Adhezion Biomedical Various Ampoule Gamma-Feasibility understand the process and ensure your facility Run can stay within the range of 8-12 kGy. Once we get the samples returned, if all testing on our end results as expected, we will most likely send a second round of samples for further investigation of material compatibility with Gamma-irradiation.
Adhezion Biomedical is interested in the effect of Gamma on PVDF ampoules and the stability of the product post-irradiation. Analytical testing Adhczion Biomedical PVDF Ampoule Gamma-Feasibility Run shall follow on our end after Gamma-irradiation to determine if this is a good sterilization method lo move into a larger scale sterilization for our medical device product line.
Oregon Stale BASF Additive Concrete Curing Examination of a BASF additive to concrete University Investigation mixtures and its effect upon curing under pressure.
Oregon State ACI Investigation of Environmental American Concrete Institute examination of atmospheric effects, particularly humidity and University Factors on Concrete Curing pressure, upon concrete curing.
Hi-Tech Precious INAA of Mine Tailings INAA to detennine precious metal (gold and PGE)
Metals Refinery content of mine tailings.
Wadia Institute of Geo-Thermochronological Investigation To study the shallow crust exhumation history Himalayan Geology of Lesser Himalayan Crystalline of of the lesser Himalayan crystalline and Garhwal Region, NW-Himalaya metasedimentary sequence of Garhwal region.
Oregon State Use ofD2O as a Contrast Enhancement Examination of the improvement in contrast gained by using D2O instead ofH2O in the University for eutron Radiography analysis of concrete curing.
This project is for the irradiation of geological Department of materials with a high flux of fast neutrons to Irradiation for 40Ar/39Ar facilitate the 39K(n,p)39Ar reaction. Irradiated Geological Sciences, Geochronology geological materials will subsequently be analyzed University of Florida for 40Ar/39Ar gcochronological analysis to determine the age of the geological materials.
Funding Adhezion Biomedical Adhezion Biomedical l li-Tech Precious Metals Refinery Wadia Institute of Himalayan Geology Department of Geological Sciences, University of Florida 0
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Table Vl.2 (continued)
Listing of Major Research and Service Projects Performed or in Progress
~
at the Radiation Center and their Funding Agencies
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Project Users Organization ame Project Title Description Funding Universite Grenoble The apatite samples are for three different projects Universit6 Grenoble 2184 Bernet Alpes Apatite Fission Track Irradiations for studying the exhumation of the Himalayas, Alpes Andes, and European Alps.
2185 Taylor University of Pioneer Mountains AFT Suite of apatite c1ystals to be irradiated for fission University of Minnesota track dating.
Minnesota 2186 Cao Oregon State Fluorine Content in PFAS Standards INAA to determine nuorine content in PFAS Department of University standards.
Chemistry Irradiation of geologic materials (minerals apatite 2187 Stevens Goddard Indiana University Fission Track Analysis and zircon) for fission track analysis (age dating Jndiana University of thermal events) using the external detector method.
2188 Orme Montana State AFT Irradiation - MSU Irradiation of apatite grains mounted in epoxy for Montana State University fission track analysis at Montana State University.
University This project will develop and build a custom 2189 Kasparek Pacific Northwest Cerenkov In-Pool Noise Characterization UV probe and spectrophotometer to map the UV Pacific orthwest National Laboratory spectrum in spent fuel ponds and identify and National Laboratory quantify light noise contributions within the pool.
The sensor is an industrial grade accelerometer which consists of a silicon sensor and ASIC hern1itically sealed in a 0.35" square ceramic 2191 Hulbert Silicon Designs Inc.
Sensor Performance vs Total Ionizing package. This project will irradiate several groups Silicon Designs Inc.
Dose (TTD) of sensors over a range ofTlD and compare the before and after results of a variety of electrical and dynamic measurements to detennine the effect(s) of the radiation.
2192 Frame Yale University INAA of Archaeological and Geological Trace-element analysis via INAA of fired clay, Yale University Materials brick, and stone.
In this project, we investigate the provenance of Quaternary-Miocene basin-fill sediments in the Pannonian Basin. For this purpose, we carry 2193 Arato institute for Nuclear Pannonian Basin Provenance Il out fission-track analysis on apatite and zircon Institute for Nuclear Research, Hungary crystals. The uranium content of these crystals will Research, Hungary be determined via the external detector method, which requires the irradiation of our samples with thermal neutrons.
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Table Vl.2 (continued)
Listing of Major Research and Service Projects Performed or in Progress
~
at the Radiation Center and their Funding Agencies
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Project Users Organization ame Project Title Description F unding Support the 69981 Program (Child Project XYZ -
Pacific Northwest Lcxan Slides for Fission Track 70039) at Pacific Northwest National Laboratory Pacific Northwest 2194 Carter National Laboratory Irradiation by providing the ability to perform fission track ational Laboratory irradiation on Lexan slide targets in the thermal column facility.
Carbon nanotube (CNT) has high mechanical and electrical properties and widely used for nanocomposite applications as reinforcement Carbon Nanotube Prope1ties materials. Highly aligned CNT sheet or yam 2195 Liang Florida State Enhancement by E-beam and Gamma-showed significant properties improvement due Florida Stale University Ray Irradiation to high alignment degree over 0.7. High energy University electron beam or gamma ray irradiation increased the crosslink between CNTs, hence the resulting CNT/epoxy or CNT/BMI composite mechanical properties will be enhanced.
These studies will explore the individual and Housing Temperature: An Important combined effects of (I) mild chronic cold stress 2196 lwaniec Oregon State Variable for Simulated Spaceflight (induced by room temperature housing) and (2)
University Studies Using Mice hindlimb unloading (HLU) on premature bone loss in C57BL/6 (86) mice, a strain commonly used in spaceflight/simulated spaceflight studies.
We are developing drug delivery systems using Gerogia Institute of Gamma Sterilization Effects on Drug transdermal delivery systems. ln one of our Georgia Institute of 2197 Prausnitz projects, we are interested in gamma sterilization Technology Loaded Patches for terminal sterilization of our product which is Teclmology basically a dru_g/polymer mixture.
We would like to get these seeds irradiated Department of Plant for inducing gamma irradiation-induced University of Gamma Irradiation-Induced chromosomal breaks in varieties MD3 I 5 and PJT 2198 Tiwari Science and Landscape Chromosomal Breaks RIL 74-whcats. It will allow us to map targeted Maryland, College Architecture candidate genes in low recombination regions and Park will help in overall wheat improvement.
85 wt% Bi-Silicone will be irradiated using a 2199 Brown Stark Street Materials 85 wt% Bi-Silicone Gamma Irradiation GammaCell 220 for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at Oregon State Stark Street Corp.
University to better understand the material Materials property changes after in-adiation.
2200 Brown Stark Street Materials Bi-Si Attenuation Coefficient Determination of attenuation coefficients for Slark S trcct Corp.
Detem1ination various gamma energies.
Materials
Project Users 2201 Ocamb 2202 Weiss 2203 Phelps 2204 Reese 2205 Privitera 2206 Langtry 2208 Cherney Table Vl.2 (continued)
Listing of Major Research and Service Projects Performed or in Progress at the Radiation Center and their Funding Agencies Organization Name Project Title Description Fusarium species are economically important pathogens of a wide range of crops across the globe. These soilbome fungal pathogens are Oregon State Fusarium Diseases in I fop, Vegetables, even more important as their populations are University and Seed Crops increasing reaching higher levels in the soil.
Research activities are focused on monitoring the fungal populations in soil and plant parts for the development of mitigation strategies.
Oregon State NSF 3D Printed Samples Studying sorptivity of3D printed samples with University respect to printing directionality.
Adhezion Biomedical is interested in the effect of gamma on COC ampoules and the stability of SecurePortlY App with COC Ampoule the product post-irradiation. Analytical testing Adhezion Biomedical Gamma-Feasibility Run shall follow on our end after gamma-irradiation to detenninc if this is a good sterilization method to move into a larger scale sterilization for our medical device product line.
Development of prototype neutron radiography Oregon State
[NL Flash Radiography Camera camera for use in the OSTR Neutron Radiography University Development Facility. The prototype camera system will be used as part of the fNL flash radiography facility al TREAT.
