ML23304A070
| ML23304A070 | |
| Person / Time | |
|---|---|
| Site: | Oregon State University |
| Issue date: | 10/26/2023 |
| From: | Reese S Oregon State University |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| Download: ML23304A070 (1) | |
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Oregon State 9 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 26, 2023
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 Oregon State University Radiation Center and OSTR Annual Report for the period July 1, 2022 through June 30, 2023.
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 /i~ /2.,
Sincerely,
~
Steven R. Reese Director Cc:
Michael Balazik, USNRC Andrew Waugh, USN RC Maxwell Woods, ODOE Dr. lrem Turner, OSU Dan Harlan, OSU
1*
I
- JULY I, 2022 - JUNE 30, 2023
- E RADIATION CENTER and TRIGA REACTOR
- ANNUAL REPORT a Or~go~State
'91 Uruvers1ty
1: * * * * * * * * * * *
- Submitted by:
Steve R. Reese, Director Radiation Center Oregon State University Corvallis, Oregon 97331-5903 Telephone: (541) 737-2341 Fax: (541) 737-0480 To satisy 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.
Con_ten_ts 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 Professional & Research Faculty.............................................................................................................. 7 Part Ill-Facilities Research Reactor.......................................................................................................................................... 8 Analytical Equipment.................................................................................................................................. 9 Radioisotope Irradiation Sources............................................................................................................ 9 Laboratories & Classrooms...................................................................................................................... 1 O Instrument Repair & Calibration............................................................................................................ 10 Part IV-Reactor Operating Statistics.................................................................................................................................... 12 Experiments Performed........................................................................................................................... 12 Unplanned Shutdowns............................................................................................................................. 13 Activities Pursuant to 10 CFR 50.59...................................................................................................... 13 Surveillance & Maintenance................................................................................................................... 14 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 & Service..................................................................................................................................... 46 Part VII-Words Documents Published or Accepted..................................................................................................... 70 Presentations................................................................................................................................................ 71 Students......................................................................................................................................................... 73
I Tables Table Title Page 111.1 Gammacell 220 60Co lrradiator Use............................................ 11 IV.1 Present OSTR Operating Statistics............................................ 15 IV.2 OSTR Use Time in Terms of Specific Use Categories.................................. 16 IV.3 OSTR Multiple Use Time................................................... 16 IV.4 Use of OSTR Reactor Experiments............................................ 17 IV.5 Unplanned Reactor Shutdowns and Scrams...................................... 17 V.1 Radiation Protection Program Requirements and Frequencies.......................... 30 V.2 Monthly Summary of Liquid Effluent Releases to the Sanitary Sewer...................... 31 V.3 Annual Summary of Liquid Waste Generated and Transferred........................... 32 V.4 Monthly Summary of Gaseous Effluent Releases................................... 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 Within the TRIGA Reactor Facility....................... 35 V.8 Total Dose Equivalent Recorded on Area Within the Radiation Center...................... 36 V.9 Annual Summary of Radiation and Contamination Levels Within the Reactor................. 38 V.10 Total Dose Equivalent at the TRIGA Reactor Facility Fence............................. 39 V.11 Total Dose Equivalent at the Off-Site Gamma Radiation Monitoring Stations................. 40 V.12 Annual Average Concentration of the Total Net Beta Radioactivity........................ 41 V.13 Radioactive Material Shipments under NRC General License R-106....................... 42 V.14 Radioactive Material Shipments under Oregon License ORE 90005....................... 43 V.15 Radioactive Material Shipments Under NRC General License 1 O CFR 110.23................. 43 Vl.1 Institutions and Agencies Which Utilized the Radiation Center.......................... 48 Vl.2 Listing of Major Research & Service Projects Performed and Their Funding.................. 52 Vl.3 Summary of Radiological Instrumentation Calibrated to Support OSU Departments............ 69 Vl.4 Summary of Radiological Instrumentation Calibrated to Support Other Agencies............. 69 Figures Table Title Page IV.1 Monthly Surveillance and Maintenance (Sample Form)................................................................................................. 18 IV.2 Quarterly Surveillance and Maintenance (Sample Form)............................................................................................... 19 IV.3 Semi-Annual Surveillance and Maintenance (Sample Form)........................................................................................ 20 IV.4 Annual Surveillance and Maintenance (Sample Form)................................................................................................... 22 V.1 Monitoring Stations for the OSU TRIGA Reactor............................................................................................................. 45 Vl.1 Summary of the Types of Radiological Instrumentation Calibrated.......................................................................... 69
Overview Executive Summary The data from this reporting year shows that the use of the Radiation Center and the Oregon State TRI GA reactor (OSTR) has returned to pre-COVID levels accross nearly every metric.
Of the work performed, eighty-seven percent (87%) of the OSTR research hours were in support of off-campus research projects, reflecting the use of the OSTR nationally and inter-nationally. Radiation Center users published or submitted 24 articles this year, and made 23 presentations on work that in-volved the OSTR or Radiation Center. The number of samples irradiated in the reactor during this reporting period was 2,454.
Funded OSTR use hours comprised 80% of the research use.
Persom1el at the Radiation Center conducted 169 tours of the facility, accommodating 2,023 visitors. The visitors included elementary, middle school, high school, and college students; relatives and friends; faculty; current and prospective clients; national laboratory and industrial scientists and engineers; and state, federal and international officials. The Radiation Center is a significant positive attraction on campus because visitors leave with a good impression of the facility and of Oregon State University.
The Radiation Center projects database continues to provide a useful way of tracking the many different aspects of work at the facility. The number of projects supported this year was 158. Reactor related projects comprised 76% of all projects.
The total research dollars in some way supported by the Radia-tion Center, as reported by our researchers, was $1 1 million.
The actual total is likely higher. This year the Radiation Center provided service to 58 different organizations/institutions, 40%
of which were from other states and 47% 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 interna-tional clientele.
The Radiation Center web site provides an easy way for po-tential 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.
4 Introduction The current annual report of the Oregon State University Radiation Center and TRI GA Reactor follows the usual for-mat by including information relating to the entire Radiation Center rather than just the reactor. However, the information is still presented in such a manner that data on the reactor may be examined separately, if desired. It should be noted that all annual data given in this report covers the period from July 1, 2022 through June 30, 2023. 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 information about the activi-ties of the Radiation Center, this report is designed to meet the reporting requirements of the U.S. Nuclear Regulatory Com-mission, 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.
ANNUAL REPORT
OVERVIEW 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 orga-nizations throughout the nation and the world. The Center also regularly provides special services to state and federal agencies, particularly agencies dealing with law enforce-ment, 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 ofNuclear Science and Engineering, the OSU Institute ofNuclear Science and Engineering, and for the OSU nuclear chemistry, radiation chemistry, geochemis-try 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 special-ized equipment and unique teaching and research facilities.
They include a TRI GA Mark II research nuclear reactor; a 60Co gamma irradiator; a large number of state-of-the art computer-based gamma radiation spectrometers and as-sociated high purity germanium detectors; and a variety of instruments for radiation measurements and monitoring.
Specialized facilities for radiation work include teaching and research laboratories with instrumentation and related equip-ment for performing neutron activation analysis and radio-tracer studies; laboratories for plant experiments involving radioactivity; a facility for repair and calibration of radiation protection instrumentation; and facilities for packaging ra-dioactive materials for shipment to national and international destinations.
Also housed in the Radiation Center is the Advanced Ther-mal Hydraulics Research Laboratory (ATHRL), which is used for state-of-the-art two-phase flow experiments. Within ATHRL is located the NuScale Integral Systems Test-2 (NIST-2) facility is 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 2022-2023 transfer performance, and 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 thermal-hydraulic test facilities-the High Temperature Test Facility (HTTF) and the Hydro-mechanical Fuel Test Facility (HMFTF). The HTTF 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 l.0MPa and a maximum core ceramic temperature of 1600°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 HTTF can be used to simulate a wide range of accident scenarios in gas reac-tors 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 qualifica-tion of the prototypic ultrahigh density U-Mo Low Enriched Uranium fuel which will be implemented into the U.S. High Performance Research Reactors upon their conversion to low enriched fuel. This data in turn will be used to verify current 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 tem-perature of 450°F.
The Radiation Center staff regularly provides direct sup-port 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, ra-diation dosimetry, environmental radioactivity, production of short-lived radioisotopes, radiation shielding, nuclear instru-mentation, emergency response, transportation of radioactive materials, instrument calibration, radiation health physics, radioactive waste disposal, and other related areas.
In addition to formal academic and research support, the Center's staff provides a wide variety of other services includ-ing public tours and instructional programs, and professional consultation associated with the feasibility, design, safety, and execution of experiments using radiation and radioactive materials.
5
People This section contains a listing 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 information 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 Steve Reese, Director Dina Pope, Office Manager Matthew Berry, Business Manager Erica Emerson, Receptionist Celia Oney, Reactor Supervisor, Senior Reactor Operator Robert Schickler, Reactor Administrator/Assistant Direc-tor, Senior Reactor Operator Scott Menn, Senior Health Physicist Taighlor Story, Health Physicist Leah Mine, Neutron Activation Analysis Manager Steve Smith, Development Engineer, Senior Reactor Operator Chris Kulah, Senior Reactor Operator Dan Sturdevant, Custodian Emory Colvin, Reactor Operator (Student)
Maren Arneson, Reactor Operator (Student)
Angelo Camargo, Reactor Operator (Student)
Nathaniel McNichols, Reactor Operator (Student)
Paul Sprague, Reactor Operator (Student)
Tracey Spoerer, Senior Reactor Operator (Student)
Zane Tucker, Reactor Operator (Student)
Nathan Wiltbank, Reactor Operator (Student)
Quinton Williams, Reactor Operator (Student)
Triton DeSilva, Health Physics Monitor (Student)
Brandon Farjardo, Health Physics Monitor (Student)
Nicolaas VanDerZwan, Health Physics Monitor (Student)
Reactor Operations Committee Dan Harlan, Chair OSU Radiation Safety Leo Bobek UMass Lowell Samuel Briggs OSU School of uclear Science and Engineering Abi Tavakoli Farsoni OSU School of uclear Science and Engineering Scott Menn OSU Radiation Center Celia Oney (not voti11g)
OSU Radiation Center Steve Reese (not voting)
OSU Radiation Center Robert Schickler OSU Radiation Center Julie Tucker OSU Mechanical, Industrial and Manufacturing Engineering Haori Yang OSU School of Nuclear Science and Engineering 1---------------------------------------
6 ANNUAL REPORT
- PEOPLE Professional and Research Faculty Samuel Briggs Assitant Professor, Nuclear Science and Engineering Alexander Chemey Assistant Professor, Nuclear Science and Engineering Tianyi Chen Assistant Professor, Nuclear Science and Engineering Abi Farsoni Associate Professor, Nuclear Science and Engineering Jzabela Gutowska Assistant Professor, Senior Research, Nuclear Science and Engineering David Hamby Professor Emeritus, Nuclear Science and Engineering Kathryn Higley School Head, Professor, Nuclear Science and Engineering Trevor Howard Assistant Professor, Senior Research, Nuclear Science and Engineering Walter Loveland Professor, Chemistry 2022-2023 Wade Marcum Senior Associate Dean, College of Engineering Professor, Nuclear Science and Engineering Mitch Meyer Professor of Practice, Nuclear Science and Engineering Scott Menn Senior Health Physicist, Radiation Center LeahMinc Associate Professor, Anthropology Guillaume Mignot Assistant Professor, Senior Research, Nuclear Science and Engineering Celia Oney Reactor Supervisor, Radiation Center Alena Paulenova Professor, Nuclear Science and Engineering Dina Pope Office Manager, Radiation Center Leila Ranjbar Instructor, Nuclear Science and Engineering Steven Reese Director, Radiation Center Associate Professor, Nuclear Science and Engineering Robert Schickler Reactor Administrator/ Assistant Director, Radiation Center Aaron Weiss Sr. Faculty Research Assistant, Nuclear Science and Engineering Qiao Wu Professor, Nuclear Science and Engineering Haori Yang Associate Professor, Nuclear Science and Engineering 7
Facilities Research Reactor The Oregon State University TRIGA 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-foot deep water-filled tank, and the tank is surrounded by a concrete bioshield which acts as a radiation shield and structural support. The reactor is li-censed by the U.S. Nuclear Regulatory Commission to operate at a maximum steady state power of 1.1 MW and can also be pulsed up to a peak power of about 2500 MW.
The OSTR has a number of different irradiation facilities including a pneumatic transfer tube, a rotating rack, a thermal colwnn, 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 experi-ments 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 radionu-clides. 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 reac-tor core in order to increase thermal neutron activation of samples. Over 99% of the neutrons in the thermal column are thermal neutrons. Graphite blocks are removed from the thermal column to enable samples to be positioned inside for irradiation.
The beam po1is 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 re-moved. 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.
8 If samples irradiated require a large neutron fluence, especially from higher energy neutrons, they may be placed in the in-core irradiation tube (ICIT), located in one of several in-core lattice positions.
The cadmium-lined in-core irradiation tube (CLICIT) enables samples to be irradiated in a high flux region near the center of the core. The cadmium lining in the facility elimi-nates 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 oc-cupied by a fuel element. It is the same as the ICIT except for the presence of the cadmium lining.
ANNUAL REPORT
FACILITIES Instructional Uses of the OSTR Instructional use of the reactor is twofold. First, it is historical-ly used for classes in Nuclear Engineering, Radiation Health Physics, and Chemistry at both the graduate and undergradu-ate levels to demonstrate numerous principles which have been presented in the classroom. Basic neutron behavior is the same in small reactors as it is in large power reactors, and many demonstrations and instructional experiments can be performed using the OSTR which cannot be carried out with a commercial power reactor. Shorter-term demonstration experi-ments are also performed for many undergraduate students in Physics, Chemistry, and Biology classes, as well as for visitors from other universities and colleges, from high schools, and from public groups.
The second instructional application of the OSTR involves 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 pro-vides 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 instrumental neutron activation analysis (INAA). This is a particularly sensitive method of elemental analysis which is described in more detail in Part VI.
The OSTR's irradiation facilities provide a wide range of neutron flux levels and neutron flux qualities which are suf-ficient 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.
2022-2023 Analytical Equipment The Radiation Center has a large variety of radiation detec-tion instrumentation. This equipment is upgraded as neces-sary, especially the gamma ray spectrometers with their associated computers and germanium detectors. Additional equipment for classroom use and an extensive inventory of portable radiation detection instrumentation are also avail-able.
Radiation Center nuclear instrumentation receives intensive e 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 of Radiation 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 6°Co irradiator which is capable of delivering high doses of gamma radiation over a range of dose rates to a variety of materials.
Typically, the irradiator is used by researchers wishing to perform mutation and other biological effects studies; studies in the area of radiation chemistry; dosimeter testing; steril-ization of food materials, soils, sediments, biological speci-men, and other media; gamma radiation damage studies; and other such applications. In addition to the 6°Co irradiator, the Center is also equipped with a variety of smaller 60Co, 137Cs, 226Ra, plutonium-beryllium, and other isotopic sealed sources of various radioactivity levels which are available for use as irradiation 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 materials including dif-ferent types of seeds.
In addition, the irradiator was used for sterilization of several media and the evaluation of the radiation effects on different materials. Table 111.1 provides use data for the Gammacell 220 irradiator.
9
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 aca-demic departments or off-campus groups.
Instructional facilities available at the Center include a labo-ratory especially equipped for teaching radiochemistry and a nuclear instrumentation teaching laboratory equipped with modular sets of counting equipment which can be configured to accommodate a variety of experiments involving the mea-surement of many types ofradiation. The Center also has two student computer rooms.
In addition to these dedicated instructional facilities, many other research laboratories and pieces of specialized equip-ment are regularly used for teaching. In particular, classes are routinely given access to gamma spectrometry equipment located in Center laboratories. A number of classes also regu-larly use the OSTR and the Reactor Bay as an integral part of their instructional coursework.
There are two classrooms in the Radiation Center which are capable of holding about 35 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 IIl.2.