Our goal is to irradiate antimony pellets in order Kavli Institute for Irradiation of Sb to 5 mCi ofSb-124 for to achieve 5 mCi activity. Up to 5 grams of pellets are available. Pellets will be housed in 0.5 in Cosmological Physics DAMlC-M diameter x I in length polyethylene vial during irradiation.
Avalanche Energy is a VC backed startup developing a small compact deuterium-deuterium fusion device which has applications as a high-flux neutron source and longer tenn potentially for energy generation. This small plasma device Avalanche Energy Compact NculTon Generator
( 12 cm diameter) combines aspects of an ion trap (electrostatic ion confinement) with a cylindrical magnetron for ExB electron confinement. First proof of concept experiments are underway at our lab in Seattle, and we would like to calibrate our neutron detection equipment at Oregon State's facilities.
Oregon State Medical Isotope Feasiblity Studies Detennination of feasibility making different University medical isotopes using the TRI GA reactor.
Funding Oregon State University NSF Adhezion Biomedical University of Chicago Avalanche Energy
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Project Users 2209 Galindo 2210 Wu 2211 Rogers 2212 Hosmer 2213 Pang 2214 Gordon 2215 Lang 2218 Mutin 2219 Dyrdahl 2220 Arato Table Vl.2 (continued)
Listing of Major Research and Service Projects Performed or in Progress at the Radiation Center and their Funding Agencies Organization ame Project Title Description Rosebud Sioux Tribe Multielement analysis offired clay samples via Historic Preservation INAA of Fired Clay Samples Office INAA.
Tectonic Thermal Evolution History of Use of fission track analysis to determine U Peking University content in the sedimentation of Junggar Basin. To Junggar Basin study the thermal historv of the basin.
Greentree Synergy INAA of Metal Products Elemental analysis via INAA of finely divided elemental metals.
102nd Oregon Civil Isotope Production of Various Sources Production of various sources for training Suooort Unit purposes.
The apatite fission track time-temperature modeling is constructed on the laboratory Institute of Geology, annealing data sets and controlled by empirical Extending the Time-Temperature Ranges Arrhenius equations and time and temperature China Earthquake of Apatite Fission Track Annealing ranges. Improvement of the annealing ranges Administration would result more comprehensive extrapolations parameters from the lab annealing to the geological time scales.
Redwood Materials Trace Impurities in Copper Foils lNAA and LSC to detect trace impurities in copper foils.
Regular irradiations for fission track dating.
Common minerals include: apatite embedded in Georgia Institute of Ongoing Fission Track Irradiations epoxy and zircon embedded in PFA Teflon. All Technology mineral samples are wrapped in Scotch Magic tape with a piece of low-U mica, labeled with a Sharpie and bound together with Parafilm.
fNAA to quantify chemical composition of Benjamin Mutin I AA of Iranian Pottery archaeological ceramics from ancient Iran to determine provenance.
Pontificia Universidad Ceramic Sourcing in N. Highland Chemical analysis of ceramics via INAA to Cat61ica del Ecuador Ecuador determine provenance.
In this project, we st11dy fission tracks in standard Georg-August FTAIGE apatite and zircon crystals. For the so-called Universitat Gottingen external detector method, the thermal irradiation of the samples is necessarv.
Funding Peking University China Earthquake Administration Georgia Institute of Technology Pontificia Universidad Cat61ica de) Ecuador Georg-August Universitat Gottingen
Project Users 2221 Williams 2223 Apigo 2225 We11h 2226 Reese 2227 Alden 2228 Gaspich 2229 Adlakha 2231 Jackson Table Vl.2 (continued)
Listing of Major Research and Service Projects Performed or in Progress at the Radiation Center and their Funding Agencies O rganization ame Project Title Description Soil blocks and wafers are to be gamma stcrlized and returned to Kop-Coat to evaluate gamma Kop-Coat KCPP Gamma Treatment of Soil Blocks sterilization as alternate to autoclave sterilization.
ASTM D 1413 recommends "a radiation level of 2.0 to 2.5 Mrad when using radioisotopes or 2.0 to 5.0 Mrad if electron accelerators are used."
This project will examine how fungi that live inside leaves control the decomposition rate of Populus trichocarpa leaves. Leaves will be Oregon State Litter Decomposition by Fungal sterilized of existing microorganisms using the University Endophytes Gamma cell 220 60Co gamma irradiator. We will inoculate specific commw1jties of fungi onto the sterilized leaves to understand how specific fungal soecies affect litter mass loss over time.
We want to sterilize our soil with gamma irradiation to prevent microbial processes from University of Texas at Abiotic TCE Reactions in Clay Soil interfering with our abiotic reactions of interest.
Austin The sterilized clay soil will be used in batch experiments to measure its reactivity toward TCE under varying conditions.
Oregon State Testing concrete curing for Oregon Department of University ODOT Concrete Curing Transportation using neutron radiography. Imaging specimens in a dry and sarw-ated state.
University of Michigan INAA of Archaeological Ceramics from Provenance determination of ceramics from lraqi Iraqi Kurdistan Kurdistan via trace-element analysis.
Oregon Stale Detection of Sodium Content in TNAA to track sodium content in fish cells as a University Biological Materials proxy for cell lvsis.
These samples are sent for thermal neutron Wadia Institute of irradiation for fission track dating purposes to Himalayan Geology Fission Track Thermochronology understand the exhumation history of various rocks exposed along Lohit and Dibang Valley region, NE India.
CleanMark to provide indicating ink material via Gamma (Material # 500) to OSU to sterilize and CleanMark Labels Gamma Activation Test validate at what point in range of sterilization application does the material start to indicate with a different color (yellow to pink).
Funding Kop-Coat Department of Botany and Plant Pathology University of Texas ODOT OSU Radiation Center, Mine Oregon State University - FST Wadia Institute of I limalayan Geology CleanMark Labels
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Table Vl.2 (continued)
Listing of Major Research and Service Projects Performed or in Progress
~
at the Radiation Center and their Funding Agencies
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Project Users Organization Name Project Title Description Funding This project uses various thermochronometers to trace the cooling and exhumation history along Thermochronology Along the lnsubric and across the most important fault system of the University of 2232 Ilcberer University of Salzburg European Alps. Among these thermochronometers Line are apatite and zircon fission track dating, which is Salzburg carried out in collaboration with Hannah Pomella from the University of Innsbruck.
2233 Wallace Andluca Technologies Trace Halogen Detection by lNAA Detection of trace halogens (Cl, Br, I) in organic Andluca materials by Neutron Activation Analysis.
2234 Reese Oregon State NRF Camera Development Development of a digital camera system for the University NRF.
Neutron imaging will be used to determine drying behavior of CAC-based pastes among these methods. Within minutes of mixing, the 2235 Weiss Oregon State Neutron Imaging of Calcium Aluminate CAC-based pastes will be placed in the beam in University Cements sealed and drying environments. The effect of the drying behavior on the transport, mechanical, and physical properties of the fresh CAC-based ternary mixtures.
Nu Planet Analysis of0.98 g Th(NO3)4-4H2O dissolved in Nu Planet 2237 Adams Pharmaceutical Nu Planet Thorium Validation 20 mL water via 1-lPGe to determine the activities Pharmaceutical Radioisotopes. Inc.
of thorium and associated daughter products Radioisotopes, Inc.
(actiniw11 and lead) for validation purposes.
CleanMark to provide indicating ink material via Gamma to OSU to sterilize and validate 2239 llagen ClearMark Labels Gamma Activation Test if processed at a full 30 kGy dose range of CleanMark Labels sterilization application does the material indicate with a different color (yellow to pink).
INAA of Archaeological Ceramics from lNAA of ceramic shards from the Zayandeh-rud 2240 Rafieri-Alavi Central Iran drainage basin in central Iran dating to the 4th-3rd millennium BC.
We plan to neutron-irradiate natural mineral samples, including hornblende, feldspar, and mica, 2244 llofmann University of Alaska, Neutron Irradiation for 40Ar/39Ar at OSTR (CLICIT) in preparation for routine University of Alaska, Fairbanks Dating at UAF 40Ar/39Ar dating at the University of Alaska, Fairbanks Fairbanks. Most individual irradiation periods will likely be 6 h.
Table Vl.2 (continued)
Listing of Major Research and Service Projects Performed or in Progress
~
at the Radiation Center and their Funding Agencies
~
Project Users Organization ame Project Title Description Funding No,throp Grumman Use of neutron radiography to explore the Northrop Grumman 2247 Mais Corporation Neutron Radiography of Components capability to determine the seating of rubber Corporation gaskets in metal components.
2251 Beveridge Atomos Space Heating Experiment Irradiation of Mn-55 to produce radioactive source Atomos Space that will be used to measure decay heat with.
2254 Cherney Oregon State Development of BPI PGNAA Facility Characterization of the beam and capabilities on University the PGNAA system located on Beam Port I.
2255 Cherney Oregon State Irradiation of Unknown Materials Short runs to detem1ine elements of unknown University matrix.
2256 Thrower ManTech - Vallecitos Yallecitos Laboratories AEM Irradiation services as part of our sample ManTech Laboratories - AEM processing.
The Argon Geochronology lab run by the U.S.
U.S. Geological Geological Survey in Moffett Field, CA conducts 2257 Stclten Smvey Argon Geochronology geochronologic investigations primarily on USGS the eruptive history of volcanic system using 40Ar/39Ar geochronolo!!V.
Basement and metamorphic cover rocks from the 2258 Idleman Lehigh University Ar/Ar Geochronology northern Appalachians with the goal of clarifying Lehigh University the long-term low-temperature evolution of the terrain.
2259 Volpi University of Rome INAA of Ceramics from Tepe Zurghul Elemental analysis via INAA to determine provenance of ancient ceramics.
2260 Reese Oregon State Surface Imaging of Metal Buttons Use of neutron radiography to look at surface of University SS sample buttons.
Oregon State Elemental characterization via INAA to determine Monash University, 2261 Mine Tepe Godin provenance of ancient ceramics from Godin Tepe, University Iran.
Australia 2262 Beveridge Atomos Space Determination ofNeutron Flux in Irradiation of foils and standards to determine flux Atomos Space Various Irradiation Facilities in the ICIT, LS, and TC.
INAA of Artifacts from the Michael Elemental analysis via INAA of ceramic artifacts Emory University, 2263 Stein Emory Umiversity Carlos Museum of Hellenstic age from the museum's collections.
Michael C. Carlos Museum Gamma Cell irradiation of three (3) sealed 2264 Bergman BWX Technologies BWXT Geotextile Gamma Irradiation samples, eacb sample containing four (4) types of geotextile fabrics. Each sample will be 6 in. x 6 in. BWX Technologies Requested irradiation doses: 20kGy for sample I, 60 kGy for sample 2, and I 00 kGv for sample 3.
2265 Cherney Oregon State Chemical Separation of Fission Products Irradiation of materials to produce fission products OSU NSE University for testing of non-traditional separation methods.
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Project Users 2266 Reese 2267 Stanevich 2268 Reese 2269 Tyler 2270 Shc1man 2271 Cherney 2272 Yasar 2273 Reese 2274 Higley 2275 Bertassoni Table Vl.2 (continued)
Listing of Major Research and Service Projects Performed or in Progress at the Radiation Center and their Funding Agencies Organization ame Project Title Description Oregon Department of Instrument Calibration Activities Working on ODOE and HazMat instrument Enern:v capabilities, calibrations, and issues.
This is a test to show that our diodes can survive Rocket Lab Diode LAT in a gamma radiation environmnet. Oregon State will provide a gamma radiation dose >50rad/s for a total dose to 120Mrad.
Oregon State Neutron Radiography of the Instrumental Use of neutron radiography to look at the status University Fuel Element of the thcm,al couples in the instrumented fuel element.
Phylos Bioscience 2024-08GC Cobalt-60 gamma irradiation of ground flower for Colombia expo11.
Tdaho National Characterization of aggregates and cement Laborato1y TN AA of Cement powders for potential reactor shielding concrete designs.
Oregon State Irradiation of metal oxides for combination with University VF Separation Project uranium oxide to simulate spent fuel separation scenarios.
This project is for the i1Tadiation of geological materials with a high flux of fast neutrons to University ofFlorida Ar/Ar Age Dating Analysis facilitate the 39K(n,p)39Ar reaction. Irradiated geological materials will subsequently be analyzed for 40Ar/39Ar geochronological analysis to determine the age of the geological materials.
Oregon Department of Hanford Emergency Response Report Support ofODOE for responses to emergencies at Enere:v Hanford.
This project is intended to experimentally investigate the presence of a hypothetical metabolic pathway utilized by eumelanin Oregon State Metabolic Response of Irradiated pigmented fungi responsible for the conversion University Eumelanin Pigmented Fungi of ionizing radiation directly into cellular energy.
Fungi cultures grown on (sealed) Sabourand Dextrose Agar plates will be irradiated to I 00, 500, and 1,000 Gy prior to further experimental procedures.
Modular, 3D-printed bTCP scaffolds loaded with Oregon Health OHSU - bTCP Lego Scaffold microgels for enhanced bone regeneration. The Sciences University modular scaffolds allow for customizable shapes to fit any defect.
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Funding Oregon Department of Enern:v Rocket Lab Phylos Bioscience Idaho National Laboratory OSU NSE University of Florida OSUNSE Oregon Health Sciences University
Table Vl.2 (continued)
Listing of Major Research and Service Projects Performed or in Progress
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at the Radiation Center and their Funding Agencies
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Project Users Organization Name Project Title Description Funding The goal of this project is to understand whether clay minerals are capable of preserving 2276 Hausrath University of Nevada, Exobiology Project biosignaturcs through the interaction of clay University of Las Vegas minerals and microorganisms. Various clay Nevada, Las Vegas minerals with different microorganisms will be investigated.
Hemingway Designs is exploring the use of polyhydroxyalkanoate (PHA) as a more sustainable material for use in a "transient contact" medical device application in the home diagnostics and therapeutics area. Nearly all such devices are Hemingway Designs, Hemingway Designs PHA Simulated sterilized via 60Co gamma irradiation at a dose of Hemingway 2279 Brandel!
25kGy to achieve a projected sterility assurance LLC Sterilization level (SAL) of 10-6. Most devices of these types Designs. LLC advertise shelf lives up to five years, so we will conduct mechanical testing following sterilization and accelerated aging includes tensile testing (ASTM D638) and flexural strenth testing (ASTM D790).
Researchers will conduct gamma irradiation studies (using 2.5 Gy and 5 Gy) on human Gamma Irradiation Studies for Human neuronal cells to anaylzc gene expression 2280 Joddar Oregon State Neuronal Cells to Determine Differential changes. Their findings will reveal differential Oregon State University Gene Alterations gene alterations in response to radiation exposure.
University These results will contribute to a deeper understanding of how neuronal cells react to gamma irradiation at the genetic level.
We have some 3D printed plastics that we want to gamma irradiate with a 20kGy dose, so that we can measure their mechanical properties. We 2281 Glathar VivoTcx Measurement of a Sample would need to send some small plastic samples VivoTcx for irradiation within a 24-well cell culture plate which has an approximate size of 15 x IO x 2 cm (I x w X h).
Dctennine if the piece of steel was manufactured 2282 Smith Self Speedster Dating before or after the above ground testing of nuclear Self bombs
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Project Users 2283 Neff 2284 Cooper 2285 Pantana 2287 Gaulke 2288 Reese 2290 Slauson 2291 Yates 2292 Parsons-Davis 2294 Pope Table Vl.2 (continued)
Listing of Major Research and Service Projects Performed or in Progress at the Radiation Center and their Funding Agencies Organization ame Project Title Description Washington State Co60 gamma irradiation ofbcrmudagrass University Bermudagrass Irradiation stolon (small plant pieces) with 90Gy to induce mutations.
Idaho National Shott-Lived Isotope Production 11Tadiation of copper and potassium bromide sol-Laborato1y gels for sho1t-lived isotope production.
This project is a material properties study Propylene Glycol Radiation Test -
of propylene glycol after exposre to gamma BWXT BWXT radiation. A gamma cell will be used at OSU to irradiate three 500ml samples of propylene glycol.
One sample to I MGy, 2 MGy, and 3 MGy.