10 Instrument Repair & Calibration Facility The Radiation Center has a facility for the repair and calibra-tion of essentially all types of radiation monitoring instru-mentation. 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 es-sentially all radiation detection instruments used by state and federal agencies in the state of Oregon. This includes instru-ments 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 Commis-sion, the Oregon Health and Sciences University, the Army Corps of Engineers, and the U.S. Environmental Protection Agency.
ANNUAL REPORT
FACILITIES Purpose of Irradiation Sterilization Material Evaluation Biological Studies Botanical Studies Dosimeter Analysis Totals 2022-2023 Table 111.1 Gammacell 220 6°Co lrradiator Use Samples Dose Range (rads) wood blocks, soil, chitosan, medical devices, nanofibers, l.5xl06 to 5.0x106 leaves, liriope seeds carbon nanotubes 2.0x l07 to l.2x108 mice 5.0xl02 to 9.0xl02 plant material 2.0xl03 to 6.0xl03 dosimeter materials 3.0xl05 to 4.0xl06 Number of Use Time Irradiations (hours) 50 615.84 3
547.35 5
0.01 5
0.07 10 84.99 73 1,247.6 11
Reactor Operating Statistics During the operating period between July 1, 2022 and June 30, 2023, the reactor produced 1,084 MWH of thermal power during its 1,106 critical hours.
Experiments Performed During the current reporting period there were 5 approved reactor experiments available for use in reactor-related pro-grams. They are:
A-1 Normal TRIGA Operation (No Sample Irradiation).
B-3 Irradiation of Materials in the Standard OSTR Ir-radiation Facilities.
B-29 Reactivity Worth ofFuel.
B-31 TRIGA Flux Mapping B-36 Irradiation of fissionable materials in the OSTR.
Of these available experiments, three were used during the reporting period Table IV.4 provides information related to the frequency of use and the general purpose of their use.
Inactive Experiments Presently 39 experiments are in the inactive file. This con-sists 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 Activa-tion.
A-3 Measurement of Cd Ratios for Mn, In, and Au in Rotating Rack.
A-4 Neutron Flux Measurements in TRIGA.
A-5 Copper Wire Irradiation.
A-6 In-core Irradiation ofLiF Crystals.
A-7 Investigation ofTRIGA's Reactor Bath Water Tem-perature Coefficient and High Power Level Power Fluctuation.
12 B-1 Activation Analysis of Stone Meteorites, Other Mete-orites, and Terrestrial Rocks.
B-2 Measurements of Cd Ratios of Mn, In, and Au in Thermal Column.
B-4 Flux Mapping.
B-5 In-core Irradiation of Foils for Neutron Spectral Mea-surements.
B-6 Measurements of Neutron Spectra in External Irradia-tion Facilities.
B-7 Measurements of Gamma Doses in External Irradia-tion Facilities.
8-8 Isotope Production.
B-9 Neutron Radiography.
B-10 Neutron Diffraction.
B-11 Irradiation of Materials Involving Specific Quantities of Uranium and Thorium in Standard OSTR Irradia-tion Facilities. (Discontinued Feb. 28th, 2018)
B-12 Exploratory Experiments. (Discontinued Feb. 28th, 2018)
B-13 This experiment number was changed to A-7.
B-14 Detection of Chemically Bound Neutrons.
B-15 This experiment number was changed to C-1.
B-16 Production and Preparation of 18F.
B-17 Fission Fragment Gamma Ray Angular Correlations.
B-18 A Study of Delayed Status (n, y) Produced Nuclei.
B-19 Instrument Timing via Light Triggering.
B-20 Sinusoidal Pile Oscillator.
B-21 Beam Port #3 Neutron Radiography Facility.
B-22 Water Flow Measurements Through TRIGA Core.
B-23 Studies Using TRIGA Thermal Column. (Discontin-ued Feb. 28th, 2018)
B-24 General Neutron Radiography.
B-25 Neutron Flux Monitors.
B-26 Fast Neutron Spectrum Generator.
B-27 Neutron Flux Determination Adjacent to the OSTR Core.
ANNUAL REPORT
REACTOR B-28 Gamma Scan of Sodium (TED) Capsule.
B-30 NAA of Jet, Diesel, and Furnace Fuels.
B-32 Argon Production Facility.
B-33 Irradiation of Combustible Liquids in LS. (Discon-tinued Feb. 28th, 2018).
B-34 Irradiation of Enriched Uranium in the Neutron Ra-diography Facility. (Discontinued Feb. 28th, 2018).
B-35 Irradiation of Fissile Materials in the Prompt Gamma Neutron Activation Analysis (PGNAA)
Facility. (Discontinued Feb. 28th, 2018).
C-1 PuO2 Transient Experiment.
Unplanned Shutdowns There were 5 unplanned reactor shutdowns during the current reporting period. Table IV.5 details these events.
Activities Pursuant to10 CFR 50-59 There was one safety evaluation performed in support of the reactor this year. It was:
23-01 Beam Port #4 Decommissioning Removed all parts of the PGNAA facility and removed the collima-tor from Beam Port #4, then installed concrete and polyethylene shielding plugs and the beam port door.
There were 15 new screens performed in support of the reac-tor this year. They were:
22-10 Revisions ofOSTROPs (New Tech Specs for IFE Removal)
Revisions to OSTROPs 4, 5, 6, 7, 10, 15, 16, and 25 to be consistent with the new amendment to Technical Specifications, including re-moval of all requirements related to the Instrumented Fuel Element.
22-11 Revisions to Safety and Log/Linear Channels in Support of Pulse and Square-Wave Mode Operation Adjusted electronics in the log/linear channel period circuit to im-prove performance during square waves, and adjusted electronics in the safety channel to improve performance following pulses.
22-12 Revisions to OSTROPs 4, 10, 18, 18 Appendix A Minor updates and revisions to the procedures for reactor opera-tions, operation of experimental facilities, approval of experiments, and irradiation requests.
2022-2023 22-13 Revisions to OSTROPs 12, 16 Minor updates and revisions to the procedures for control rod mainte-nance and for annual surveillance and maintenance.
22-14 Revisions to OSTROP 11 and 16 for Fuel Inspections Updates to the fuel handling procedure and to the fuel inspection section of the annual surveillance and maintenance procedure.
23-01 Revisions to RCHPPs 8, 16, 21, and 24 Minor updates and revisions to the procedures for water analysis, leak testing, gamma irradiator, and radiation surveys.
23-02 Installation of Air Line on North Side of Bioshield Installed an air line near Beam Port # 1 to support a shutter that will be added to that facility.
23-03 Revisions to OSTROPs 2, 3, 16, and 31 Minor updates and revisions to the procedures for startup and shutdown checklists, annual surveillance and maintenance, and archival storage of documents.
23-04 ERIP Name Changes Updated names in the Evacuation and Notification tabs to reflect recent staffing changes.
23-05 Addendum to Evaluation 23-01 Update to the evaluation for Beam Port #4 decommissioning following completion of that work. Incldes exact measurements of component dimensions that were estimated in the evaluation.
23-06 Installation of PGNAA Equipment in Beam Port #1 Removed inner and outer beam plugs from Beam Port #1 and installed the PGNAA collimator that had been in Beam Port #4. Installed the pneumatic shutter and connected it to the air line, then installed borated poly shielding material and the beam stop.
23-07 New Stepper Motor for Regulating Rod Installed a new stepper motor for the regulating rod.
23-08 Cancellation of RCHPP 35 Cancelled the procedure for beta irradiation with the strontium-90 source, which is no longer in use.
23-09 Adjustment to Control Rod Drives Modified the linkage and set screws in the safety and shim rod limit switches to reduce likelihood of switch misalignment after SCRAMs.
23-10 Addendum to Screen 23-09 Clarified the work described in 23-09, and added the same modification on the regulating rod.
13
REACTOR Surveillance and Maintenance Non-Routine Maintenance July 2022 Replaced the weather monitor on the reactor building roof.
Cleaned the rotating rack by filling it with Simple Green, scrubbing the sample positions, then rinsing with water.
Then applied lubricating oil.
August 2022 Replaced a faulty diode in the safety channel to prevent non-op SCRAMs from occurring when in pulse mode.
Installed new weather instrumentation in the control room.
Modified console electronics to improve performance in pulse and square wave modes.
September 2022 Cleaned the rotating rack sample positions using towels dipped in acetone.
October 2022 Moved the ventilation supply fan flow sensor to a different location to reduce false alarms.
November 2022 Replaced the CAM/Stack/Weather instrumentation re-corder with a new model.
December 2022 14 Replaced a fried wire connection in the bulk shield tank pump.
January 2023 Cleaned the rotating rack with acetone again.
March 2023 Replaced solenoid valve and associated tubing and fittings on the Neutron Radiography Facility.
Removed the collimator from Beam Port #4 and installed concrete and poly beam port plugs.
Replaced the pre-resin filter on the demineralizer system.
April 2023 Installed a new air line on the north side of the bioshield for future use when an irradiation facility is constructed for Beam Port # 1.
Removed the door, lead shutter, poly plug, and concrete plug from Beam Port #1 and installed the collimator, shut-ter, borated poly shielding, and bioshield that had been on Beam Port #4.
Replaced the post-resin filter on the demineralizer system.
May 2023 Disassembled the darkroom that had been installed in the bay for N-Ray Services.
Replaced the GM detector for the primary water activity monitor.
June 2023 Modified the set screws on the rod down limit switches for the safety, shim, and regulating rods.
ANNUAL REPORT
REACTOR Table IV.1 Present OSTR Operating Statistics I
- Operational Data For LEU Core MWH of energy produced MWD of energy produced Grams 235U used Number of fuel elements added to ( +) or removed(-) from the core Number of pulses Hours reactor critical Hours at full power ( 1 MW)
Number of startup and shutdown checks Number of irradiation requests processed Number of samples irradiated 2022-2023 Annual Values (2022/2023) 1,084 45.2 60 0
99 1,106 1,045 246 255 2,454 Cumulative Values 18,739 780.8 1,071 91 424 19,984 18,584 3,366 3,561 28,767 15
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) 54 13,873 OSU research 659 26,010 Off campus research 1,764 63,631 Facility time 20 7,950 Total Reactor Use Time 2,497 111,464 Table IV.3 OSTR Multiple Use Time Number of Users Annual Values (hours)
Cumulative Values (hours)
Two 245 12,414 Three 242 7,068 Four 87 3,854 Five 61 1,673 Six 25 565 Seven I
177 Eight or more 0
29 Total Multiple Use Time 661 25,780 16 ANNUAL REPORT
REACTOR 1
Table IV.4 Use of OSTR Reactor Experiments Experiment Research Teaching Facility Use Total Number A-1 0
4 8
12 B-3 232 6
4 242 B-11 0
0 0
0 B-29 0
0 0
0 B-36 I
0 0
1 Total 233 10 12 255 Table IV.5 Unplanned Reactor Shutdowns and Scrams Type of Event Percent Power SCRAM Manual SCRAM Safety Power SCRAM Safety Power SCRAM Safety and Percent Power SCRAM 2022-2023 Number of Cause of Event Occurrences 1
Power reading fluctuations from rotating rack samples 1
Response to Stak & CAM alarm 1
Excessive rod withdrawal on startup 1
Operator error during shutdown 1
Operator error during square wave 17
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OSTROP 13, Rev. LEU-10 Surveillance & Maintenance for the Month of in the year of 20 _
SURVEILLANCE & MAINTENANCE TARGET DATE DATE REMARKS
[SHADE INDICATES LICENSE REQUIREMENT]
LIMITS ASFOUND DATE NOTTO BE COMPLETED EXCEEDED
- INITIALS MAXIMUM HIGH:
INCHES REACTOR TANK HIGH AND LOW WATER 1
LEVEL ALARMS MOVEMENT LOW:
INCHES
+/-3 INCHES ANN:
2 REACTOR TANK TEMPERATURE ALARM FUNCTIONAL Tested @ __
CHECK 3A CHANNEL TEST OF STACK CAM GAS CHANNEL 8.5E4+/-
Ann.?
cpm Ann.
8500 cpm 3B CHANNEL TEST OF STACK CAM PARTICULATE 8.5E4+/-
Ann.?
Ann.
CHANNEL 8500 cpm
_cpm 3C CHANNEL TEST OF REACTOR TOP CAM 8.5E4+/-
Ann.?
Ann.
PARTICULATE CHANNEL 8500 cpm
_cpm 4
MEASUREMENT OF REACTOR PRIMARY
<5 µmho\\cm WATER CONDUCTIVITY 5
PRIMARY WATER pH MEASUREMENT MIN:5 NIA MAX:9 6
BULK SHIELD TANK WATER pH MIN:5 NIA MEASUREMENT MAX:9 7
CHANGE LAZY SUSAN FILTER FILTER NIA CHANGED 8
REACTOR TOP CAM OIL LEVEL CHECK OSTROP 13.8 NEED OIL?
NIA 9
STACK CAM OIL LEVEL CHECK OSTROP 13.9 NEED OIL?
NIA JO EMERGENCY DIESEL GENERATOR CHECKS
> 50%
Oil ok?
NIA Visual Hours NIA 11 RABBIT SYSTEM RUN TIME Total hours/Hours NIA on current brushes 12 OIL TRANSIENT ROD BRONZE BEARING WD40 NIA 13 CRANE INSPECTION Hooks Hoist NIA Rope 14 WATER MONITOR CHECK RCHPP 8 App. F.4 NIA 15 EMERGENCY LIGHT TESTING 30 seconcs?
- Date not to be exceeded is only applicable to shaded items. lt is equal to the time completed last month plus six weeks.
Figure IV.2 Quarterly Surveillance and Maintenance (Sample Form)
OSTROP 14, Rev. LEU-7 Surveillance & Maintenance for the 1st / 2nd / 3rd / 4th Quarter of 20 __
SURVEILLANCE & MAINTENANCE LIMITS ASFOUND TARGET DATE NOTTO DATE REMARKS&
[SHADE INDICATES LICENSE REQUIREMENT]
DATE BE EXCEEDED*
COMPLETED INITIALS l
REACTOR OPERATION COMMITTEE (ROC) AUDIT QUARTERLY 2
INTERNAL AUDIT OF OSTROPS QUARTERLY 3
QUARTERLY ROC MEETING QUARTERLY 4
ERP INSPECTIONS QUARTERLY 5
ROTATING RACK CHECK FOR UNKNOWN SAMPLES EMPTY 6
WATER MONITOR ALARM CHECK FUNCTIONAL 7A CHECK FILTER TAPE SPEED ON STACK MONITOR l"/HR +/- 0.2 7B CHECK FILTER TAPE SPEED ON CAM MONITOR 1"/HR +/- 0.2 8
INCORPORATE 50.59 INTO DOCUMENTATION QUARTERLY 9
EMERGENCY CALL LIST QUARTERLY ARM SYSTEM ALARM CHECKS ARM 1
2 3S 3E 4 5
7 8
9 10 11 12 AUD 10 FUNCTIONAL LIGHT PANEL ANN 11 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.
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OSTROP 15, Rev. LEU-11 Surveillance & Maintenance for the 1st / 2nd Half of 20 SURVEILLANCE & MAINTENANCE TARGET DATE NOT DATE REMARKS
[SHADE INDICATES LICENSE REQUIREMENT]
LIMITS AS FOUND DATE TOBE COMPLETED EXCEEDED*
INITIALS NO WITHDRAW NEUTRON SOURCE COUNT RATE INTERLOCK
?: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
- '.S $2.25 TWO ROD WITHDRAWAL PRHOHIBIT IONLY PULSE PROHIBIT ABOVE I kW
?:I kW PREVIOUS PULSE DATA FOR COMPARJON
- 520%
PULSE # --
PULSE #
2 TEST PULSE CHANGE MW MW oc oc 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 BEARINGS WD-40 6
CONSOLE CHECK LIST OSTROP 15.Vll HlGH 7
STANDARD CONTROL ROD MOTOR CHECKS LO-17 Bodine Oil
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- Date not to be exceeded is only applicable to shaded items. It is equal to the date last time plus 7.5 months.