Gnotobiotic experiments in zebrafish requires a source of high-quality sterile feed. We have previously demonstrated that 20kGy dose of University of Illinois, Gaulke Zcbrafish Food Gamma gamma irradiation is sufficient to produce sterile Urbana-Champaign Irradiation feed without significantly altering animal growth rates. This project will treat customer provided zebrafish feed with 20kGy dose of gamma irradiation for use in downstream gnotobiotic zcbrafish experiments.
The purpose of this agreement is to develop and maintain Oregon State University procedures to Oregon Depa1tmcnt of Columbia Generating Station Support prepare and participate in exercises and drills, Energy and if necessary, actual emergencies related to the Energy NW-Columbia Generating Station nuclear power plant.
Identify isotope and detem1inc specific activity (uCi/gram) of three concrete samples that arc known to contain a long-lived radioisotope Western States Physics Central Oregon Humane Society (possibly thorium or radium). Count two steel samples for radioactivitiy. If radioactive isotope is contained within steel, determine isotope and specific activity.
JNAA for Trace-Element INAA for trace-element characterization of Self - Individual Characterization of Geological Samples geological materials of potential commercial interest.
Lawrence Livermore Fission Product Production Irradiation of highly enriched and highly depleted National Laborato1y foils for nuclear forensics.
Washington State JNAA of Apatite Bulk chemical analysis of apaptite samples via University INAA.
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Funding Washington State University Jdaho National Laboratory BWXT Univeristy of Illinois, Urbana-Champaign Oregon Department of Energy Western States Physics Lawrence Livermore National Laboratory Washington State University
Project Users 2295 Ogden Table Vl.2 (continued)
Listing of Major Research and Service Projects Performed or in Progress at the Radiation Center and their Funding Agencies Organization Name Project Title Description Gemoftheamericas.
The Effects of Irradiation on Topaz, The purpose of this project is to analyze the economic and commercial benefits of irradiation com Beryl, and Xonotlite on gem quality pieces of topaz, beryl, and xonotlite.
Funding Gemoftheamericas.
com
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=- WORK Table Vl.3 Summary of Radiological Instrumentation Calibrated to Support OSU Departments OSU Department Number of Calibrations Chemistry Radiation Safety Office 11 Vet Med TOTAL 13 TableVl.4 Summary of Radiological Instrumentation Calibrated to Support Other Agencies Agency Number of Agency Number of Calibrations Calibrations Columbia Memorial I lospital 2
Oregon Lottery I
EPA I
Oregon State Fire Marshal 8
Hillsboro Medical Center 10 Radiation Protection Services 122 Knife River 3
Salem Health 21 NETL, Albany 4
Salem Radiology Consultants 2
ODOT 4
Samaritan Health 41 Oregon Health Sciences University 77 Vancouver Fire Department 44 TOTAL 340 Figure Vl.1 Summary of the Types of Radiological Instrumentation Calibrated to Support the OSU TRIGA Reactor and Radiation Center 40 35 30 25 20 15 10 AlPHA DETECTORS 37 GM DETECTORS 18 ION CHAMBERS MICRO METERS 29 PERSONAl DOSIMETERS
-WORDS Documents Published or Accepted Abdcina, E. H., Jourdan, F., Chazot, G., Bertrand, H., & Le GaU, B. (2024). How old is the Eye of Africa? A polyphase history for the igneous Richat Structure, Mauritania. Lithos, 482-483.
Ahn, U.S., et al. (2024). Geologic map and explanation (Hallasan, 1 :25,000) (346 p.). Jeju World Heritage Office.
Amato, V., Ciaccia, S., Galli, P., Cicchella, D., Galderisi, A.,
Monaco, L., FernaJ1dez, G., Jsaia, R., Nomade, S.,
Pereira, A., & Giaccio, B. (2025). Unveiling the hidden source of major historical earthquakes: A multi-scale, trans-disciplinary approach to the 1456 and 1688 Sannio earthquakes (Mw 7.0, southern Italian Apennines). Quaternary Science Review.
https:/ /doi.org/10.10 I 6/j.quascirev.2025.109282 Arriga, G., Marchegiano, M., Peral, M., Hu, IL, Cosentino, 0., Shen, C., Dalton, H., Brilli, M., Aldega, L.,
Claeys, P., & Rossetti, F. (2024, accepted). Long-term tectono-stratigraphic evolution of a propagating rift system, I:Aquila intermontane basin (Central Apen11incs). Tectonics, 43( 12). https:/ /doi.
org/ 10.1029/2024TC008548 Barnes, C. J., Larson, K., Button, M., & Camacho, A.
(Accepted, pending revisions). Coupled K/Ca and Rb/Sr geochronology ofpotas~ic mica and comparison with V/ Pb geochronometers: A case study from the Scandinavian Caledonidcs.
Geostandards and Geoanalytical Research.
Baud1,, A., Sillger, 8. S., Jicha, B. R., Jilly Rehak, C. E.,
Vazquez, J. A., & Keller, C. B. (2024). A Bayesian age from dispersed plagioclase and zircon dates in the Los Chocoyos ash, Central America. Earth and Planetary Science Letters, 643, 118826. https:/ /doi.
org/ 10.1016/j.epsl.2024.118826 Bennell, S. E. K., Darin, M. H., Dorsey, R. J., I Jausback, B.,
Grandy, S., Heizler, M. T., Stelten, M. E., Pecha, M.
E., Schmitt, A., & Dolby, G. A. (2025). Neogene volcano-tectonic evolution of the central Baja CaJifornia Peninsula, Mexico: Transition from subduction to rifting and marille incursion.
Geological Society of America Abstracts with Programs, 57(4). https://doi.org/ 10.1 130/
abs/2025CD-4099 l 6 Billstrom. K., Bergman. S., Mark. C., & Barfod, D. N. (2025).
New 40Ar/39Ar mineral ages of Archaean to early Proterozoic rocks in northern Sweden and implications for the 1.8-1.5 Ga tectonothermal history of northernmost Fennoscandia. International Journal of Earth Sciences. https://doi.org/10.1007 /
s00531-024-02488-6 Bineli Betsi, T., Kelepile, T., Shindo, K., Mapeo, R. B., &
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Rivera, T. A., Jicha, B. R., Kirby, S., & Peacock, H. B. (2024).
Temporal, spatial, and chemical evolution of Quaternary high sjJjca rhyolites in the Mineral Mountains, Utah. U.S. Geological Survey Professional Paper, 1890, chap. K. https://doi.org/10.3133/ppl890K Rivera, T., & Jicha, B. R. (2025). Not so mush: Discrete pulses of high silica melt generation in the Mineral Mountains, Utah. Contributions to Mineralogy and Petrology, 180(56). https://doi.org/10.1007/s00410-025-02243*3 Rivera, T., Holliday, M., Jicha, B., Malone, D., Braunagel, M.,
Bonilla Franco, V. A., Biek, R., Griffith, W. A., &
Hacker, D. (2025). Emplacement age of the Sevier Gravity Slide, Utah, USA. Geochronology, 7, 35 44.
https:/ /doi.org/ 10.5194/gchron-7-35-2025 Roberts, C. A., Zanchetta, G., Giaccio, B., Nomade, S.,
Mannella, G., Sadori, L., Drysdale, R., Maselin, M.
A., Albert, P. G., Smidt, C., Smith, V C., Flynn, M.,
Sottili, G., Wagner, 8., & Tzedakis, P. C. (2025). A radiometricaUy-constrained reference record of the last interglacial climate and vegetation changes from the Fucino Basin, Central ftaly. Quaternary Science Reviews. https://doi.org/10.1016/j.
quascirev.2025.109377 Rout, S.S., Worner, G., Wegner, W., & Singer, B. S. (2024).
Heat pulse dominated magmatic storage: The 33 ka dacite dome eruption at Taapaca volcano (Central Andes). Geology, 52,683 688.https://doi.org/10.1130/
G52I73.l Rozefelds, A., Milroy, A., Carpenter, R., Douglas, A., Fabillo, M., Savelkou]s, A., & Dalton, H. (2024, submitted).
Silicified Melastomataceae fruits preserved by intraplate volcanism from an early Oligocene Capella Flora, Eastern Australia.
Rybar, S., Sarinova, K., Jourdan, F., Mayers, C., & Sliva, L.
(2024). Middle Miocene volcanic flare up preceding and synchronous with the Langhian/Serravallian sea-level decline in the North Pannonian Basin:
Insights from 40Ar/39Ar dating, gee-seismic analysis and 3D visualization of the subterranean Kral'ova stratovolcano. Basin Research, 36(1 ).
Samim, S., Dalton, H., Phillips, D., & Hergt, J. (2025, accepted). High-resolution tephrochronology resolves stratigraphic complexities in archaeologically significant Nariokotome tuffs, Turkana Basin.
Proceedings of the National Academy of Sciences of the United States of America, 122(38), e2424142122.
https://doi.org/10.1073/pnas.2424142122 Sanfilippo, A., Ligi, M., AvanziJ1elli, R., et al. (2025). Magmatic underplating and crustal intrusions accommodate extension during Red Sea continental rifting. Nature Communications, 16, 6488. https://doi.org/10.1038/
s41467-025-61598-0 Savelkouls, A., Dalton, H., & Phillips, D. (2024, submitted).
Higb resolution 40Ar/39Ar geochronology of the Koobi Fora Tuff Complex, Omo-Turkana Basin, Kenya. Quaternary Geochronology.
Shan, P. F., M. J. Cao, N. J. Evans, P. Hollings, F. Jourdan, L.
Wang, and K. Z. Qin. (2024). ln-situ geochronology combined with geochemical and isotopic signatures record mineralization and fluid characteristics at the Xiaox:i'nancha porphyry Au-Cu deposit, NE China.
Mineralium Deposita, 59(8), 1703-1719. doi: 10.1007 /
s00126-024-01294-z Shang, S., Uunk, B. A., Kuiper, K. F., Brouwer, F. M., &
Wijbrans, J. R. (2025). Early Cretaceous to Miocene Tectonic Evolution of the NW Cyclades Based on 40Ar/39Ar Multiple Single Crystal Dating of White Mica From Andros. Tectonics, 44(6), e2024TC008590.
doi:10.1029/2024TC008590 Singer, B. S., Baudry, A., Keller, C. B., Jicha, B. R., filly Rehak, C.
E., & Vazquez, J. A. (2025). Response to comment on:
A Bayesian age from dispersed plagioclase and zircon dates in the Los Chocoyos ash, Central America.
Earth and Planetary Science Letters. https://doi.
org/10.1016/j.epsl.2025.119215 Singer, B. S., Jicha, B. R., Sawyer, D., Walaszczyk, I., Landman, N., Sageman, B. B., & McKinney, K. C. (2025). A 40Ar/39 Ar and U Pb time scale for the Cretaceous Western Interior Basin, North America. Geological Society of London, Special Publications Series, 544:
Cretaceous Project 200: Volume 1 The Cretaceous World, SP544 2023 76. https://doi.org/10. l 144/SP544-2023-76
WORDS Singer, B. S., Moreno Yaeger, P., Townsend, M., Huber, C.,
Cuzzone, J., Edwards, B. R., Romero, M., Orellana Salazar, J., Marcott, S., Breunig, R. E., Ferrier, K. L.,
Scholz, K., Coonin, A. N., Alloway, B. V, Tremblay, M. M., Stevens, S., Fustos Toribio, I., Moreno, P. I.,
Vera, F., & Amigo, A. (2024). New perspectives on ice forcing in continental arc magma plwnbing systems.
Journal ofVolcanology and Geothermal Research.
https:/ /doi.org/ 10.1016/j.jvolgeores.2024. l 08187 Spilcings, R., Betancur, S., Vallejo, C., Chiaradia, M., Ulianov, A., de Haller, A., Forti, S., Winkler, W., & Beate, B.
(2024). New constraints on the tectonic history of the basement of the Western Cordillera and coastal forearc of Ecuador. Lithos, 488-489, 107821. https://
doi.org/ 10.1016/j.lithos.2024.107821 Stojadinovic, U., Pomella, H., Krstekanic, N., Kostic, B.,
Males, M., Randjelovic, N., & Radonjic, M. (2024).
Exhumation history of the Ju110r Mts. in central Serbia, the Northern Serbo-Macedonian Subunit.
Geologica Carpathica, 75(3), 213-223. https://doi.
org/ 10.31577 /GeolCarp.2024.12 Su, F., Zhang, X., Li, Y., Jicha, B. R., Joy, K. H., Li, Q., Chen, Y., Cai, S., Liu, R., Zhou, Q., Yang, S., Li, X., Yang, L.,
Chen, W., Li, J., Zhang, W., Qiu, H., He, H. (2025).
Constraining 2.0 Ga volcanism on the moon via 40Ar/39Ar dating of Chang'e 5 basalts. Journal of Geophysical Research: Planets, 130, e2024JE008495.
https:/ /doi.org/ 10.1029/2024JE008495 Sun, X., Ding, W, Kuiper, K. F., Tian, Y., Zhang, Z., Guo, R., & Wijbrans, J. R. (2024). New early Oligocene age for the Mouding Basin, Southwestern China:
Source and paleoenvironment. Palaeogeography, Palaeoclimatology, Palaeoecology, 636, 111983.
doi:10.1016/j.palaeo.2023.111983 Tan, F., Yin, J., Xiao, W., TI1omson, S. N., Eizenhi:ifer, P.R.,
Chen, W., Wang, T., Huang, H., Wang, Y., Zhao, Y., & De Grave, J. (2025). Meso-Cenozoic episodic uplift and exhumation of the Zhangguangcai Range, Northeast China: Insight from low-temperature thermochronology. Geological Society of America Bulletin. https:/ /doi.org/10.l 130/B38074.1 Teodoro, M. A. M., A. C. Dos Santos, L. C. Bertolino, P. A. D.
S. Rosa, C.R. Bezerra, L. G. P. Monteiro, J.C. L. da Silva, M. B. Fagundes, M. C. Geraldes, L. M. D. C.
Cardoso, and 1 more contributor. (2025). Poyos de Caldas - Cabo Frio Alignment: a Petrochronological Review of an Unconventional Plume Model. Anuario do Institute De Geociencias, 48. doi:10.11137/1982-3908_2025_48_65281 Tortelli, G., Gioncada, A., Pagli, C., Barfod, D. N., Corti, G.,
Sani, F., Mark, D. F., Dymock, R. C., Gebru, E. F., &
Keir, D. (2025). Volcanism records plate thinning driven rift localization in Afar (Ethiopia) since 2-2.5 million years ago. CommW1ications Earth &
Environment. https:/ /doi.org/ 10.1038/s43247-025-02356-4 Totaro, F., Petrosino, P., Valente, E., Arienzo, 1., D'.Antonio, M., Di Vito, M. A., Giaccio, B., Jicha, B. R., PetrelJi, M., Santangelo, N., Santo, A., & Zanchetta, G.
(2024). Last interglacial paJeoshoreline location and tectono-stratigraphic evolution of the peri Tyrrhenian Sarno basin, southern Italy, constrained by tephrostratigraphy. Earth Surface Processes &
Landforms. https:/ /doi.org/10.1002/esp.6039 Tremblay, M. M., Mark, D. F., Barfod, D. N., Cohen, B. E.,
Ickert, R. B., Lee, M. R., Tomkinson, T., & Smith, C. L. (2024). Dating recent aqueous activity on Mars. Geochemical Perspectives Letters. https://doi.
org/10.7185/geochemlet.2443 Trapper, P., Klotz, T., Pomella, H., & Dunk.I, I. (2024). Visible and invisible complexities in low-to medium grade metamorphic rocks: Mineralogical and petrological constraints on the Variscan metamorphic gradient in the Southalpine metamorphic basement (BrLxen quartzphyllites, Northern Italy). In EGUsphere: EGU
- General Assembly 2024 - Book of Abstracts (No.