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Semi-Annual Surveillance and Maintenance (Sample Form)
O STROP 15, Rev. LEU-11 Surveillance & Maintenance for the I st / 2nd Half of 20 SURVEILLANCE & MAINTENANCE
[SHADE INDICATES LICENSE REQUIREMENT]
8 FUNCTlONAL CHECK OF HOLDUP TANK WATER LEVEL ALARMS 9
INSPECTION OF THE PNEUMATIC TRANSFER SYSTEM LIMITS OSTROPl5.IX BRUSH INSPECTION ASFOUND HIGH __
FULL __
SAMPLE Observed INSERTION AND insertion/
WITHDRAWAL withdrawal time
- Date not to be exceeded is only applicable to shaded items. It is equal to the date last time plus 7.5 months.
TARGET DATE DATE NOT DATE REMARKS &
TOBE EXCEEDED*
COMPLETED INITIALS
Figure IV.4 Annual Surveillance and Maintenance (Sample Form)
OSTROP 16, Rev. LEU-10 Annual Surveillance and Maintenance for 20 SURVEILLANCE AND MAINTENANCE AS TARGET DATE NOT DATE REMARKS
[SHADE INDICATES LICENSE REQUIREMENT]
LIMITS FOUND DATE TOBE COMPLETED EXCEEDED*
INITIALS 1
BIENNIAL INSPECTION OF FFCRS OSTROP 12.0 CONTROL RODS:
TRANS 2
STANDARD CONTROL ROD DRIVE INSPECTON OSTROP 16.2 3
CONTROL ROD CALIBRATION:
OSTROP9.0 TRANS SAFE SHIM REG CONTROL ROD SCRAM
~2 sec 4
WITHDRAWAL INSERTION &
W/D
<50 sec SCRAM TIMES INSERT
~50 sec FUEL ELEMENT INSPECTION FOR SELECTED
~ 20% t<E s mspected.
5 ELEMENTS No damage rlPtPnnr<>tinn nr on,all 6
REACTOR POWER CALIBRATION OSTROP8 7
CALIBRATION OF REACTOR TANK WATER TEMP OSTROP 16.8 TEMPERATURE METERS CONTINUOUS
!Particulate Monitor 8
AIR MONITOR Gas Monitor RCHPP 18 CALlBRATION 9
CAM OIL/GREASE MAINTENANCE STACK MONITOR Particulate Monitor RCHPP 10 CALIBRATION 18 & 26 Gas Monitor 11 STACK MONITOR OIL/GREASE MAINTENANCE 12 AREA RADIATION MONITOR CALIBRATION RCHPP18
- 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 comoleted last time olus 2 1/2 vears.
N 0
Figure IV.4 (continued)
N N
I N Annual Surveillance and Maintenance (Sample Form) 0 N
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OSTROP 16, Rev. LEU-10 Annual Surveillance and Maintenance for 20 I
SURVEILLANCE AND MAINTENANCE AS TARGET DATE OT DATE LIMITS TOBE REMARKS
[SHADE INDICATES LICENSE REQUIREMENT]
FOUND DATE EXCEEDED*
COMPLETED
& INITIALS 13 CORE EXCESS
~$7.55 DAMPERS
]ST FLOOR 14 !REACTOR BAY VENTILATION SYSTEM SHUTDOWN TEST CLOSE rN <5 SECONDS 4TH FLOOR 15 CRANE INSPECTION 16 SNM PHYSICAL INVENTORY NIA NIA OCTOBER I-17 MATERIAL BALANCE REPORTS IA IA NOVEMBER CFO TRAINING GOOD SAM TRAlNING ERP REVIEW MEMO ERP DRILL CPR CERT FOR:
CPR CERT FOR:
EMERGENCY FIRST AID CERT FOR:
18
RESPONSE
PLAN FIRST AID CERT FOR:
EVACUATION DRILL AUTO EVAC ANNOUNCEMENT TEST ERP EQUIPMENT INVENTORY BIE JAL SUPPORT AGREEMENTS PSPREVIEW MEMO PSPDRILL PHYSICAL PART 3 7 PLAN REVIEW 19 SECURITY PART 37 PLAN DRILL PLAN DPS TRAINING LOCK/SAFE COMBO CHANGES AUTHORIZATION UST UPDATE
- Date not be exceeded is only applicable to shaded items. It is equal to the date completed last year plus 15 months.
N For biennial license requirements, it is equal to the date completed last time plus 2 1/2 years.
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Annual Surveillance and Maintenance (Sample Form)
OSTROP 16, Rev. LEU-I 0 Annual Surveillance and Maintenance for 20 AS TARGET lJAlt NU l DATE REMARKS SURVEILLANCE AND MAINTENANCE
[SHADE INDICATES LICENSE REQUIREMENT]
LIMITS FOUND DATE TO BE COMPLETED
& INITIALS F.Yri:i:n F n
- 20 ANNUAL REPORT NOV 1 OCT l NOV 1 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 NEUTRON RADIOGRAPHY FACILTIY INTERLOCKS 26 EXPERIMENTS REVIEW MEMO 27 REACTOR OPERATOR LICENSE CONDITIONS
- 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.
REACTOR 2022-2023 25
Radiation Protection Introduction The purpose of the radiation protection program is to ensure the safe use of radiation and radioactive material in the Cen-ter'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 V. 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 Health Physicist, a Health Physicist, and several part-time Health Physics Monitors (see Part 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 hav nb je 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 con-tained in that license. The material has also been prepared in compliance with Oregon Department of Energy Rule No.
345-30-010, which requires an annual report of environmental effects due to research reactor operations.
26 Within the scope of Oregon State University's radiation pro-tection program, it is standard operating policy to maintain all releases ofradioactivity to the umestricted environment and all exposures to radiation and radioactive materials at levels which are 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 ofradioactive effluents 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 are discussed briefly below. Data regarding these effluents are also summarized in detail in the designated tables.
Liquid Effluents Released Liquid Effluents Oregon State University has implemented a policy to reduce the volume of radioactive liquid effluents to an absolute mini-mum. For example, water used during the ion exchanger resin change is now recycled as reactor makeup water. Waste water ANNUAL REPORT 1
1 **
1 r
- I
- r I
1 1
RADIATION PROTECTION 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 seven liquid effluent releases to the sanitary sewer. All Radiation Center and reac-tor 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 experi-ments is transferred by the campus Radiation Safety Office to its waste processing facility. The annual summary of liquid waste generated and transferred is contained in Table V.3.
Airborne Effluents Released Airborne effluents are discussed in terms of the gaseous com-ponent and the particulate component.
Gaseous Ejfluents Gaseous effluents from the reactor facility are monitored by the reactor stack effluent monitor. Monitoring is continuous, i.e., prior to, during, and after reactor operations. It is normal for the reactor facility stack effluent monitor to begin opera-tion 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 TableV.4.
Particulate effluents from the reactor facility are also moni-tored by the reactor facility stack effluent monitor.
Particulate Ejfluents Evaluation of the detectable particulate radioactivity in the stack effluent confirmed its origin as naturally-occurring radon daughter products, within a range of approximately 3 x 10-11
µCi/ml to 1 x 10-9 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 aver-age concentration of radioactive particulates with half lives greater than eight days is not applicable.
2022-2023 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 Radia-tion 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 materi-als license.
Solid radioactive waste is disposed ofby OSU Radiation Safety by transfer to the University's radioactive waste dis-posal vendor.
Personnel Dose The OSTR annual reporting requirements specify that the licensee shall present a summary of the radiation exposure received by facility personnel and visitors. The summary in-cludes all Radiation Center personnel who may have received exposure to radiation. These personnel have been categorized into six groups: facility operating personnel, key facility research personnel, facilities services maintenance personnel, students in laboratory classes, police and security personnel, and visitors.
Facility operating personnel include the reactor operations and health physics staff. The dosimeters used to monitor these in-dividuals include quarterly TLD badges, quarterly track-etch/
albedo neutron dosimeters, monthly TLD (finger) extremity dosimeters, pocket ion chambers, electronic dosimetry.
Key facility research personnel consist of Radiation Center staff, faculty, and graduate students who perform research using the reactor, reactor-activated materials, or using other research facilities present at the Center. The individual dosim-etry requirements for these personnel will vary with the type of research being conducted, but will generally include a quar-terly 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 normally issued a gamma sensitive electronic dosimeter as their basic monitor-ing device.
Students attending laboratory classes are issued quarterly XB(y) TLD badges, TLD (finger) extremity dosimeters, and track-etch/albedo or other neutron dosimeters, as appropriate.
27
RADIATION PROTECTION 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 results are not included with the laboratory class students.
OSU police and security personnel are issued a quarterly XB(y) TLD badge to be used during their patrols of the Radia-tion Center and reactor facility.
Visitors, depending on the locations visited, may be issued gamma sensitive electronic dosimeters. OSU Radiation Center policy does not normally allow people in the visitor category to become actively involved in the use or handling of radioac-tive 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 10 CFR 20 or State of Oregon regulations during the reporting period.
Facility Survey Data The OSTR Technical Specifications require an annual sum-mary 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 Radiation Dosimeters Area monitoring dosimeters capable of integrating the radia-tion dose are located at strategic positions throughout the reactor facility and Radiation Center. All of these dosimeters contain at least a standard personnel-type beta-gamma film or TLD pack. In addition, for key locations in the reactor facility and for certain Radiation Center laboratories a CR-39 plas-tic track-etch neutron detector has also been included in the monitoring package.
The total dose equivalent recorded on the various reactor facil-ity dosimeters is listed in Table V. 7 and the total dose equiva-lent 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 Radiation and Contamination Surveys The Center's program for routine radiation and contamination surveys consists of daily, weekly, and monthly measurements 28 throughout the TRIGA reactor facility and Radiation Center.
The frequency of these surveys is based on the nature of the radiation work being carried out at a particular location or on other factors which indicate that surveillance over a specific area at a defined frequency is desirable.
The primary purpose of the routine radiation and contamina-tion survey program is to assure regularly scheduled surveil-lance over selected work areas in the reactor facility and in the Radiation Center, in order to provide current and characteristic data on the status of radiological conditions. A second objec-tive of the program is to assure frequent on-the-spot personal observations (along with recorded data), which will provide advance warning of needed corrections and thereby help to ensure the safe use and handling of radiation sources and radioactive materials. A third objective, which is really derived from successful execution of the first two objectives, is to gath-er 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 reason-ably 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 Tec¥ical Specifications include "an annual summary of envirmrnental surveys performed 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 re-actor facility stack effluent monitor described in Section V and nine environmental monitoring stations.
During this reporting period, each fence environmental 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 3 TLDs per station x 4 quarters). The total number ofTLD samples for the reporting period was 108. A summary of the TLD data is also shown in Table V.10.
ANNUAL REPORT
1* * * *
- RADIATION PROTECTION From Table V. l O it is concluded that the doses recorded by the dosimeters on the TRIGA facility fence can be attributed to natural back-ground radiation, which is about 110 mrem per year for Oregon (Refs. 1, 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 of the 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 summary ofTLD data for the off-site monitoring stations is given in Table V.11.
After a review of the data in Table V.11, it is concluded that, like the dosimeters on the TRIGA facility fence, all of the doses recorded by the off-site dosimeters can be attributed to natural background radiation, which is about 110 mrem per year for Oregon (Refs. 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 a annual basis. The program monitors highly unlikely radioactive material releases from either the TRIGA reactor facility or the OSU Radiation Center, and also helps indicate the general trend of the radioactivity concentration in each of the various substances sampled. See Figure V.1 for the locations of the sampling stations for grass (G), soil (S), water (W) and rainwater (RW) samples. Most locations are within a 1000 foot radius of the reactor facility and the Radiation Center. In general, samples are collected over a local area having a radius of about ten feet at the posi-tions indicated in Figure V.1.
There are a total of22 sampling locations: four soil loca-tions, four water locations (when water is available), and fourteen vegetation locations.
The annual concentration of total net beta radioactivity (mi-nus tritium) for samples collected at each environmental soil, water, and vegetation sampling location (sampling station) is 2022-2023 listed in Table V.12. Calculation of the total net beta disinte-gration rate incorporates subtraction of only the counting sys-tem back-ground 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 concentra-tion. Table V.13 gives the concentration and the range of val-ues for each sample category for the current reporting period.
As used in this report, the LLD has been defined as the amount or concentration of radioactive material (in terms of
µCi 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 conduct-ed if unusual radioactivity levels above natural background were detected. However, from Table V.12 it can be seen that the levels of radioactivity detected were consistent with naturally occurring radioactivity and comparable to values reported in previous years.
Radioactive Materials Shipments A summary of the radioactive material shipments originating from the TRIGA reactor facility, NRC license R-106, is shown in Table V.14. A similar summary for shipments originating from the Radiation Center's State of Oregon radioactive ma-terials license ORE 90005 is shown in Table V.15. A summary of radioactive material shipments exported under Nuclear Regulatory Commission general license 10 CFR 110.23 is shown in Table V.16.
References
- 1.
U. S. Environmental Protection Agency, "Estimates oflonizing Radiation Doses in the United States, 1960-2000," ORP/CSD 72-1, Office of Radiation Programs, Rockville, Maryland (1972).
- 2.
U. S. Environmental Protection Agency, "Radiologi-cal Quality of the Environment in the United States, 1977," EPA 520/1-77-009, Office of Radiation Pro-grams; Washington, D.C. 20460 (1977).
29
RADIATION PROTECTION 30 TableV.1 Radiation Protection Program Requirements and Frequencies I
Frequency Daily/Weekly/Monthly Monthly As Required Quarterly Semi-Annual Annual Radiation Protection Requirement
!Perform Routing area radiation/contamination monitoring Collect and analyze TRIG A primary, secondary, and make-up water.
Exchange personnel dosimeters, and review exposure reports.
Inspect laboratories.
Calculate previous month's gaseous effluent discharge.
Process and record solid waste and liquid effluent discharges.
Prepare and record radioactive material shipments.
Survey and record incoming radioactive materials receipts.
Perform and record special radiation surveys.
Perform thyroid and urinalysis bioassays.
Conduct orientations and training.
rssue 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.
Collect and analyze samples from reactor stack effluent line.
I I
Exchange personnel dosimeters and inside area monitoring dosimeters, and review exposure reports.
Leak test and inventory sealed sources.
Conduct floor survey of corridors and reactor bay.
Calibrate portable radiation monitoring instruments and personnel pocket ion chambers.
Calibrate reactor stack effluent 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 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.
ANNUAL REPORT
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Table V.2 Monthly Summary of Liquid Effluent Release to the Sanitary Sewer(11 Specific Activity for Total Quantity of Average Percent of Applicable Total Each Detectable Radio-Date of Quantity of Detectable nuclide in Each Detectable Concentration Monthly Average Discharge Radioactivity !Radionuclide in the Waste, Where the Radionuclide Of Released Concentration for (Month and Released the Waste Release Concentration Released in the Radioactive Material Released Radioactive Year)
(Curies)
Was>l x 10-7 Waste at the Point of Release Material
( µCi ml-1)
(Curies)
( µCi ml-1)
(%)<2)
No sewer disposal for the year (1) The OSU operational policy is to subtract only detector background from the water analysis data and not background radioactivity in the Corvallis city water.
(2) Based on values listed in 10 CFR 20, Appendix B to 20.1001 - 10.2401, Table 3, which are applicable to sewer disposal.
Total Volume of Liquid Effluent Released Including Diluent (gal)
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RADIATION PROTECTION 32 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 )
Radionuclides Radioactivity in the for Transfer to the Waste Waste Packaged Waste Processing (gallons) in the Waste Waste (Curies)
Facility TRIGA 28 Co-60, Zn-65, Se-75, 3.90xl04 8/22/2022 Sb-124, Yb-169, Hg-203 Radiation Center 9
U-235, U-238, Np-237, 4.20x10*8 8/22/2022 Laboratories Pu-239, Cf-252 2/7/2023 TOTAL 37 See above 3.90xl04 (1)
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 Estimated Estimated Quantity of Concentration of Month Activity Argon-41 Argon-41 at Point of Annual Average Released (Curies)
Released0> (Curies)
Release Argon-41
(µCi/cc)
Concentration Limit(%)
July 2.01 2.01 1.53x10*7 3.84 August 2.54 2.54 1.94x10*7 4.84 September 0.84 0.84 6.65xl0*8 1.66 October 0.93 0.93 7.1lxl0*8 1.78 November 0.78 0.78 6.1 3xlQ*M 1.53 December 1.09 1.09 8.35xlQ*M 2.09 January 1.19 1.19 9.12xlQ*M 2.28 February 1.73 1.73 1.46x10*7 3.66 March 2.08 2.08 1.59x10*7 3.96 April 1.30 1.30 l.02x10*'
2.56 May 1.73 1.73 1.32x10*7 3.30 June 1.53 1.53 1.21x10*7 3.02 TOTAL
('22-'23) 17.75 17.75 l.15x10*7<2i 2.88 (1) Routine gamma spectroscopy analysis of the gaseous radioactivity in the OSTR stack discharge indicated the only detectable radionuclide was argon-41.