EGU24-J 731). Vienna, Austria & Online I 14-19 April 2024. Gottingen: Copernicus. https:/ /doi.
org/ 10.5 l 94/egusphere-egu24-l 73 l Uguagliati, F., Zattin, M., Waldschlaeger, K., & Ghinassi, M. (2024). Optimising microplastic polyethylene terephthalate fibre extraction from sedin1ents:
Tailoring a density-separation procedure for enhanced recovery and reliability. Science of the Total Environment, 957, 177483. https://doi.org/10.1016/j.
scitotenv.2024.177483 Uguagliati, F., Zattin, M., Waldschlaeger, K., & Ghinassi, M. (2024). Optimising microplastic polyethylene terephthalate fibre extraction from sediments:
Tailoring a density-separation procedure for enhanced recovery and reliability. Science of the Total Environment, 957, 177483.
van Grinsven, L., Beguin, A., Kuiper, K., & de Groot, L. V (2025). The evolution of a Mid-Miocene geomagnetic reversal. Earth and Planetary Science Letters, 667, l 19464. doi:10.1016/j.epsl.2025.119464
le * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *
- WORDS Vranjkovic A., Gierlowski-Kordesch E., de Leeuw A., Mandie 0., Aljinovic D., Dragicevic r., Harzhauser M., Kuiper K., Brcic V., Pavelic D. (2025). Sedimentology and palaeoenvironmental analysis of a karstic shallow carbonate lake (Early-Middle Miocene, Sinj Basin, Croatia). Depositional Record, 11(1), 121-146.
doi: 10.1002/dep2.292 Walker, L., Shire, J., Jaffe, )., Sprando, P., Olinger, J., & Cherney, A. (2025). Development and benchmarking of JANOGFETT: A novel Geant4-operated fission event tracking tool. Nuclear Instruments and Methods in Physics A, 1082, Article 170948.
Wallace, P. A., Otieno, V., Godec, P., Njoroge, R. W., Tubula, M. S., Cappelli, L., Kamau, P. M., Nomade, S., Mariita, N. 0., & Fontijn, K. (2025). Temporal and spatial evolution of explosive silicic peralkaline eruptions at the Olkaria Volcanic Complex and Longonot volcano in the Southern Kenya Rift. Journal of Volcanology and Geothermal Research. https:/ /doi.org/10.1016/j.
jvolgeores.2025.108275 Wang,)., Peng, H., Ding, L., Liu, C., Zattin, M., & Wang, L. (2024). Middle Triassic transcontinental connection between the North China Craton and the Paleo-Tethys Ocean. Communications Earth &
Environment, 5, 775. https://doi.org/10.1038/s43247-024-01276-w Wang, J., Peng, H., Ding, L., Liu, C., Zattin, M., & Wang, L. (2024). Middle Triassic transcontinental connection between the North China Craton and the Paleo-Tethys Ocean. Communications Earth &
Environment, 5, 775.
Wang, Y., Wei, Z., Yuan, S., & Rui, Y. (2025, under review).
Tectonic uplift of western East Kunlun Mountains since early Miocene: Consu*aints from detritaJ zircon fission track geochronology and subsurface data.
Palaeogeography, Palaeoclimatology, Palaeoecology.
Wang, Y., Yin, J., Xiao, W., Sobel, E. R., TI,omson, S. N., Wang, Y., He, z., Chen, W., Cai, K., & De Grave, J. (2025).
Multi-stage differential exhumation of the West Junggar and adjacent regions, NW China, revealed by regional low-temperature thermochronology.
Earth-Science Reviews, 267, 105154. https://doi.
org/10.1016/j.earscirev.2025.l 05154 Wei, X; Chen, H; Garzanti, E; Zheng, H; Wang, P; Jourdan, F; Shi, X; Zhu, K. (2025). Isochronous Miocene volcaniclastic horizon in the SW Tarim Basin:
Composition, ages, origins, and implications for tephrochronology. Bulletin of the Geological Society of America, 137(5-6), 2191-2215. doi:10.1130/
B37521.1 Wei, z., Wang, Y., & Yuan, S. (2025). Cenozoic initial widespread uplift of the Eastern Kunlun Mountains onset at approximately 20 Ma: Evidence from low-temperature thermochronology. Acta Sedimentologica Sinka. https://doi.org/ 10.14027 /j.issn.1000-0550.2025.0 l 2 Wilde, S. A., Jourdan, F., Frewer, L., & Kusiak, M.A. (2025).
Precise 40Ar/39Ar dating of multiple potassic minerals constrain the age and rapid cooling history of the WaJgidee Hills lamproite pipe, Kimberley Region, Western Australia, at 17.49 Ma. Chemical Geology, 680. doi:10.1016/j.chemgeo.2025.122698 Xia, W., Yin, J., He, Z., Thomson, S. N., Tan, F., & Wang, Y.
(2025). Meso-Cenozoic tectonic and thermal history of the Kuqa Depression, Tarim Basin: Insights from low-temperature thermochronology and vitrinite reflectance. Journal of Earth Science. https://doi.
org/10.1007 /s12583-025-2027-y Zech, R. F., Onken, C. T., Sartori, G., Simon, S. J., Shipandeni, A., Galli, A., Spi.kings, R. A., & Schmidt, M. W.
(2025). The age and source of Cambrian post-orogenic magmatism in the Kuboos-Bremen Igneous Province (Southern Namibia). Journal of African Earth Sciences, 226, 105592. https://doi.org/10.1016/j.
jafrearsci.2025.105592 Zhang, L., Huang, F., Xu, J., Liu, X., Yang, X., Zhang, Z.,...
Zattin, M. (2024). Continental crustal growth in the post-collisional setting: insights from the Late Triassic high-Mg andesites in the eastern Central Asian Orogenic Belt. GSA Bulletin. doi: 10.1130/B37578. l Zhang, L., Huang, F., Xu, J., Liu, X., Yang, X., Zhang, Z.,..
. Zattin, M. (2025). Continental crustal growth in the post-collisional setting: insights from the Late Triassic high-Mg andesites in the eastern Central Asian Orogenic Belt. Bulletin of Geological Society of America, 137, 1521-1537.
Zhang, L., Huang, F., Xu, J., Liu, X., Yang, X., Zhang, Z.,
Zhang, M., Zeng, Y., & Zattin, M. (2025). Continental crustal growth in the post-collisional setting: Insights from the Late Triassic high-Mg andesites in the eastern Central Asian Orogeni.c Belt. Bulletin of the Geological Society of America, 137, 1521-1537.
Zhang, W. F., D. W. Zheng, F. Jourdan, A. Frew, C. Mayers, Y.
G. Xu, H. Y. He, Y. Q. Zhang, ). J. Wang, Y. D. Jiang, and 3 more contributors. (2024). ZMT04 muscovite:
a potential Paleoproterozoic reference material for 40Ar/39Ar dating. Journal of Analytical Atomic Spectrometry, 39(9), 2173-2182.
WORDS Presentations Adkins, R., Taylor, J. M., Siddoway, C. S., Thomson, S. N., &
Teyssier, C. (2024). Unveiling the geologic history of Marie Byrd Land, West Antarctica: Insights from thermo-kinematic modeling and low-temperature thermochronology. Geological Society of America Abstracts with Programs, 56(5). https://doi.
org/ I 0. l 130/abs/2024AM-402995 Arslan Azizoglu, G. (2024, September 17-18). Development of a microneedle patch for long-acting contraception
[Invited presentation]. Microneedle & IntradennaJ Delivery Forum 2024, Philadelphia, PA, USA.
Augustine, V., et al. (2024). Molten salt synthesis of transition metal and lanthanide nitride surrogates for actinide nitride fuels. ANS Transactions, 131, 550-553.
Bennett, S. E. K., Darin, M. H., Dorsey, R. J., Stelten, M. E.,
Sawlan, M. G., Hagstrum, J. T., Thompson, L.A.,
Gardner, K., Morebeck, C., & Switzer, B. (2024).
Geologia de la Sierra de San Jorge, margen occidental de la rift de) Golfo de California, peninsula central de Baja California, Mexico. GSA Connects 2024 Meeting, Anaheim, California, 22-25 September, Paper No. 94-9.
Brunig, D., Soreghan, G. S., DuUn, S., Thomson, S. N., & de Aguinaco, H. L. (2024). Exploring the buried bedrock surface ofUnaweep Canyon to assess landform origin. American Geophysical Union, Fall Meeting 2024, Abstract, Session EP13B-1337.
Cardello, G. L., Rahn, M., Fellin, G., Bernasconi, S.,
& Mancktelow, N. (9 November 2024). New geochronological constraints from the Simplon-Rh6ne Fault and the SW Helvetic nappes, Switzerland. Swiss Geoscience Meeting, S. 4.