(2) Annual Average.
ANNUAl REPORT
I 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 Packagedu>
in the Waste in Solid Waste Waste Processing (Cubic Feet)
(Curies)
Facility TRIGA Co-58, Co-60, Sc-46, Cr-5 1, 8/22/2022 Reactor 28 Mn-54, Sb-124, Fe-59, Zn-65,Ag-ll0m, l.474x10*3 2/7/2023 Facility As-74, Eu-152, Sc-46, Cs-134, Hf-1 81 5/25/2023 Radiation 8/22/2022 Center 16 Cf-252, U-238, Pu-239, Am-241,
4.23xl0*6 2/7/2023 Laboratories Am-243, Co-60, Nat U, U-233, U-235 5/25/2023 TOTAL 44 See Above l.478xl0*3 (1) OSTR and Radiation Center lab waste is picked up by OSU Radiation Safety for transfer to its waste processing facility for fina l packaging.
2022-2023 33
RADIATION PROTECTION Table V.6 Annual Summary of Personnel Radiation Doses Received Average Annual Greatest Individual Total Person-mrem Dose(l)
Dose<1J for the Group<1l Personnel Group Whole Body Extremities Whole Body Extremities Whole Body Extremities (mrem)
(mrem)
(mrem)
(mrem)
(mrem)
(mrem)
Facility Operating 125 213 217 806 999 1,707 Personnel Key Facility Research 2
64 31 245 31 577 Personnel Facilities Services Maintenance 0
NIA 0
NIA 0
NIA Personnel Laboratory Class 7
23 83 328 417 816 and Students Campus Police and 2
NIA 30 NIA 65 NIA Security Personnel Visitors 1
NIA 14.1 NIA 113 NIA (I) "NIA" indicates that there was no extremity monitoring conducted or required for the group.
34 ANNUAL REPORT
- RADIATION PROTECTION Table V.7 Total Dose Equivalent Recorded on Area Dosimeters Located Within the TRIGA Reactor Facility Total Dose Equivalentox2l Monitor TRIGA Reactor Recorded I.D.
Facility Location XB(y)
Neutron (See Figure V.1)
(mrem)
(mrem)
MRCTNE D104:
North Badge East Wall 149 ND MRCTSE D104:
South Badge East Wall 551 ND MRCTSW D104:
South Badge West Wall 281 ND MRCTNW D104:
orth Badge West Wall 123 ND MRCTWN D104:
West Badge North Wall 333 ND MRCTEN D104:
East Badge North Wall 233 ND MRCTES D104:
East Badge South Wall 2,403 ND MRCTWS Dl04:
West Badge South Wall 567 ND MRCTTOP D104:
Reactor Top Badge 904 ND MRCTHXS D104A: South Badge HX Room 528 ND MRCTHXW D104A: West Badge HX Room 242 ND MRCD-302 D302:
Reactor Control Room 395 ND MRCD-302A D302A: Reactor Supervisor's Office 0
ND MRCBPl D104: Beam Port Number 1 296 ND MRCBP2 D104: Beam Port Number 2 134 ND MRCBP3 D104: Beam Port Number 3 1,281 ND MRCBP4 D104: Beam Port Number 4 761 ND (l) The total recorded dose equivalent values do not include natuml background contribution and reflect the summation of the results of four quarterly beta-gan1ma dosimeters or four quarterly fast neutron dosimeters for each location. A total dose equivalent ofND" in-dicates that each of the dosimeters during the reporting period was less than the vendor's gamma dose reporting threshold of 10 mrem or that each of the fast neutron dosimeters was less than the vendor's threshold of 10 mrem. "NIA" indicates that there was no neutron monitor at that location.
(2) These dose equivalent values do not represent radiation exposure through an exterior wall directly into an unrestricted area.
- -------------------------------i 2022-2023 35
RADIATION PROTECTION 36 Monitor LD.
MRCAIO0 MRCBRF MRCA120 MRCA120A MRCA126 MRCCO-60 MRCA130 MRCA132 MRCA138 MRCBl00 MRCB114 MRCB119-l MRCB119-2 MRCB119A MRCB120 MRCB122-2 MRCB122-3 MRCB124-1 MRCB124-2 MRCB124-6 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<1J Facility Location XB(y) eutron (See Figure V.1)
(mrem)
(mrem)
AlO0:
Receptionist's Office 0
ND A102H: Front Personnel Dosimetry Storage Rack 0
ND A120:
Stock Room 20 ND Al20A: NAA Temporary Storage 82 ND Al26:
Radioisotope Research Laboratory 61 ND Al28:
6°Co Irradiator Room 518 ND Al30:
Shielded Exposure Room 0
ND A132:
TLD Equipment Room 0
ND Al38:
Health Physics Laboratory 0
lD BlO0:
Gamma Analyzer Room (Storage Cave) 740 ND Bll4:
Lab (226Ra Storage Facility) 0 ND Bl 19:
Source Storage Room 75 ND Bl 19:
Source Storage Room 258 ND Bll9A: Sealed Source Storage Room 5,633 485 Bl20:
Instrument Calibration Facility 0
ND B122:
Radioisotope Hood 0
ND Bl22:
Radioisotope Research Laboratory 0
D B124:
Radioisotope Research Laboratory (Hood) 145 ND B124:
Radioisotope Research Laboratory 0
ND B124:
Radioisotope Research Laboratory 0
ND B128:
Instrument Repair Shop 0
ND B136 Gamma Analyzer Room 0
ND ClO0:
Radiation Center Director's Office 0
ND C 106A: Office 0
ND C106B: Custodian Supply Storage 0
ND (l) 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 equiva-lent of"ND" indicates that each of the dosimeters during the rep01ting period was less than the vendor's gamma dose report-ing threshold of 10 mrem or that each of the fast neutron dosimeters was less than the vendor's threshold of 10 mrem. NIA" indicates that there was no neutron monitor at that location.
ANNUAL REPORT I
1 I. ** * * * * * * *
- 1 I* *
- i
RADIATION PROTECTION Monitor I.D.
MRCC106-H MRCC118 MRCC120 MRCFl00 MRCF102 MRCB125N MRCN125S MRCC124 MRCC130 MRCDl 00 MRCD102 MRCD102-H MRCD1 06-H MRCD200 MRCD202 MRCBRR MRCD204 MRCATHRL MRCD300 MRCA144 Bl32X B132 Bl04 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. l)
X B(y)
Neutron (mrem)
(mrem)
C 106H: East Loading Dock 0
ND Cll8:
Radiochemistry Laboratory 0
ND C120:
Student Counting Laboratory 0
ND FlO0:
APEX Facility 0
ND F102:
APEX Control Room 0
ND Bl25:
Gamma Analyzer Room (Storage Cave) 0 ND Bl25:
Gamma Analyzer Room 0
ND Cl24:
Classroom 0
ND Cl30:
Radioisotope Laboratory (Hood) 0 ND DI 00:
Reactor Support Laboratory 0
ND Dl02:
Pneumatic Transfer Terminal Laboratory 255 ND D 102H: 1st Floor Corridor at D l 02 38 ND D 106H: 1st Floor Corridor at D I 06 196 ND D200:
Reactor Administrator's Office 142 ND D202:
Senior Health Physicist's Office 194 ND D200H: Rear Persom1el Dosimetry Storage Rack 0
ND D204:
Health Physicist Office 225 ND Fl04:
ATHRL 0
ND D300:
3rd Floor Conference Room 129 ND A144:
Radioisotope Research Laboratory 14 ND B132X:
0 ND Bl32:
0 ND B104:
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 equiva-lent of"ND" indicates that each of the dosimeters during the repmting period was less than the vendor's gamma dose report-ing threshold of 10 mrem or that each of the fast neutron dosimeters was less than the vendor's threshold of 10 mrem. "N/A" indicates that there was no neutron monitor at that location.
2022-2023 37
RADIATION PROTECTION 38 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 (D104)
Reactor 2nd Deck Area (D 104)
Reactor Bay SW (D104)
Reactor Bay NW (D 104)
Reactor Bay NE (D104)
Reactor Bay SE (D104)
Class Experiments (D104, D302)
Demineralizer Tank & Make Up Water System (Dl04A)
Particulate Filter--Outside Shielding (D104A)
Radiation Center:
NAA Counting Rooms (AJ46, Bl00)
Health Physics Laboratory (A138) 60Co Irradiator Room and Calibration Rooms (A128, B 120, A 130)
Radiation Research Labs (A126, A136)
(B108, B114, B122, Bl24, Cl26, C130, Cl32A)
Radioactive Source Storage (B 119, B 119 A, A120A, Al32A)
Student Chemistry Laboratory (Cl 18)
Student Counting Laboratory (C120)
Operations Counting Room (B136, B125)
Pneumatic Transfer Laboratory (D 102)
RX support Room (D100)
Whole Body Radiation Levels (mrem/hr)
Average I Maximum 2.62 110 4.83 30
<l 80
<1 8
<l 15
<1 21.6
<I
<1
<I 9
<1 1.1
<I J.9
<1
<1
<l 22
<1 2.3
<1 35
<l
<l
<1
<1
<1
<1
<1 2.6
< I
< I Contamination Levels([>
(dpm/cm2)
Average I 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 (I) <500 dpm/100 cm2 = Less than the lower limit of detection for the portable survey instrurnent used.
ANNUAL REPORT
1*
- I RADIATION PROTECTION 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 TLDso, 2i (See Figure V.1)
(mrem)
MRCFE-1 74 +/- 16 MRCFE-2 70+/- 16 MRCFE-3 71 +/- 18 MRCFE-4 72 +/- 17 MRCFE-5 70+/- 15 MRCFE-6 74 +/- 18 MRCFE-7 74+/- 18 MRCFE-8 69+/- 15 MRCFE-9 81 +/-29 (I) Average Corvallis area natural background using Mirion TLDs totals 68+/- 35 mrem for the same period.
(2) +/- values represent the standard deviation of the total value at the 95% confidence level.
2022-2023 39
RADIATION PROTECTION Table V.11 Total Dose Equivalent at the Off-Site Gamma Radiation Monitoring Stations Off-Site Radiation Total Recorded Dose Equivalent 40 Monitoring Station (Including Background)
Based on Mirion TLDs<1, 2i (See Figure V. 1)
(m.rem)
MRCTE-2 66 +/- 09 MRCTE-3 69 +/- 14 MRCTE-4 72 +/- 19 MRCTE-5 73 +/- 11 MRCTE-6 71 +/- 14 MRCTE-7 79 +/- 20 MRCTE-8 74 +/- 07 MRCTE-9 73 +/- 11 MRCTE-10 63 +/- 12 MRCTE-12 75 +/- 11 MRCTE-13 71 +/- 16 MRCTE-14 74 +/- 19 MRCTE-15 69 +/- 19 MRCTE-16 75 +/- 14 MRCTE-17 76 +/- 25 MRCTE-18 75 +/- 19 MRCTE-19 63 +/- 16 MRCTE-20 74 +/- 18 MRCTE-21 66 +/- 17 MRCTE-22 69 +/- 17 (1) Average Corvallis area natural background using Mirion TLDs totals 68 +/- 35 mrem for the same period.
(2) +/- values represent the standard deviation of the total value at the 95% confidence level.
ANNUAL REPORT 1 * * * * *
- 1 * *
- RADIATION PROTECTION Sample Location (See Fig. V. l) 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 Table V.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 Total Net Beta (Minus 3H)
LLD Type Radioactivity<])
Units Water
- 1. 77xl o-7(2J
- 1. 77x 10-7(2J
µCi m1-l Water l.48x 1 o-7(2J l.48x 1 o-7<2J
µCi mJ-1 Water 5.9lx10-8<2 5.9 lxl o-8<2J
µCi m1-l Water
- 1. 77x 10-7(2) l.77xl0_7<2J
µCi mJ-l Soil 2.17xl -
5 <2J
- 2. l7x10-5
µCi g-1 of dry soil Soil l.69x10-5<
2>
l.69xl0-5<2J
µCi g-1 of dry soil Soil 1.85xl 0*
5 <
2 1.85xl0*
5
µCi g-1 of dry soil Soil 2.60x10-5<
2J 2.60x 1 o-5<2)
µCi g-1 of dry soil Grass 2.64xl0-4+/- 5.78xl0*
5 l.l 7x10-4
µCi g-1 of dry ash Grass l.40x10-4+/- 2.80x10.
5 5.59xl0*5
µCi g-1 of dry ash Grass 2.70x10-4 +/- 6.3 lx l0" 5
l.29xl0-4
µCi g-1 of dry ash Grass 2.59xl0-4 +/- 4.53x10.
5 8.78xl0*5
µCi g-1 of dry ash Grass l.89xl0-4 +/- 5.10xl0*
5 l.07x10-4
µCi g-I of dry ash Grass 1.53xl0-4 +/- 2.25xl0*
5 4.l 7xl0*5
µCi g-1 of dry ash Grass 8.09x10.
5 +/- 2.71x10" 5
5.86xl0*5
µCi g-1 of dry ash Grass 3.99x10-4 +/- 5.25xl0.
5 9.46x}0*5
µCi g-1 of dry ash Grass 4.67xl0-4 +/- 5.79x10*
5 l.02xJ0-4
µCi g-I of dry ash Grass 8.86xl0*
5 +/- 2.80xl0*
5 6.00x10*5
µCi g-I of dry ash Grass 2.44x10-4+/- 4.24xJ0-S 8.20xJ0*5
µCi g-1 of dry ash Grass 2.89xl0-4+/- 5.86xl0*
5 l.17xI0-4
µCi g-1 of dry ash Grass 2.62x10-4 +/- 6.02xlo*S l.23xI0-4
µCi g-1 of dry ash Grass 2.78xl0-4 +/- 5.2lxl0*
5 l.02xJ0-4
µCi g-1 of dry ash (1) +/- values represent the standard deviation of the value at the 95% confidence level.
(2) Less than lower limit of detection value shown.
2022-2023 41
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 III Arizona State University l.80x10-<>
2 0
1 0
Tucson AZ USA Berkeley Geochronology Center 3.37xl0*1 2
1 0
0 Berkelev. CA USA Materion Corporation 2.89xl0*2 0
0 0
3 Elmore OH USA Materion Natural Resources l.02xlQ*I 0
0 0
19 Delta UT USA Montana State University l.33xI0*8 1
0 0
0 Bozeman, MT USA Oregon State University l.67xl0*1 4
1 0
0 Corvallis. OR USA Pacific Northwest National Lab 2.23xl08 9
0 0
0 Richland. WA USA University of Arizona 2.80xl0*6 5
0 1
0 Tucson. AZ USA University of Chicago 4.22xl04 0
0 1
0 Chica!!o. IL USA University of Nevada, Las Vegas 2.71xl0*6 1
1 1
0 Las Vegas. NV USA University of Vermont 3.82xJ0*8 1
0 0
0 Burlin!:!:ton. VT USA University of Wisconsin-Madison 1.15xI0*5 3
2 2
0 Madison WI USA Totals 2.23xl08 28 5
6 22 Total 3
3 3
19 1
5 9
6 1
3 1
7 61 42 ANNUAL REPORT
RADIATION PROTECTION 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 Argonne National Lab 2.69xl0-1 0
1 0
0 Argonne, IL USA Duke University 3.32x10-7 1
1 0
0 Durham, NC USA Los Alamos National Lab 3.80xl0"° 0
4 2
0 Los Alamos, NM USA Rensselaer Polytechnic Institute 3.90x10-7 0
1 0
0 Troy,NY USA Totals 4.79xl0"° l
7 2
0 Table V.15 Annual Summary of Radioactive Material Shipments Exported Under NRC General License 1 O CFR 110.23 Number of Shipments Shipped To Total Activity Exempt Limited Yellow (TBq)
Quantity II Beijing Research Institute of Uranium Geology 5.19xl0*8 1
0 0
Beijing, CHINA China Earthquake Administration 1.55xl0-8 2
0 0
Beijing, CHINA Curtin University of Technology 1.47x10-5 0
0 2
Bently Western Australia AUSTRALIA Dalhousie University 2.59xlo-s 1
0 0
Halifax, Nova Scotia CANADA ISTO 6.56xl0-8 2
0 0
Orleans, FRANCE Korean Baskic Science Institute 2.12xI0-7 5
0 0
Cheongju-si, Chungcheongbuk:-do KOREA Lanzhou Center of Oil and Gas Resources l.9lxl0-8 1
0 0
Lanzhou, CHINA Lanzhou University 2.44xio-s 1
0 0
Lanzhou, Gansu CHINA LSCE-CNRS l.14xI0-7 3
0 0
Gif-Sur-Yvette, FRANCE 2022-2023 Total 1
2 6
1 10 Total 1
2 2
1 2
5 1
1 3
43
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 Northwest University 4.12xl0-9 1
0 0
XiAn, CHINA Polish Academy of Sciences 8.70x10-9 l
0 0
Krakow, POLAND Scottish Universities Research & Reactor Centre l.70xI0*7 3
0 0
East Kilbride, SCOTLAND Universidade de Sao Paulo l.6lxl0*7 4
0 0
San Paulo, BRAZIL Universita' Degli Studi di Bologna 3.47x10*9 1
0 0
Bologna, ITALY Univeritat Potsdam 4.2lxl0*8 2
0 0
Postdam, GERMANY University of Grenoble Alps 4.24xl0-9 1
0 0
Grenoble, FRANCE University of Geneva 7.47xI0*7 4
0 0
Geneva, SWITZERLAND University of Gottagen 8.9lxl0*10 I
0 0
Gottagen, GERMANY University of Innsbruck l.10xl0*8 I
0 0
Innsbruck, AUSTRIA University of Manitoba l.14xI0*5 0
3 0
Winnipeg, CANADA University of Melbourne l.06xl0-6 2
I 0
Parkville, Victoria AUSTRALIA University ofMilano-Bicocca 2.37xl0*8 1
0 0
Milano, ITALY University of Padova 2.28xl0*9 I
0 0
Padova, ITALY Vrijc Universiteit l.22x10-6 0
2 0
Amsterdam, THE NETHERLANDS Wadia Institute of Himalayan Geology l.56xl0*8 1
0 0
Dehradun Uttarakhand, INDIA Totals 3.00xl0*5 40 6
2 Total l
1 3
4 1
2 1
4 I
1 3
3 I
1 2
1 48 44 ANNUAL REPORT
RADIATION PROTECTION Figure V.1 Monitoring Stations for the OSU TRIGA Reactor 1
- 2022-2023
~ !
i
' i j
IREXD(
r;DN CNl"lJS UTlUTY
- IWl0C tffl.a:
trMlD.1Uffl4
-... *,,i7.*.,.
ft CAIOCA ffJ)ff.U'ION Tl c:uoCUt.DS'l'A.TIOK
- c; Ql,SS C
fl0ll.
W WA.'ID aw aunt"A.ttk NCnW: Tl:UZSLOCA%mlllllUSIDOVl1l
~MIIUDalCCZl!rD..U
~CCla'41.US.AmOl:I' 45
-k**.
-W-or Summary The Radiation Center offers a wide variety of resources for teaching, research, and service related to radiation and radioac-tive materials. Some of these are discussed in detail in other parts of this report. The purpose of this section is to sum-marize the teaching, research, and service efforts carried out during the current reporting period.
Teaching An important responsibility of the Radiation Center and the reactor is to support OSU's academic programs. Implementa-tion of this support occurs through direct involvement of the Center's staff and facilities in the teaching programs of various departments and through participation in University research programs. Table IIl.2 plus the "Training and Instuction" sec-tion (see next page) provide detailed information 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, information about students in-volved, a description of the project, Radiation Center resources needed, the Radiation Center project manager, status of indi-vidual runs, billing information, and the funding source.
Table VI. 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 students involved, 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 information relating to the personnel and institution involved, the type of project, and the funding agency. Projects which used the reactor are indicated by an asterisk. In addition to identifying specific projects carried out during the current reporting period, Part 46 VI also highlights major Radiation Center capabilities in research and service. These unique Center functions are described in the following text.
Neutron Activation Analysis Neutron activation analysis (NAA) stands at the forefront of tech-niques 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 radionu-clides are quantitatively measured by suitable semiconductor radia-tion detectors, and the gamma rays detected at a particular energy are usually indicative of a specific radionuclide's presence. Com-puterized 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 quanti-tatively about 35 elements in small samples (5 to 100 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 spectrum of material types and involving virtually every scientific and technical field.
While some researchers perform their own sample counting on their own or on Radiation Center equipment, the Radiation Center provides a complete NAA service for researchers and others who may require it. This includes sample preparation, sequential irra-diation and counting, and data reduction and analysis.
Irradiations As described throughout this report, a major capability of the Radiation Center involves the irradiation 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.
Radiological Emergency Response Services The Radiation Center has an emergency response team capable of responding to all types of radiological accidents. This team directly supports the City of Corvallis and Benton County emergency re-sponse organizations and medical facilities. The team can also pro-vide assistance at the scene of any radiological incident anywhere ANNUAL REPORT I * * * * * *
- I. * *
- WORK in the state of Oregon on behalf of the Oregon Radiation Protection Services and the Oregon Department of Energy.
The Radiation Center maintains dedicated stocks of radio-logical emergency response equipment and instrumentation.
These items are located at the Radiation Center and at the Good Samaritan Hospital in Corvallis.
During the current reporting period, the Radiation Center emergency response team conducted several training ses-sions and exercises, but was not required to respond to any actual incidents.
Training and Instruction In addition to the academic laboratory classes and courses discussed in Parts III and VI, and in addition to the routine training needed to meet the requirements of the OSTR Emer-gency Response Plan, Physical Security Plan, and operator requalification program, the Radiation Center is also used for special training programs. Radiation Center staff are well ex-perienced 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 behav-ior (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; Interna-tional Atomic Energy Agency fellows; special short-term courses; or individual reactor operator or health physics training programs. During this reporting period there were a large number of such people as shown in the People Section.
As has been the practice since 1985, Radiation Center personnel annually present a HAZMAT Response Team Ra-diological Course. This year the course was held at Oregon State University.
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 equip-ment 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 supplies health physics services which are not readily available else-2022-2023 where. In 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 phys-ics services in any of the areas which are discussed in Part V. These include personnel monitoring, radiation surveys, sealed source leak testing, packaging and shipment of radio-active materials, calibration and repair of radiation monitor-ing 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 Radi-ation Protection Services (RPS) in the event of a radiological emergency within the state of Oregon. In this role, the Radia-tion 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 neces-sity, 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 vari-ety 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 in-struments, components for most common repairs are often on hand and repair time is therefore minimized.
In addition to the instrument repair capability, the Radia-tion Center has a facility for calibrating essentially all types of radiation monitoring instruments. This includes typical portable monitoring instrumentation for the detection and measurement of alpha, beta, gamma, and neutron radiation, as well as instruments designed for low-level environmental monitoring. Higher range instruments for use in radiation accident situations can also be calibrated in most cases.
Instrument calibrations are performed using radiation sources certified by the National Institute of Standards and Technol-ogy (NIST) or traceable to NIST.
47
woRK Table Vl.3 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, while Table VI.4 shows instruments calibrated for other OSU departments and non-OSU agencies.
Consultation Radiation Center staff are available to provide consulta-tion 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 research-ers encountering problems or planning the design of experi-ments. 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 Number of Number of Times of Intuitions, Agencies and Groups Projects Faculty Involvement
- Andluca Technologies 1
0 Rochester, NY USA
- Arizona State Univeristy 1
0 Tempe, AZ USA Avalanche Energy 1
0 Seattle, WA USA
- Beijing Research Institute of Uranium Geology 1
0 Beijing, CHINA
- Benjamin Mutin 1
1 Cambridge, MA USA
- Berkeley Geochronology Center 1
0 Berkeley, CA USA Branch Engineering 1
0 Springfield, OR USA CDM Smith 1
Edison, NJ USA 0
CleanMark Labels 2
- Dalhousie University 1
2 Halifax, Novia Scotia CANADA
- Department of Geosciences 1
0 Tucson, AZ USA
- Environmental and Molecular Toxicology 1
3 Corvallis, OR USA Florida State University 1
0 Tallahassee, FL USA Genis, Inc.
1 0
Reykjavik, ICELAND Numberot Uses of Center J<<1{';J;t;PC 1
3 1
1 8
4 1
8 10 1
1 1
3 3
~--------------------------------------
48 ANNUAL REPORT
- WORK Table Vl.1 (continued)
Institutions, Agencies and Groups Which Utilized the Radiation Center Number of Number of Times of Intuitions, Agencies and Groups Projects Faculty Involvement
- Georg-August Universitat Gottingen 1
1 Gottingen, Lower Saxony GERMANY
- Georgia Institute of Technology 1
0 Atlanta, GA USA
- Greentree Synergy 1
0 Gardiner, NY USA
- Howe Industries Scottsdale, AZ USA 1
0
- Institute of Geology, China Earthquake Administration 1
0 Beijing, CHINA
- INSU-CNRS - Universite d'Orleans Orleans, FRANCE 1
l Kop-Coat 1
- Korea Basic Science Institute Cheongwon-gun, Chungcheongbuk-do SOUTH KOREA 1
1
- Lanzhou Center of Oil and Gas Resources, CAS 1
1 Lanzhou, CHINA
- Lanzhou University 1
0 Lanzhou City, Gansu Province CHINA
- Lanzhou University l
0 Lanzhou, CHINA
- LSCE-CNRS 1
0 Gif-Sur-Yvette Cedex, FRANCE
- Materion Brush, Inc.
1 0
Elmore, OH USA
- Materion Natural Resources l
- Montana State Univeresity 1
- Northwest University 1
0 Xi' An, CHINA Nu Planet Pharmaceutical Radioisotopes, Inc.
l 0
Scottsdale, AZ USA OMIC USA Inc.
1 0
- Oregon State University<1>
- Oregon State University - Educational Tours 1
- Oregon State University Radiation Center 1
1 Corvallis, OR USA 2022-2023 Number of Uses of Center P<>,-ilitie,<:
1 8
24 15 3
2 I
7 1
1 1
4 4
14 l
1 1
20 6Q(2) 10 12 49
woRK 50 Table Vl.1 (continued)
Institutions, Agencies and Groups Which Utilized the Radiation Center Number of Number of Times of Intuitions, Agencies and Groups Projects Faculty Involvement
- Pacific Northwest National Laboratory 1
0 Richland, WA USA
- Polish Academy of Sciences 1
0 Krakow, POLAND
- Scottish Universities Environmental Research Centre 1
0 East Kilbride UK
- Universita' Degli Studi di Padova 1
2 Padova ITALIA
- Universitat Potsdam 1
0 Potsdam, GERMANY
- Universite Grenoble Alpes 1
1 Grenoble, Isere FRANCE
- University of Arizona 2
3 Tucson, AZ USA
- University of Geneva 1
1 Geneva SWITZERLAND
- University oflnnsbruck 1
I Innsbruck, AUSTRIA
- University of Manitoba 1
1 Winnipeg, Manitoba CANADA
- University of Melbourne I
1 Melbourne, Victoria AUSTRALIA
- University of Michigan 1
1 Ann Arbor, Ml USA
- University ofMilano-Bicocca 1
0 Milano, ITALY
- University of Nevada, Las Vegas 1
- University of Potsdam 1
0 Potsdam, GERMANY
- University of Salzburg 1
I Salzburg, AUSTRALIA
- University of Sao Paulo 1
0 Sao Paulo BRAZIL University of Texas at Austin 1
- University of Vermont 1
- University of Wisconsin 1
1 Madison, WI USA US National Parks Service 1
0 Crater Lake, OR USA Number or Uses of Center Faciliti"'~
9 1
6 2
1 2
5 6
1 3
3 14 1
6 1
I 1
12 1
7 3
ANNUAL REPORT
WORK Table Vl.1 (continued)
Institutions, Agencies and Groups Which Utilized the Radiation Center Number of Number of Times of Intuitions, Agencies and Groups Projects Faculty Involvement
- Vrije Universiteit 1
1 Amsterdam THE NETHERLANDS
- Wadia Institute of Himalayan Geology 1
0 Dehradun, Uttarakhand INDIA
- Western Australian Argon Isotope Facility 1
0 Perth, Western Australia AUSTRALIA Totals 75 76 ProJect which mvolves the OSTR.
Number of Uses of Center Fa,,ilitii><<
2 2
4 331 (I)
(2)
Use by Oregon State University does not include any teaching activities or classes accommodated by the Radiation Center.
2022-2023 This number does not include on going projects being performed by residents of the Radiation Center such as the APEX project, others in the Department ofNuclear Engineering and Radiation Health Physics or Department of Chemistry or projects conducted by Dr. Walt Loveland, which involve daily use of the Radiation Center facilities.
51
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Table Vl.2 Listing of Major Research and Service Projects Preformed or in Progress
~
at the Radiation Center and Their Funding Agencies
~
Project Users Organization Name Project Title A
Description Funding Oregon State Ar-40/Ar-39 Dating of Oceanographic Production of Ar-39 from K-39 to measure OS U Oceanography 444 Duncan radiometric ages on basaltic rocks from ocean University Samples basins.
Department 815 Morrell Oregon State Sterilization of Wood Samples Sterilization of wood samples to 2.5 Mrads in Co-OSU Forest Products University 60 irradiator for fungal evaluations.
Berkeley Production of Ar-39 from K-39 to determine ages Berkeley 920 Becker Geochronology Center Ar-39/Ar-40 Age Dating in various anthropologic and geologic materials.
Geochronology Center 1074 Wijbrans Vrije Universiteit Ar/ Ar Dating of Rocks and Minerals Ar/Ar dating of rocks and minerals.
Vrije Universiteit, Amsterdam University of Production of Ar-39 from K-39 to determine ages Earth Sciences, 1191 Vasconcelos Ar-39/ Ar-40 Age Dating University of Queensland in various anthropologic and geologic materials.
Queensland 1465 Singer University of Ar-40/Ar-39 Dating ofYoung Geologic Irradiation of geological materials such as volcanic University of Wisconsin Materials rocks from sea floor, etc. for Ar-40/Ar-39 dating.
Wisconsin Teaching and Oregon State OSU Nuclear Engineering & Radiation 1504 University -
OSTR tour and reactor lab.
NA Tours Educational Tours Health Physics Department 1514 Sobel Universitat Potsdam Apatite Fission Track Analysis Age detennination of apatites by fission track Universitat Potsdam analysis.
1523 Zattin Universita' Degli Studi Fission track analysis of Apatites Fission track dating method on apatites by fission NA diPadova track analysis.
Irradiation to induce U-235 fission for fission track thermal history dating, especially for hydrocarbon 1555 Fitzgerald Syracuse University Fission track thermochronology exploration. The main thrust is towards tectonics, Syracuse University in particular the uplift and formation of mountain ranges.
University of Nevada Irradiation of rocks and minerals for Ar/ Ar dating Univerity of Nevada 1568 Zanetti Ar/ Ar dating of rocks and minerals to determine eruption ages, emplacement histories, Las Vegas and provenances studies.
Las Vegas 1617 Spikings University of Geneva Ar-Ar geochronology and Fission Track Argon dating of Chilean granites.