Cherney, A. (2024, August). Alternative syntheses of metal ceramics for nuclear technologies. Contributed talk at the National Meeting of the American Chemical Society, Denver, CO.
Colburn, B., Hausrath, E. M., Cycil, L. M., Picard, A., Huang, S., & Duggan, B. (2025). Potential biosignatures in Mars-relevant clay minerals: A key to uncovering past life on Mars (Abstract #2574). In 56th Lunar and Planetary Science Conference (LPSC 2025). Lunar and Planetary Institute. https://www.hou.usra.edu/
meetings/lpsc2025/pdf/2574.pdf Dalton, H., et al. (2024). Isotopic fingerprinting of the Plio-Pleistocene Turkana Tuffs. Geological Society of America (GSA) Connects, Anaheim.
Dalton, H., et al. (2025). Assigning an eruption age: The challenges of dispersed single crystal Ar-Ar ages and insights from geochemistry. International Association of Volcanology and Chemistry of tJ1e Earth's Interior, Geneva.
Dalton, H., et al. (2025). Episodic eruptions in the Turka11a Basin, Kenya: An isotopic perspective. Goldschmidt, Prague.
Dimaggio, et al. (2024). Geochronol.ogy of Late Miocene Fossil Sites in the Southern Kenya Rift. American Geophysical Union Fall Meetjng. Retrieved from https:// agu.con fex.com/agu/agu24/ meeti nga pp.cgi/
Paper/ 1663185 Dorsey, R. J., Darin, M., Bennett, S. E. K., Hausback, B.,
Garner, K., Niemi, T., Busby, C., Graettinger, A.
H., Salgado Munoz, V. 0., Martinez Gutierrez, G.,
Morebeck, C., Usher, E., Heizler, M. T., Pecha, M. E.,
Stelten, M. E., Schmitt, A. K., & Dolby, G. (2024).
Miocene tectonic and stratigraphic evolution of the central Baja California peninsula and rapid marine flooding into the Gulf of California at ca. 6.3 Ma.
GSA Connects 2024 Meeting, Anaheim, CA, 22-25 September, Paper No. 72-13. (Invited Presentation)
Downs, D. T., Deligne, N. I., & Stelten, M. E. (2025). Volcanic mapping, geochemistry, and geochronology from caldera to coast within the American Samoa archipelago. American Geophysical Union Chapman Conference on Caldera-Forming Eruptions at Basaltic Volcanoes, Hilo, Hawaii, USA.
Evers, C., Park, J. G., Vondrasek, B., Johnson, C., Martin, T.,
Czabaj, M., Odegard, G., & Liang, R. (2025). Electron beam and gamma ray radiation treatments to achieve high strength in carbon nanotube laminates.
Proceedings of the International Conference on Composite Materials (ICCM 24), Baltimore, MD, August 4-8, 2025.
Finzel, E., Thomson, S. N., Pearson, D. M., Horkley, L. K.,
Garber, K., & Gardner, C. (2024). First cycle or polycyclic? Combining apatite and zircon detrital U-Pb geochronology and geochemistry to assess sediment recycling in the southwestern Montana foreland basin, North American Cordillera.
Geological Society of America Abstracts with Programs, 56(5). https:/ /doi.org/ 10.1130/
abs/2024AM-401321 l * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *
- 1* * * * * * *
- 1* *
- WORDS Flores, ). I., Witt, C., Poma, 0., Bruguier, 0., Bosch, D.,
Bosse, V., Zattin, M., Seyler, M., Hernandez, M. J.,
Chanier, F., & Averbuch, 0. (2025, April 27-May 2). Geochronology and geochemistry of Cenozoic magmatic intrusions in the north-western Ecuadorian Andes: 1l1e role of crustal thickness [Conference presentation]. EGU General Assembly, Vienna, Austria.
Franz, B., Geiger, H., Rahn, M., Todd, A., & Zwingmann, H. (9 November 2024). Age, origin and exhumation history of a Variscan djke aJong the Upper Rhine Graben Vosges shoulder. Swiss Geoscience Meeting, S. I 05.
Gibbs, T., & Cherney, A. T. (2024). Fluoride saJt separation of uranium from fission products. ANS Transactions, 131, 238-240.
Heberer, B., Rahn, M., Gerdes, A., Neubauer, F., Dunkl, I.,
Holzner, E., & Czepl, A. (23-27 September 2024).
Deciphering the 4-0 evolution along and across the Insubric Line using a multi-method geo-and thermochronological approach. Pangeo/DEUQUA,
- s. 74.
Jakobsson, V., et al. (2024, November). Tectonic implications of geological mapping and Rb-Sr isotopic dating for the timing and duration of the early Alpine top-to-the-W imbrication and exhumation of the Austroalpine-Pennine boundary region. Swiss Geoscience Meeting.
Jakobsson, V., et al. (2025, July). Assessing intragrain chemical heterogeneities in white mica and their impact on 40Ar/39Ar and Rb-Sr dates. Goldschmidt Geochemistry Conference, Prague.
Kapla11, M. R., Martini, M.A., Cunningham, M., Rupper, S.,
Thomson, S. N., Nobile, J.C., Flores, E., Romero, M., & Schaefer, J. M. (2024). Understanding glacial-geomorph ic-climatic changes in the arid Andes:
Cordillera Oriental as a case study. American Geophysical Union, Fall Meeting 2024, Abstract, Session EP23C-l 336.
Kelhofer, N., Arslan Azizoglu, G., Zheng, T., Dalvi, A.,
Schwendeman, S. P., & Prausnitz, M. R. (2025, January). 6-month sustained contraceptive delivery from a gamma-sterilized microneedle patch [Poster presentation, recipient of 2nd place award]. MEdX at Carle Illinois.
McGlamery, D., et al. (2024). Molten salt synthesis of functional carbide materials. ANS Transactions, 131, 554-557.
Mouthereau, F., Boschetti, L., Schwartz, S., Rolland, Y.,
Bernet, M., Cogne, N.,... (2025). Evolution of the Iberia-Adria-Europe plate boundary revealed by the Meso-Cenozoic thermal history of the European paleomargin in SE FraJ1ce. European Geosciences Union General Assembly 2025 (EGU25), EGU25-16940.
Phillips, D., et al. (2024). High precision 40Ar/39Ar dating of Pliocene Turkana Tuffs. Geological Society of America (GSA) Connects, Anaheim.
Phillips, D., ct al. (2025). Unravelling the PHo-Pleistocene history of the paleontologically significant Turkana Basin, Kenya. Goldschmidt, Prague.
Pomella, H. (2024, September 18). The complex thermotectonic history of the Eastern Southern Alps [Conference presentation]. 16th Emile Argand Conference on Alpine Geological Studies, Siena, Italy. Co-authors:
Klotz, T., Sieberer, A.-K., & Dunk!, I.
Pomella, H. (2024, September 26). The Subpenninic unHs in the western Tauern Window [Conference presentation]. Pangeo / DEUQUA 2024, Salzburg, Austria. Co-authors: Hinterwirth, S., Rudmann, J., &
Burger, U.
Samim, S., et al. (2024). Unravelling stratigraphic complexities in the Nariokotome Tuff Complex using a combination of high-resolution tephrochronological tools. Geological Society of An1erica (GSA) Connects, AJ1aheim.
Samim, S., et al. (2025). Contrasting styles of silicic magma mixing dynamics in Turkana Basin, Kenya: Insights from high-resolution tephrochronological tools.
International Association of Volcanology and Chemistry of the Earth's Interior, Geneva.
Samim, S., et al. (2025). High-resolution tephrochronological tools reveal geochemical complexity in volcanic products: Examples from the Turkana Basin, Kenya.
Goldschmidt, Prague.
Savelkouls, A., et al. (2024). High-resolution stratigraphy and 40Ar/39Ar geochronology of the Okote Tuff Complex.
Geological Society of America (GSA) Connects, Anaheim.
Savelkouls, A., et al. (2025). Application of tephrochronology in the Omo-Turkana Basin; using 40Ar/39Ar-geochronology to develop a high-resolution stratigraphic framework for the Okote Tuff Complex.
International Association ofVolcanology and Chemistry of the Earth's Interior, Geneva.