University of Geneva dating 1623 Blythe Occidental College Fission Track Analysis Fission track Thermochronology of geological Occidental College sarnoles 1660 Reactor Oregon State Operations support of the reactor and Operations use of the reactor in support ofreactor NA Operations Staff University facilities testing and facilities testing.
1745 Girdner US National Parks C 14 Measurements LSC analysis of samples for C 14 measurements.
US National Parks Service Service
N 0
~
Table Vl.2 (continued)
~
Listing of Major Research and Service Projects Preformed or in Progress
~
at the Radiation Center and Their Funding Agencies (11
(.I)
Project 1768 1777 1778 1785 1818 1831 1855 1860 1864 1865 1882 1884 1886 1887 Users Bringman Storey Gislason Mine Sabey Thomson Anczkiewicz Mine Gans Carrapa Bray Contreras Coutand Farsoni Organization Name Brush-Wellman Quaternary Dating Laboratory Genis, Inc Oregon State Univesity Brush Wellman University of Arizona Polish Academy of Sciences Oregon State University University of California at Santa Barbara University of Wyoming Wayne State Univerity Oregon State University Dalhousie University Oregon State University Project Title Description Antimony Source Production Production of Sb-124 sources.
Quaternary Dating Production of Ar-39 from K-39 to determine radiometric ages of geological materials.
This project subjects chitosan polymer in 40 and 70% DDA formulations to 9 and 18 Kgy, bow1dary Gamma exposure of Chitosan polymer doses for commerical sterilization for the purpose of determine changes in the molecular weight and product formulation properites.
INAA of Maya ceramics Trace-element analysis of ancient Maya ceramics from Pultrouser Swamp, Belize.
Antimony source production (Utah)
Fission track thermochronometry of the Fission Track Patagonian Andes and the Northern Apennines, Italy.
Fission Track Services Verification of AFT data for illite-mechte data.
INAA of Archaeological Ceramics Trace-element analysis of archaeological ceramics.
Production of Ar-39 from K-40 to determine Ar-40/Ar-39 Sample Dating radiometric ages of geologic samples.
Apatite fission track to reveal the exhumation Fission Track Irradiations history of rocks from the ID-WY-UY postion of the Sevier fold and thrust belt, Nepal, and Argentina.
INAA of Archaeological Ceramics from Trace-element analysis of Inca-period ceramics for South America provenance detennination.
The current project is designed to identify the LD50 rate of gamma irradiation so that large Mutation breeding of woody plants seed lots may be irradiated in order to develop novel phenotypes that exhibit reduced fertility or sterility.
Fission Track Irradiation Fission track irradiations of apatite samples.
Xenon Gas Production Production of xenon gas.
Funding Brush-Wellman Quaternary Dating Laboratory Genis, Inc.
Brush-Wellman Yale University Polish Academy of Sciences NIA University of California at Santa Barbara University of Wyoming Wayne State University OSU Horticulture Dahousie University OSUNERHP
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Listing of Major Research and Service Projects Preformed or in Progress
~
at the Radiation Center and Their Funding Agencies
- x, Project Users Organization Name Project Title Description Funding A
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 Minnesota 235U, 232Tb in natural rocks and minerals.
1905 Fellin ETH Zurich Fission Track Analysis Use of fission tracks to determine location of Geologisches Institut, 235U, 232Tb in natural rocks and minerals.
ETH Zurich Oregon State Fission Yield Determination Using Use of neutron activation to determine fission 1913 Reese yields for various fissile and fertile materials using NIA University Gamma Spectroscopy gamma spectroscopy, Scottish Universities Scottish Universities 1914 Barfod Environmental Ari Ar Age Dating Ar/ Ar age dating.
Research and Reactor Research Centre Centre 1927 Seward Victoria University of Fission Track Dating Fission track dating of apatite samples.
Vitoria University of Wellington Wellington 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 Ari Ar age dating Irradiation with fast neutrons to produce Ar-39 University of Vermont from K-39 for Ar/Ar geochronology.
Use offissin tracks to determine last heating event School of 1975 McDonald University of Glasgow Samuel Jaanne Geographical and of apatites.
Earth Science 1995 Camacho University of Manitoba Ar/Ar dating Production of Ar-39 from K-39 to determine 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 Postdam Ar/Ar Geochronological Studies Ari Ar dating of natural rocks and minerals for geological studies.
2007 Wartho Arizona State Argon-Argon Geochronology Fast neutron irradiation of mineral and rock Arizona State University samples for 40 Ar/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 Wester Australian Age dating of geological material Ari A f geochronology.
Curtin University Argon Isotope Facility
C1I C1I Project Users 2023 Cassata 2028 Mine 2029 Kim 2031 Malusa 2034 Morrell 2035 Wang 2036 Loveland 2039 Gombart 2048 Christensen 2060 lshizuka 2061 Weiss 2064 Schaefer 2067 Reese Table Vl.2 (continued)
Listing of Major Research and Service Projects Preformed or in Progress at the Radiation Center and Their Funding Agencies Organization Name Project Title Description Lawrence Livermore Ar/ Ar dating Production of neutron induced 39Ar from 39K for National Laboratory Ar/ Ar dating.
Oregon State INAA of ceramics from the Ancient Provenance determination of ceramics from the University Near East Ancient Near East via trace-element analysis.
Korea Basic Science Ar/ Ar geochronology Ar/ Ar analysis for age dating of geological Institute samples.
University of Milano-Fission Track Dating Use of fission tracks fron U-235 to determine age Bicocca ofrocks.
Oregon State Sterilization of Wood Products Sterilization of wood to 2.0 Mrad for fungal University experiments.
Lanzhou Center of Oil and Gas Resources, Fission Track Fission track dating ofrock samples.
CAS Oregon State Measurement of fission product TKE Measurement of fission product kinetic energy for University various fissile elements.
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 of Infections 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 nanofibers must be irradiated so that they are sterile. These experiments will be performed in cell culture and in animal models.
Oregon State INAA of IV Fluids INAA to determine 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 applicablity of neutron University Concrete radiography for evaluating concrete curing processes.
We will be performing bench scale microcosm CDMSmith 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 of neutron radiography and omography imaging in long-term studies of concrete curing University Concrete Curing used in civil construction.
Funding Lawrence Livermore National Laboratory OSU Anthropology Korea Basic Science Institute Universita degli Studi di Milano-Bicocca OSU Forest Products Lanzhou Center of Oil and Gas Resources, CAS OSU College of Pharmacy Geological Survey of Japan CDM Smith Oregon State University CCE
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Table Vl.2 {continued)
Listing of Major Research and Service Projects Preformed or in Progress
~
at the Radiation Center and Their Funding Agencies
- o Project Users Organization Name Project Title Description Funding A
2069 Scaillet INSU-CNRS-Ar/ Ar dating of geologic samples Ar/ Ar analysis for age dating of geologic samples INSU-CNRS-Universite d'Orleans (solid rock chips and minerals)
Universite d'Orleans The purpose of this experiment is to determine what color a nearly colorless Tourmaline will turn with dosages of 5, 10 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 Gema and 2070 Lowell Mineral Co.
color in Tourmaline from a Pegmatite in to red. The commercial value of colorless gem Mineral Co.
the Oban Massif, Nigeria Tourmaline is very low, but other colors of gem Tourmaline, 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 Nadel Charlotte Pipe and ABS Antimony Testing Testing for trace antimony in ABS via INAA Charlotte Pipe &
Foundry Co.
according to ASTM E3063.
Foundry Co.
2085 He Lanzhou University Apatite Fission Track Use of fission track analysis to determine Ucon-Lanzhou University tent in the sedimentation of Xining Basin.
2092 Jianaiqng Northwest University Fission Track Dating of Qaidam Basin Fission track dating ofQaidam Basin, China to determine its age.
Project is designed to 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 This project is a collaboration with OSU Robotics.
We are investigating the performance of PDMS School of Nuclear Soft Robotic Applications for Nuclear materials, which are used to fabricate soft robotics, Idaho National 2100 Palmer Science and following radiation exposure. We would like Engineering Safeguards to characterize any changes in hardness, tensile Laboratory strength, and recovery after exposure to high radiation environments.
N
~
Table Vl.2 (continued)
~
Listing of Major Research and Service Projects Preformed or in Progress
~
at the Radiation Center and Their Funding Agencies 01 Project 2101 2111 2115 2120 2121 2122 2135 2136 2142 2144 2145 Users Yang Turrin Scao Li Jia Jia Pomella Higley Heizler Hemming Morgan Organization Name Zhejiang University Rutgers LSCE-CNRS Institute of Tibetan Plateau Research, Chinese Academy of Sciences Beijing Research Institue of Uranium Geology Beijing Research Institue of Uranium Geology University of Innsbruck Oregon State University New Mexico Institue of Mining &
Technology Columbia University U.S. Geological Survey Project Title Description Fission-track thennochronometry Fission-track analysis for dating geological material.
Ar/ Ar Geochronology Lunar/solar system chronology.
Age dating of geologic materials Ar/Ar analysis for age dating of Geologic materials.
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 Me V ion tracks Alpha-particle induced annealing effects (simulating fission tracks) in apatite. For the next step, we are planning to use chemical etching to of fission tracks in apatite further confirm the alpha-annealing effects on real fission tracks. Neutron-induced fission tracks are essential to the etching experiments because neutron-induced fission tracks, have no thermal history (or thermal annealing effects).
Fission track analysis to determine U content in South China Fision track dating of areas of South China.
Ar-Ar analysis for age dating of geologic Ar-Ar analysis for age dating of geologic materials materials.
(solid rock grains and minerals).
Apatite Fission Track Apatite fission track, standards for zeta calibration.
INAA of Mining Site Soils Soil analysis by INAA for Uranium/Thorium concentration assessment.
Fast neutron irradiation of geological samples Irradiation of samples for 40Ar/39Ar to primarily transmute 39K to 39Ar for the geochronology for NM Tech purposes of rock and mineral dating. Samples are for academic geological investigations requiring knowledge of age and/or thermal history.
We analyze a variety of geological samples for Ar Geochronology for the Earth their 40Ar/39Ar ages, including samples for Sciences (AGES) external collaborators and for internal grant-supported research.
Neutron irradiation requested for 40Ar/39Ar 40 Ar/39Ar Geochronology geochronology. Will use 39K (n,p) 39Ar reaction to determine ages on rocks and minerals.
Funding Zhejiang University NASA LSCE-CNRS Chinese Academy of Sciences Beijing Research Institue of Uranium Geology University of Innsbruck NM Bureau of Geology Columbia Univeristy USGSArgon Geochronology
(J1
- 0)
Table Vl.2 (continued)
Listing of Major Research and Service Projects Preformed or in Progress
~
0 at the Radiation Center and Their Funding Agencies
- c i
Project Users Organization Name Project Title Description Funding Menlo Park Geochronology uses 40Ar/39Ar techniques to date materials for geologic hazards, 2146 Calvert U.S. Geological 40 Ar/39Ar Geochronology mapping, tectonic and mineral resource projects.
Menlo Park Survey The method requires fast-neutron irradiation of Geochronology separates from volcanic, plutonic, sedimentary and metamorphic rocks to convert 39K to 39Ar.
2149 Vanderstelt Nray Services, Inc.
Titanium Trubine Blade Activation Examination of neutron activation in titanium Nray Services, Inc.
turbine blades from neutron radiography.
2153 Quinn Solidia Technologies Neutron Radiography to Image Carbon Using neutron radiography to look at pressurized Solidia Technologies Dioxide in Concrete CO2 in concrete that is curing.
2157 Fawcett University of MN2019a Neutron irradiation of geologic material for noble University of Manchester gas analysis and dating.
Manchester 2160 Schaen Department of University of Arizona 40Ar/39Ar Irradiation rock & mineral samples for 40Ar/39Ar University of Arizona Geosciences geochronology dating.
NAA of clays to determine radioactivity level 2161 Turina 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 of microbiota in fatty liver Oregon State 2162 Jump polyunsaturated fatty acids (PUFA) on University liver disease and in beneficial effect of PUFA on liver.
University The main idea is to introduce gamma rays to tissue cultures of 3 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, we will Oregon State 2163 Sathuvalli Dept of Horticulture Gamma irradiation of potatoes evaluate the plants (if they survive the mutation)
University for those qualities. The first stage is to ascertain the optimum radiation dosage for the 3 varieties Horticulture 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.
z A set of 5 polymers (EPDM, PTFE, PCTFE, PFA, z
PAI) used in common spaceflight applications are C
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NASA Marshall Space to be exposed to the mixed neutron/gamma field of r
2165 Caffrey Nuclear Propulsion Polymer Tests the OSTR in order to evaluate changes in material NASA
- 0 Flight Center m
properties. The current test includes a total of "ti 60 'microdogbone' ASTM D638 Type V tensile 0
~
specimens.
- ~******************************************
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Table Vl.2 (continued)
I\\)
~
Listing of Major Research and Service Projects Preformed or in Progress
~
at the Radiation Center and Their Funding Agencies CJ1 (0
Project 2166 2167 2168 2169 2170 2171 2172 Users Kampfer Reese Radniecki Field Howe Tiwari Graziano Organization Name Materion Corp.
Oregon State University Oregon State University CBEE Environmental and Molecular Toxicology Howe Industries Department of Plant Science and Landscape Architecture University of Alaska Anchorage Project Title Description Trace-element analysis of Be powder.
INAA to determine U content of Be powder.
Neutron Radiography of Artifacts Use of neutron radiography to examine archaeological artifacts.
We are trying to isolate the effects that biofilm growth and fouling has on sorption kinetics, breakthrough, and desorption in packed columns The Effects ofBiofilms in elm testing of two different proprietary adsorbents. By looking of sorbents for removal of Cu, Zn and at the data for triplicate columns with and without PFAS's from Storwater biofilms enriched from the OGSIR facility in Avery park, we hope to isolate the effects that naturally occuring biofilms have on sorption removal of PFASs, zinc and copper in stormwater.
PFAS Compounds in the Environment INAA to determine total fluorine content in consumer products and the environment.
Testing electrical conductivity changes of Thennoelectric Cooler Conductivity materials while monitoring temperatures of device Experiment and ambient conditions. Power will be stepped at various levels to determine these parameter changes.
We would like to get these seeds irradiated for inducing gamma irradiation-induced chromosomal Gamma induced chromosomal breaks in breaks in CS and MOY-wheats.It will allow CS and MOV wheats us to map targeted candidate genes in low recombination regions and will help in overall 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 Control of invasive plants at high soil herbicide isothenns for aminopyralid and 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.
Funding Materion Corp.
Oregon State University CBEE OSU Toxicology Howe Industries University of Maryland College Park University of Alaska
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Table Vl.2 (continued)
Listing of Major Research and Service Projects Preformed or in Progress
~
at the Radiation Center and Their Funding Agencies
- o
~
Project Users Organization Name Project Title Description Funding 2173 Lee University of Oregon INAA of Ancient Korean Ceramics Trace-element analyses of Neolithic and Bronze University of Oregon Age ceramics from Korea.
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 Fl8 Solutions, Inc.
decay from Ol6+T reactions to be measured on an OSU HPGe detector.
2175 Gess Oregon State Neutron Radiography of two Phase Flow Use of neutron radiography to evaluate two phase University MIME 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 2176 Phelps Adhezion Biomedical Various Ampoule Gamma-Feasibility understand the process and ensure your facility Adhczion Biomedical Run can stay within the range of 8-12 kGy. Once we get the samples returned, if all testing on our end result 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 2177 Phelps Adhezion Biomedical PVDF Ampoule Gamma-Feasibility Run shall follow on our end after Gamma-irradiation Adhezion Biomedical to determine if this is a good sterilization method to move into a larger scale sterilization for our medical device product line.
BASF Additive Concrete Curing Examination of a BASF addative to concrete 2178 Weiss Oregon State mixutures and it's effect upon curing under University Investigation pressure.
BASF Additive Concrete Curing Examination of a BASF addative to concrete 2179 Weiss Oregon State mixutures and it's effect upon curing under Univer ity Investigation pressure.
2180 Meqbel Hi-Tech Precious INAA of Mine Tailings INAA to determine precious metal (gold and PGE)
Metal Refinery content of mine tailings.
I\\)
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Table Vl.2 (continued)
I\\)
~
Listing of Major Research and Service Projects Preformed or in Progress
~
at the Radiation Center and Their Funding Agencies 0,
Project 2181 2182 2183 2184 2185 2186 2187 2188 2189 2190 Users Singh Reese Sprain Bernet Taylor Cao Stevens Goddard Orme Kasparek Loveland Organization Name Wadia Institute of Himalayan Geology Oregon State University Department of Geological Sciences, University ofFlorida Univeresite Grenoble Alpes Univeresity of Minnesota Oregon State University Indiana University Montana State University Pacific Northwest National Laboratory Oregon State University Project Title Description Geo-Thennochronological investigation To study the shallow crust exhumation history of Lesser Himalayan Crystialline of of the lesser Himalayan crystalline and Meta-Garhwal region,NW-Himalaya sedimentary sequence of Garhwal region.
Use ofD2O as a contrast enhancement Examination of the improvement in contrast for neutron radiography gained by using D2O instead of H2O in the analysis of concrete curing.
This project is for the irradiation of geological materials with a high flux of fast neutrons to facilitate the 39K(n,p )39Ar reaction. Irradiated Irradiation for 40Ar/39Ar geochronology geological materials will subsequently be analyzed for 40Ar/39Ar geochronological analysis to determine the age of the geological materials.
The apatite samples are for three different projects Apatite Fission Track irradiations for studying the exhumation of the Himalayas, Andes, and European Alps.
Pioneer Mountains AFT Suite ofapatite crystals to be irradiated for fission track dating.
Fluorine Content in PFAS standards INAA to determine fluorine content in PFAS standards.
Irradiation of geologic materials (minerals apatite Fission Track Analysis and zircon) for fission track analysis (age dating of thermal events) using the external detector method.
AFT Irradiation - MSU Irradiation of apatite grains mounted in epoxy for fission track analysis at Montana State University.
This project will develop and build a custom Cerenkov In-Pool Noise Characterization UV probe and spectrophotometer to map the UV spectrum in spent fuel ponds and identify and quantify light noise contributions within the pool.
Seperation characterization of mid and Seperation characterization of mid and high Z high Z elements.
elements.
Funding Wadia Institute of Himalayan Geology Department of Geological Sciences, University of Florida Universite Grenoble Alpes University of Minnesota Department of Chemistry Indiana University Montana State University
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Listing of Major Research and Service Projects Preformed or in Progress
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The sensor is an industrial grade accelerometer which consists of a silicon sensor and ASIC hermitically sealed in a 0.35" square ceramic 2191 Hulbert Silcon Designs Inc.
Sensor Performance vs Total Ionizing package. This project will irradiate several groups Dose (TID) of sensors over a range ofTID and compare the before and after results of a variety of electrical and dynamic measurements to determine the effect(s) of the radiation.
2192 Frame Yale University INAA of archaeological and geological Trace-element analysis via INAA of fired clay, 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 II 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.
Support the 69981 Program (Child Project XYZ -
Pacific Northwest 70039) at Pacific Northwest National Laboratory Pacific Northwest 2194 Gruendell National Laboratory Lexan slides for fission track irradiation by providing the ability to perform fission track National 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 properties materials. Highly aligned CNT sheet or yam Florida State showed significant properties improvement due Florida State 2195 Liang University enhancement bye-beam and gamma-ray to high alignment degree over 0. 7. High energy University l'>
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Listing of Major Research and Service Projects Preformed or in Progress at the Radiation Center and Their Funding Agencies Organization Name Project Title Description These studies will explore the individual and Housing temperature: an important combined effects of(l) mild chronic cold stress Oregon State variable for simulated spaceflight studies (induced by room temperature housing) and (2)
University using mice hindlimb unloading (HLU) on premature bone loss in C57BL/6 (B6) mice, a strain commonly used in spaceflight/simulated spaceflight studies.
We are developing drug delivery systems using Gamma Sterlization Effects on Drug transdermal delivery systems. In one of our Gerogia Institute of projects, we are interested in gamma sterilization Technology Loaded Patches for terminal sterilization of our product which is basically a drug/polymer mixture.
We would like to get these seeds irradiated Department of Plant for inducing gamma irradiation-induced Gamma irradiation-induced chromosomal breaks in varieties MD3 l5 and PJT Science and Landscape chromosomal breaks RIL 74-wheats. It will allow us to map targeted Architecture candidate genes in low recombination regions and will help in overall wheat improvement.
85 wt.% Bi - Silicone will be irradiated using a 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 Corp.
University to better understand the material property changes after irradiation.
Stark Street Materials Bi-Si Attenuation coefficient Determination of attenuation coefficients for Corp.
determination various gamma energies.
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 hop, 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 of 3D printed samples with University respect to printing directionality Funding Oregon State University Georgia Institute of Technology University of Maryland College Park Stark Street Materials Stark Street Materials Oregon State University NSF
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- o Project Users Organization Name Project Title Description Funding A
Adhezion Biomedical is interested in the effect of Gamma on COC ampoules and the stability of SecurePortIV app with COC Ampoule the product post-irradiation. Analytical testing 2203 Phelps Adhezion Biomedical shall follow on our end after Gamma-irradiation Adhezion Biomedical Gamma-Feasibility Run to determine 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 INL Flash Radiography Camera camera for use in the OSTR Neutron Radiography 2204 Reese Facility. The prototype camera system will be University Development used as part of the INL flash radiography project at 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 2205 Privitera Cosmological Physics DAMIC-M are available. Pellets will be housed in in 0.5 in University of Chicago 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 term potentially for energy generation. This small plasma device 2206 Langtry Avalanche Energy Compact Neutron Generator (12 cm diameter) combines aspects ofan ion trap Avalanche Energy (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.
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Listing of Major Research and Service Projects Preformed or in Progress at the Radiation Center and Their Funding Agencies Organization Name Project Title Description This project is funding by INL through NNSN NA-22 to investigate using soft snake-like School ofNuclear robots for inspection purposes. Soft material Science and Soft Robotics samples (PDMS with a liquid metal paste) will be Engineering irradiated and materials testing performed to better understand the operating constraints of soft robots in radiation environments.
Oregon State Medical Isotope Feasiblity Studies Determination offeasibility making different University medical isotopes using the TRIGA reactor.
Rosebud Sioux Tribe Multielement analysis of fired clay samples via Historic Preservation INAA offired clay samples Office INAA.
Tectonic thermal evolution history of Use of fission track analysis to determine U Peking University Junggar Basin content in the sedimentation of Junggar Basin. To study the thermal history of the basin.
Greentree Synergy INAA of metal products.
Elemental analysis via INAA of finely divided elemental metals.
I 02nd Oregon Civil Isotope production of various sources Production of various sources for training Support 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 INAA 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 oflow-U mica, labeled with a sharpie and bound together with Parafilm.
Oregon State Looking at the effects of control rod heights during Investigating Rod Shaddowing calibrations in comparison to MCNP calucalations University of rod worths.
Funding NNSA Peking University China Earthquake Administration Georgia Institute of Technology
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Project Users Organization Name Project Title Description Funding School of Nuclear Evaluating fission product yields and branching 2217 Palmer Science and High Fidelity Fission Product ratios for intermediate lived fission products.
Lawrence Livermore Engineering Measurements This involves the use of a series of clover HPGe National Laboratory detectors to measure the photon spectrums.
INAA to quantify chemical composition of 2218 Mutin Benjamin Mutin INAA oflranian Pottery archaeological ceramics from ancient Iran to determine provenance.
Pontifcia Ceramic Surcing in N. Highland Chemical analysis of ceramics via INAA to 2219 Dyrdahl Universidad Catolica del Ecuador Ecuador determine provenance In this project we study fission tracks in standard 2220 Arato Georg-August FTAIGE apatite and zircon crystals. For the so-called Georg-August Universitat Gottingen external detector method, the thermal irradiation Universitat Gottingen of the samples is necessary.
Soil blocks and wafers are to be gamma sterlized and returned to Kop-Coat to evaluate KCPP Gamma Treatment of Soil gamma sterilization as alternate to autoclave 2221 Williams Kop-Coat Blocks sterilization. ASTM D1413 recommends "a Kop-Coat radiation level of 2.0 to 2.5 Mrad when usinig radioisotopes or 2.0 to 5.0 Mrad if electiron acceleratiors are used.
2222 Meier OMIC USA Inc Sample Counting Sample counting for export shipments.
OMIC USA Inc This project will examine how fungi that live inside leaves control the decomposition rate of Populus trichocarpa leaves. Leaves will be Oregon State Litter Docomposition by Fungal sterilized of existing microorganisms using Department of Botany 2223 Apigo University Endophytes the Gamma cell 220 60Co gamma irradiator.
and Plant Pathology We will inoculate specific communities of fungi onto the sterilized leaves to understand how specific fungal species affect litter mass loss over time.
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Listing of Major Research and Service Projects Preformed or in Progress at the Radiation Center and Their Funding Agencies Project Users Organization Name Project Title Description Funding We want to sterilize our soil with gamma irradiation to prevent microbial processes 2225 Werth University of Texas Abiotic TCE Reactions in Clay Soil from interfering with our abiotic reactions of University of Texas at Austin interest. The sterilized clay soil will be used in batch experiments to measure its reactivity toward TCE under varying conditions.
Testing concrete curing for Oregon 2226 Reese Oregon State ODOT Concrete Curing Department of Transportation using neutron ODOT University radiography. Imaging specimens in a dry and saturated state.
2227 Alden University of INAA of Archaeological Ceramics Provenance determination of ceramics from OSU Radiation Michigan from Iraqi Kurdistan Iraqi Kurdistan via trace-element analysis.
Center, Mine 2228 Gaspich Oregon State Detection of sodium content in INAA to track sodium content in fish cells as Oregon State University biological materials.
a proxy for cell lysis.
University - FST These samples are sent for thermal neutron Wadia Institute of irradiation for Fission track Dating purpose to 2229 Adlakha 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 2231 Jackson CleanMark Labels Gamma Activation Test sterilize and validate at what point in range of CleanMark Labels sterilization application does the material start to indicate with a different color (Yellow to Pink).
This project uses various thermochronometers to trace the cooling and exhumation history along and across the most important fault 2232 Heberer University of Thermochronology along the system of the European Alps. Among these University of Salzburg lnsubric Line thermochronometers are apatite and zircon Salzburg fission track dating, which is carried out in collaboration with Hannah Pomella from the University oflnnsbruck.
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Listing of Major Research and Service Projects Preformed or in Progress
~
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- o Project Users Organization Name Project Title Description Funding Andluca Detection of trace halogens (Cl, Br, I) in 2233 Wallace Technologies Trace halogen detection by INAA organic materials by Neutron Activation Andluca Analysis.
2234 Reese Oregon State NRF Camera Development Development of a digital camera systems for University the NRF.
Neutron imaging will be used to determine drying behavior of CAC-based pastes among these methods. Within minutes of mixing 2235 Weiss Oregon State Neutron Imaging of Calcium the CAC-based pastes will be placed in the University Aluminate Cements beam in sealed and drying environments. The effect of the drying behavior on the transport, mechanical and physical properties of the fresh CAC-based ternary mixtures.
Analysis of 0.98 g Th(NO3)4-4H2O dissolved Nu Planet in 20 mL water via HPGe to determine the Nu Planet 2237 Adams Pharmaceutical Nu Planet Thorium Validation activities of thorium and associated daughter Pharmaceutical Radioisotopes, Inc.
products (actinium and lead) for validation Radioisotopes, Inc.
purposes.
2238 Qu Envista Holdings Envista polymer sheet Irradiate polymer sheets with several Envista Holdings Corporation predetermined dosages.
Coporation CleanMark to provide indicating ink material via Gamma to OSU to sterilize and validate 2239 Hagen 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 INAA of ceramic shards from the Zayandeh-2240 Rafieri-Alavi rud drainage basin in central Iran dating to from Central Iran the 4th-3rd millennium BC.
WORK Table Vl.3 Summary of Radiological Instrumentation Calibrated to Support OSU Departments OSUDepartment Number of Calibrations Chemistry Radiation Safety Office 16 Vet Med 2
Total 19 Table Vl.4 Summarv of Radioloaical Instrumentation Calibrated to Suooort Other Aaencies Agency Number of Agency Number of Calibrations Calibrations Columbia Memorial Hospital 2
ODOT 5
EPA 1
Oregon Health Sciences University 73 CDI Gateway 2
Oregon Lottery 1
Grand Ronde Hospital 5
Oregon State Fire Marshal 45 Hillsboro Medical Center 7
Oregon Veterinary Referral Associates 1
Hollingsworth & Vose 1
PSU 7
Knife River 3
Radiation Protection Services 42 Lake Health District 5
River Bend Sand & Gravel 2
NETL, Albany 4
Salem Health 20 ODOE 6
Samaritan Health 38 TOTAL 270 Figure Vl.1 Summary of the Types of Radiological Instrumentation Calibrated to Support the OSU TRIGA Reactor and Radiation Center 45 44 40 35 31 30 25 20 18 15 10 5
0 ALPHA GM ION MICRO PERSONAL DETECTORS DETECTORS CHAMBERS METERS DOSIMETERS 2022-2023 69
-W-ords Publications Crossingham, T., Sobczack, K., La Croix, A., Esterle, J.,
Dalton, H., & Hayes, P. (submitted). Detrital or Re-Set? 40Ar/39Ar dating of mica from the Lower Jurassic Precipice Sandstone and Evergreen Formation in the Surat Basin. Australian Journal of Earth Sciences.
Genge, M C; Zattin, M; Witt, C; Derycke, A; Gautheron, C; Mazzoli, S; Petrelli, M; Cogne', N; Bosch, D; Bruguier, O; Marquez, M. (2022). Denudation of the Cordillera and intraplate belt in central Patagonia inferred by detrital multi-dating of foreland basin deposits. Sedimentary Geology, 440, 106237.
Korasidis, V. A., Wallace, M. W., Chang, T., & Phillips, D.
(2023). Eocene paleoclimate and young mountain-building in the Australian Eastern Highlands.
Review of Paleobotany and Palynology, 312, 104875.
Liu, J Q; Chen, L H; Wang, X J; Krmicek, L; Zeng, G; Zhang, X Y; Murphy, D; Dalton, H; Pandey, A; Cha\\apathi Rao, NV. (submitted). Zinc isotopes reveal disparate enriched sources of contemporary lamprophyres in Eastern Dharwar Craton.
Contributions to Mineralogy and Petrology.
Margirier, A., Strecker, M.R., Reiners, P.W., Thomson, S.N.,
Casado, I., George, S.W.M. & Alvarado, A. (2023).
Late Miocene exhumation of the Western Cordillera, Ecuador, driven by increased coupling between the subducting Carnegie Ridge and the South American continent. Tectonics, 42, e2022TC007344.
doi: 10.1029/2022TC007344 Marschalek, J.W., Thomson, S.N., Hillenbrand, C.-D.,
Vermeesch, P., Siddoway, C.S., Carter, A., Nichols, K., Rood, D.H., Venturelli, R., Hammond, S.J..,
Wellner, J.S. & Van de Flierdt, T. (2023, in press).
Geological Insights from the Newly Discovered Granite ofSiflsland between Thwaites and Pine Island Glaciers. Antarctic Science.
70 Murphy, D; Moore, T; Amijaya, D; Anggara, F; Friederich, M; Gainia, C; Trofimovs, J; Dalton, H. (submitted). Late Eocene Rift-Derived magmatism within the Tanjung Formation, Selatan (Borneo), Indonesia. Journal of Asian Earth Sciences.
Okay, A. I., Topuz, G., Kylander-Clark, A. C., Sherlock, S., & Zattin, M. (2022). Late Paleocene-Middle Eocene magmatic flare-up in western Anatolia.
Lithos, 428-429, 106816. doi:10.1016/j.
lithos.2022.106816 Olivetti, V; Belestrieri, M L; Chew, D; Zurli, L; Zattin, M; Pace, D; Drakou, F; Comamusini, G; Perotti, M. (2023). Ice volume variations and provenance trends in the Oligocene-early Miocene glaciomarine sediments of the Central Ross Sea, Antarctica (DSDP Site 270).