WORDS Siddoway, C. S., Thomson, S. N., Hemming, S. R., &
Brachfeld, S. A. (2024). Multichronometer dating of drops tones and ice-rafted debris (latest Miocene through Pliocene) recovered from IODP drill cores offshore West Antarctica, to extend knowledge of bedrock geology and past ice sheet extent. American Geophysical Union, Fall Meeting 2024, Abstract, Session T51D-3l 77.
Siddoway, C. S., Thomson, S. N., Taylor, J.M., &Teyssier, C.
P. (2025, September 14-20). Thermochronology of glacially transported clasts from the marine shelf and slope of West Antarctica (Marie Byrd Land/
Amundsen Sea). Thermo2025, 19th International Conference on Thermochronology, Kanazawa, Japan.
Singer, B. S. (2024, September 13). The Quaternary Southern Andean Volcanic Zone: Geologic, geochronologic, and petrologic perspectives. Fulbright Scholar Orientation, Fulbright Chile Office, Las Condes/
Santiago, Chile.
Taylor, J. M., Siddoway, C. S., Thomson, S. N., & Teyssier, C.
(2024). Differential exhumation in western Marie Byrd Land, West Antarctica, exposed through low-temperature thennochronology and thermo-kinematic modeUng. Geological Society of America Abstracts with Programs, 56(5). https://doi.
org/ l O. l l 30/abs/2024AM-4034 73 Volcanic and Magmatic Studies Group. (n.d.). A critical appraisal of the interrogation of sedimentary archives to investigate the proposed forcing of drainage network reorganisation by plateau uplift in Southeast Tibet. Poster presentation at EGU.
Volcanic and Magmatic Studies Group. (n.d.). Dating recent aqueous activity on Mars. Poster presentation at A.GU.
Volcanic and Magmatic Studies Group. (n.d.). Eruption history of the Columbia River Basalt Group constrained by high-precision U-Pb and 40Ar/39Ar geochronology.
Poster presentation at GSA.
Volcanic and Magmatic Studies Group. (n.d.). Progress on supergene mineral datfag via the 40Ar/39Ar technique and terrestrial weathering in Great Britain and Ireland. Poster presentation at the Geological Society of London: Chemical Weathering & Climate Change Conference.
Volcanic and Magmatic Studies Group. (n.d.). v\/here did the ice reach the sea? The utility of coupled K-feldspar Rb-Sr, Ar-Ar, and Pb-isotope analysis applied to mid-Miocene ice-rafted debris in Antarctic marine sediment. Poster presentation at EGU.
Werth, C. /., Berns, E. C., Kearney, K., You, X., Sanford, R.
A., Valocchi, A. J., Strathmann, T. J., & Schaefer, C. E. (2022, October 4-6). Iron cycling and the role of reduced iron species in promoting abiotic transformations of chlorinated ethenes in groundwater. REMTEC and Emerging Contaminants Summit, Denver, CO.
Students Andersen, Rohan. MS, University of Melbourne.
"Geochemistry and age oftbe Si Ibo Tuff, Turkana Basin." Advisor(s): Hayden Dalton, Saini Samim.
Boschetti, L. Ph.D. student. Advisors: Frederique Moutherau (Toulouse), Stephane Schwartz (Grenoble), Yann Rolland (Chambery).
Chai id, lntan. PhD student, Vrijc Un.iversiteit Amsterdam.
Chen, Jonathan. PhD candidate, University of Illinois Urbana-Champaign. "Development and clinical translation ofmicroneedle patches for long-term contraception and cystic fibrosis diagnosis." Supervisor: Mark Prausnitz.
Chibuko, Chizimuzo. PhD candidate, University of Illinois Urbana-Champaign. "Effects ofmicroneedle design and sk.in physiology on interstitial fluid collection."
Supervisor: Mark Prausnitz.
Colburn, Baylee. PhD, Geoscience Department, University of Nevada Las Vegas. "Seeking signs oflife on Mars."
Advisor: Prof. Elisabeth Hausrath.
Conde, Camilo. MSc student. "Geochronological and Geochemical Characterisation of the Quebradagrande Complex, Colombia" Advisor: Richard Spikings.
Coudun, Charline. Ph.D. student. Advisor(s): Christophe Basile.
Craig, Jason. PhD student, Stanford University. "Ancient and active tectonics of Arctic Alaska: Structural framework of the south-central Brooks Range and geoi.hennal potential of the Kigluaik Mountains, Seward Peninsula." Advisor: Elizabeth Miller.
Expected completion: Dec. 2025.
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"Quantifying the distribution ofabiotic transformation rate constants in low penneability clay zones for improved assessment ofTCE impacts to groundwater at DoD field sites."
Drayson, D. PhD, Department of Earth Sciences, University of Manitoba. "Isotopic and Petrologic Constraints on lntracontinental Deformation and Metamorphism, Churchill Province, Nunavut." Advisor: A. Camacho.
Fioraso, Marco. PhD student, Department, University of Siena. "Erosion Antarctica: Looking into erosional processes and uplifting of the Transantarctic Mountains (Southern Victoria Land) through low-temperature thermochronology and numerical modeling of landscape evolution." Advisor(s): Dr.
Valerio Olivetti.
1-Iuseynov, Akbar. PhD student, Vrije Universiteit Amsterdam.
Iglesias Flores, Jorge Andres. PhD student, University of Lille.
"Arc-forearc interactions in the Northern Peruvian Andes." Advisor(s): Prof. Massimiliano Zattin.
Jakobsson, Vidar. PhD student. "Assessing the mechanisms of Ar redistribution and loss from white mica." Advisor:
Richard Spikings.
Martinez, Eduardo. PhD, Geoscience Department, University of Nevada Las Vegas. "Phosphate and implications for Mars." Advisor: Prof. Elisabeth Hausrath.
Moreno-Yaeger, Pablo. PhD student, Department of Geoscience, University of Wisconsin-Madison.
Advisor: Brad Singer.
Okyere, Lydia. PhD, Department of Pathobiology (Veterinary Medicine), University oflllinois Urbana-Champaign.
"Microbiome-Mediated Modulation of Herbicide Toxicity and Host Detoxification Pathways."
Advisor: Prof. Christopher Gaulke.
Rosenberger, A. PhD student, Washington State University.
Advisor: Prof. Sean Long. Collaborating with the University of Arizona Fission Track Laboratory as part of the NSF AGcS2 Program.
Samim, Saini. PhD, University of Melbourne.
"Geochronology and Geochemistry ofNachukui Tuffs, Omo-Turkana Basin, Kenya." Advisor(s):
David Phillips, Janel Hergt, Hayden Dallon.
Sandoval Espinel, Leidy Carolina. PhD student, University of Pad ova. "Thermolectonic history of the southenunost Northern Andes." Advisor: Prof. Massimiliano Zattin.
Savelkouls, Ashley. PhD, University of Melbourne.
"Constraining the volcanic-magmatic history of the Koobi Fora Fonnation in the Omo-Turkana Basin using precise 40Ar/39Ar dating to improve the current stratigraphy." Advisor(s): David Phillips, I layden Dalton.
Shang, Shij ie. PhD student, Yrije Universiteil Amsterdam.
Sta Ila, Jack. MS student, Department of Geoscience, University of Wisconsin-Madison. Advisor: Brad Singer.
van den Bosch, Thomas. MS student, Vrije Universileit Amsterdam.
Wu, Yang. PhD student, Vrije Universiteit Amsterdam.
Zhang, Dongdong. PhD student, University of Padova.
"Anthropogenic impact on sediment transfer in the Yellow River catchment detected by delrital geochronology." Advisor: Prof. Massimiliano Zattin.
Zhang, Liying. PhD student, China University ofGeosciences, Beijing. "Tectonic evolution of the Great Xing'an Range and its relationships with climatic and surface processes." Advisor(s): Prof. Massimiliano Zattin.
Zhou, Wei. MSD student. "Cenozoic initial widespread uplift of the Eastern Kunlun Mountains as constrained by low-temperature thern1ochronology." Advisor:
Associate Professor Yadong Wang.
WORDS
Oregon State University Radiation Center, 100 Radiation Center, Corvallis, OR 97331 www.radiationcenter.oregonstate.edu
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