Global and Planetary Change. doi:10.1016/j.
gloplacha.2023.104042 Peng, H; Wang, J; Liu, C; Zhao, H; Huang, L; Zhao, X; Zhang, S; Liang, C; Wang, Z; Catto', S; Jiao, X; Zhang, L; Zhang, T; Zhang, D; Zattin, M. (2023).
Long-term and multiple stage exhumation of the Ordos Basin, western North China Craton:
insights from seismic reflection, borehole and geochronological data. Earth Science Review, 238, 104349.
Phillips, D., Clarke, W., & Jaque, A. L. (2022). Age and origin of the West Kimberley Iamproites, Wetsern Australia. Lithos, 432-433, 106913.
Phillips, D; Matchan, E L; Gleadow, A J; Brown, F H; McDougall, I A; Cerling, TE; Leakey, M G; Hergt, J M; Leakey, L N. (2023). 40Ar/39Ar eruption ofTurkana Basin tuffs: millennial-scale resolution constrains palaeoclimate proxy tuning models and hominin fossil ages. Journal of the Geological Society, 180( 4 ), 1-19.
ANNUAL REPORT
WORDS Pomella, H., Klotz, T., Sieberer, A. K., Ortner, H., Wzietek, A., Dunkl, I., & Willingshofer, E. (23-28 April 2023). ): The evolution of a thrust belt within a continental indenter: investigating the internal deformation of the Dolomites Indenter, eastern Southern Alps, in a combined low-temperature thermochronology, field and analogue modelling study. EGUsphere: EGU General Assembly 2023 -
Book of Abstracts., EGU23-12479. Retrieved from https :/ /meetingorganizer.copernicus.org/EGU23/
EGU23-13479.html Reno, B. L., Dalton, H., Weisheit, A., & Phillips, D. (2023).
Thermochronologic constraints on the tectonic and thermal history of the northeastern Aileron Province:
Results from 40Ar/39Ar step-heating of hornblende and biotite. NTGS submission to National Argon Map initiative. NGTS Record 2023-001.
Scott, J., Cooper, A., Craw, D., le Roux, P., Dalton, H., &
Palmer, M. (2023). Basanite cobbles in Pleistocene sediments in Central Otago and their implications for intraplate volcanism and Clutha River paleo-drainage. New Zealand Journal of Geology and Geophysics.
Shea, J., Foley, S., Dalton, H., Lanati, A., & Phillips, D.
(submitted). Mid-Jurassic volcanism at Bokhara River and insights into metasomatism in the lithospheric mantle of the Thomson Orogen, eastern Australia. Australian Journal of Earth Sciences.
Timmerman, M. J., Krmicek, L., Krmickova, S., & Slama, J. (2023). Tonian-Ediacaran evolution of the Brunovistulian microcontinent (Czech Republic) deciphered from LA-ICP-MS U-Pb zircon and 40Ar/39Ar muscovite ages. Precambrian Research, 3 87, 106981. doi: 10.1016/j. precamres.2023.I 06981 Wang, X; Zattin, M; Wang, L; Pang, B; Yang, Y; He, K; Danisik, M; Li, X; Ma, Z; Tao, J; Song, A; Liu, H; Zhang, Y. (n.d.). Cenozoic morphotectonic evolution of the northeastemmost Tibetan Plateau: evidence from detrital thermochronology. Global and Planetary Change, 225, 104131.
Wang, Y., Wang, Y., Yin, J., Thomson, S.N., Xiao, W.,
He, Z., Chen, W., Cai, K., Wu, M. & Meng, Y.
(2023). Mesozoic exhumation of the northern West Junggar, NW China: insights from low-temperature thermochronometers. Tectonophysics, 862, 229939.
doi: 10.1016/j.tecto.2023.229939 2022-2023 Wang, Y., Zuo, R., Cao, K., Xu, X., & Zattin, M. (2022). Late Mesozoic to Cenozoic exhumation of the SE South China Block: constraints from zircon and apatite fission-track thermochronology. Tectonophysics, 838, 229518. doi: 10.1016/j.tecto.2022.229518 Whitney, D.L, Delph, J.R., Thomson, S.N., Beck S.L.,
Brocard, G., Cosca, M.A., Darin, M.H., Kaymakct, N., Meijers, M.J.M., Okay, A., Rojay, B., Teyssier, C.
& Umhoefer, P.J. (2023). Breaking plates: Creation of the East Anatolian fault, the Anatolian plate, and a tectonic escape system. Geology, 51, 5673-677.
doi: 10. l 130/G5121 l.1 Willner, A. P., Anczkiewicz, R., Glodney, J., Pohlner, J.
E., Sudo, M., van Staal, C. R., & Vujovich, G. I.
(2023 ). Interrelated pressure-temperature-time-paths of medium to high pressure metamorphic rocks in the Sierra Pie de Palo (W-Argentina): Evolution of a "hard" collisional wedge during an Ordovician microcontinent-arc collision. Tectonophysics, 859, 229861. doi: I 0.10 I 6/j.tecto.2023.229861 Wu, T; Liu, L; Zhang, W; Wilde, S; Zhang, G; Che, X; Li, C; Lu, J; Tian, L; Song, T; Hong, Y; Zhu, H; Li, Q L; Xiao, X; Dalton, H. (submitted). The enigmatic Challenger Deep formed by subduction of resurfaced seafloor. Science Advances.
Yin, J., Wang, Y., Hodges, K.V., Xiao, W., Thomson, S.N.,
Chen, W., Yuan, C., Sun, M., Cai, K. & Sun, J.
(2023). Episodic long-term exhumation of the Tianshan orogenic belt: new insights from multiple low-temperature thermochronometers. Tectonics, 42, e2022TC007 469. doi: 10.1029/2022TC007 469 Presentations Apigo, A., Salas-Lizana, R., Busby, P., & Oono, R. (August 2023). Biogeography and ecological function of foliar fungal endophytes. Mycological Society of America Annual Meeting. Flagstaff, AZ.
ArslanAzizoglu, G., Kelhofer, N., Dalvi, A., Terry, R. N.,
Schwendeman, S. P., & Prausnitz, M. R. (2023).
Evaluation of Gamma Sterilization as a Terminal Sterilization Method for Contraceptive Drug-Loaded Microneedle Patches. CRS Annual Meeting &
Exposition. Las Vegas, NV.
71
woRDS Betka, P.M., Oryan, B., Steckler, M.S., Mathews, A.,
Thomson, S.N., Rakshit, R., Zoramthara, C.,
Sincavage, R. & Lalremruatfela, C. (2022).
Active tectonics of the Indo-Burman forearc, a revised perspective from new structural and geodetic modeling. Geological Society of America Abstracts with Programs, 54(5). doi: 10.1130/
abs/2022AM-383589 Field, J. (31 July - 3 August 2023). Approaches toward characterization offluoropolymers and residual PFAS prior to thermal degradation, (poster).
Strategic Environmental Restoration and Development Program. Portland, OR.
Fioraso, M., Olivetti, V., Sternai, P., Balestrieri, M. L.,
Cornamusini, G., & Zattin, M. (23-28 April 2023).
Rock melting in slow rifts: the role of surface processes and the case of Victoria Land Basin, Antarctica.
Genge, M., Witt, C., Zattin, M., Bosch, D., Bruguier, 0., &
Mazzoli, S. (23-28 April 2023). Are the long-lasting isotope trends in central Patagonia independent from slab dynamics and upper-plate architecture? EGU General Assembly.
Gusmeo, T; Schito, A; Cavazza, W; Corrado, S; Zattin, M; Alania, V; Enukidze, O; Pace, P;. (19-21 September 2022). Contrasting subsidence-exhumation patterns in the hinterland of the Africa-Eurasia collision zone: the eastern Adjara-Trialeti, western Kura and central Greater Caucasus inverted sedimentary basins (Georgia). Congresso SGI-SIMP. Torino.
Jiao, X., Zattin, M., Olivetti, V., Wang, J., Peng, H., & Catto',
S. (23-28 April 2023). The topographic growth of Tibetan Plateau in Oligocene-Early Miocene:
constraints on the paleo-geography and Yellow River drainage evolution. EGU General Assembly.
Licht, K.J., Mallery, C., Marschalek, J., Perotti, M., Zurli, 72 L., Thomson, S.N., van de Flierdt, T. & IODP Expedition 374 Scientists. (Fall Meeting 2022).
The Rise and Fall of the Late Neogene West Antarctic Ice Sheet in the Central Ross Sea Using a Multianalytical Provenance Approach. American Geophysical Union, (pp. Abstract, Session, PP026).
Margirier, A., Thomson, S. N., Reiners, P. W., & King, G.
(3-8 September 2023). Incision history of Zion Canyon, new constraints from low temperature thermochronology (western margin of the Colorado Plateau, USA). Thermo2023, 18th International Conference on Thermochronology. Riva del Garda, Italy.
Margirier, A., Thomson, S. N., Reiners, P. W., & King, G. E.
(Fall Meeting 2022). Incision history of Zion Canyon, western Colorado Plateau, from new apatite fission track and (U-Th-Sm)/He data (Invited). American Geophysical Union, (pp. Abstract, Session, EP020).
Marschalek, J.W., Biard, P.-H., Sarigulyan, E., Ehrmann, W.,
Hemming, S., Thomson, S., Hillenbrand, C.-D., Licht, K., Tison, J.-L., Allen, C., Marrocchi, Y., Siegert, M.l, and van de Flierdt, T. (n.d.). Byrd Ice Core Debris Constrains the Sediment Provenance Signature of West Antarctic Ice Sheet Collapse. UK Geochemistry Group Research in Progress Meeting. Cambridge.
Olivetti, V; Balestrieri, M L; Zurli, L; Perotti, M; Pace, D; Chew, D; Cornamusini, G; Zattin, M. (19-21 September 2022). Oligocene Miocene ice volume variations in the Ross Sea, Antarctica: insight from a provenance study on core DSDP270 empowered by U-Pb dating, apatite geochemical signature and fission-track data. Congresso SGI-SIMP. Torino.
Peng, H., Wang, J., Liu, C., Jiao, X., Zhang, L., & Zattin, M. (23-28 April 2023). Revealing the hidden Mesozoic exhumation history of the Qinling orogenic belt, Central China: insights from multiple geochronological and geochemical data of the molasse granitic gravels. EGU General Assembly.
Peng, H., Wang, J., Liu, C., Zhang, T., & Zattin, M. (19-21 September 2022). Long-term exhumation of the western North China Craton: insights from seismic, borehole and geochronological data. Congresso SGI-SIMP. Torino.
Phillips, D., & et al. (2023). Determining eruption ages from non-gaussian feldspar 40Ar/39Ar age distributions:
insights from paleoanthropologically significant tuffs in the Turkana Basin, Kenya. International Association ofVolcanology and Chemistry of the Earth's Interior. New Zealand.
ANNUAL REPORT
WORDS Pomella, H., Klotz, T., Sieberer, A.-K., Reiser, M., Tropper, P., & Schuster, R. (13 September 2022). The thermotectonic evolution in front of the Dolomites Indenter. 15th Alpine Workshop. Ljublijana.
Retrieved from https:/ /meetingorganizer.copernicus.
org/alpshop2022/session/44891 #Orals Samim, S., & et al. (2023). Single-grain 4-0Arf39Ar geochronology and LA-ICPMS trace-element geochemistry ofNariokotome Tuffs, Turkana Basin: a tephrochronological toolkit for tu.ff characterization. International Association of Volcanology and Chemistry of the Earth's Interior.
New Zealand.
Savelkouls, A., & et al. (2023). 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 of Volcanology and Chemistry of the Earth's Interior.
New Zealand.
Siddoway, C. S., Thomson, S. N., Cavousie, A., Alfaro, J.,
& Iverson, N. (24-28 April 2023). Inventory ofice-rafted clasts and sediment constituents that pertain to dynamic ice-margin processes and biological productivity, Amundsen Sea region, Antarctica.
EGU General Assembly, (pp. EGU23-9728).
Vienna.
Sieberer, A.-K., Willingshofer, E., Klotz, T., Ortner, H.,
& Pomella, H. (13 September 2022). Internal deformation of the Dolomites Indenter, eastern Southern Alps: A combined field and analogue modelling study. 15th Alpine Workshop. Ljublijana.
Retrieved from https://meetingorganizer.copernicus.
org/alpshop2022/session/44889#Orals Thomson, S. N., Reiners, P. W., He, J., Hemming, S. R., &
Licht, K. J. (3-8 September 2023). End-Eocene to Mid-Miocene uplift and retreat of the central Transantarctic Mountains great escarpment revealed using a regional-scale multiple low-temperature thermochronometer dataset. Thermo2023, 18th International Conference on Thermochronology.
Riva del Garda, Italy.
2022-2023 Whitney, D.L., Delph, J., Teyssier, C., Beck, S.L., Brocard, G.,
Cosca, M.A., Darin, M.H., Kaymack1, N., Meijers, M.J.., Okay, A., Rojay, B., Thomson, S.N. and Umhoefer, P.J. (2022). Development of the Anatolian Plate and Tectonic Escape System. Geological Society of America Abstracts with Programs, 54( 5).
doi: 10. l 130/abs/2022AM-380195 Students Espinel, Leidy Carolina Sandoval. PhD student, University of Padova. "Thermotectonic history of the southernmost Northern Andes." (Advisor Massimiliano Zattin.)
Fioraso, Marco. PhD student, 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." (Co-advisor Valerio Olivetti.)
He, John. PhD student, University of Arizona. Collaboration as part of NSF award PLR #1443556. (Advisor Paul Kapp.)
Jiao, Xiaoqin. PhD student, University of Padova. "Single-grain multi-technique dating of sediments: a new approach to study the uplift and exhumation of the northeastern Tibetan plateau." (Advisor Massimiliano Zattin.)
Kim-Fu, Mitchell. PhD student, Oregon State University.
(Advisor Jennifer Field.)
Klotz, Thomas. PhD student, Universitat Innsbruck. "Fine Constraints of the Continental Indentation Process:
High Resolution Thermo-tectonic Analysis of the Dolomites Indenter (Eastern Southern Alps.)"
(Supervisors Hannah Pomella & Bernhard Fiigenschuh.)
Mallery, Chris. PhD student. Indiana University - Purdue University Indianapolis. Collaboration as part ofNSF award PLR #1443556. (Advisor Kathy Licht.)
Marschalek, Jim. PhD student, Imperial College London, UK.
Collaboration as part of NSF award PLR# 1917009.
(Advisor Tina Van de Flierdt.)
73
woRDS Ojo, Oyewande. Masters student, Oklahoma State University.
Visiting student to the University of Arizona Fission Track Laboratory as part of the NSF AGeS2 Program. (Advisor Daniel Lao Davila.)
Peng, Heng. PhD student, Northwest University of Xi'an.
"Tectono-thermal history of the southern Ordos Basin." (Co-advisor Massimiliano Zattin.)
Samim, Saini. PhD student. "Geochronology and Geochemistry ofNachukui Tuffs, Omo-Turkana Basin, Kenya." (Advisors David Phillips, Erin Matchan, Janet Hergt, Hayden Dalton.)
Savelkouls, Ashley. PhD student. "Constraining the volcanic
- magmatic history of the Koobi Fora Formation in the Omo - Turkana Basin using precise 40Ar/39Ar dating to improve the current stratigraphy."
(Advisors David Phillips, Erin Matchan, Hayden Dalton.)
Taylor, Jennifer. PhD student, University of Minnesota.
Collaboration as part of NSF award PLR#1917009.
(Advisor Christian Teyssier.)
Wzietek, Alexandra. MS student, Universitat Innsbruck.
"Geology along the Valsugana fault system (Dolomites, Italy.)" (Supervisor Hannah Pomella.)
Zhang, Liying. PhD student, China University of Geosciences of Beijing. "Tectonic evolution of the Great Xing'an Range and its relationships with climatic and surface processes."
74 ANNUAL REPORT
Oregon State University Radiation Center, 100 Radiation Center, Corvallis, OR 97331 www.radiationcenter.oregonstate.edu
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