ML18297A120
| ML18297A120 | |
| Person / Time | |
|---|---|
| Site: | Oregon State University |
| Issue date: | 10/19/2018 |
| From: | Reese S Oregon State University |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML18297A120 (82) | |
Text
Oregon State 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 19, 2018
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, 2017 through June 30, 2018.
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: /c b
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I Sincerely, Director Cc:
Michael Balazik, USNRC Craig Bassett, USNRC Ken Niles, ODOE Dr. lrem Turner, OSU Dan Harlan, OSU
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.
CoI1teI1ts Part I-Overview Executive Summary..................................................................................................................................... 4 lntroduction.................................................................................................................................................... 4 Overview of the Radiation Center.......................................................................................................... 4 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.......................................................................................................... 10 Laboratories & Classrooms...................................................................................................................... 10 Instrument Repair & Calibration............................................................................................................ 10 Library............................................................................................................................................................. 10 Part IV-Reactor Operating Statistics.................................................................................................................................... 14 Experiments Performed........................................................................................................................... 14 Unplanned Shutdowns............................................................................................................................. 15 Changes Pursuant to 10 CFR 50.59...................................................................................................... 15 Surveillance & Maintenance................................................................................................................... 16 Part V-Radiation Protection lntroduction.................................................................................................................................................. 28 Environmental Releases........................................................................................................................... 28 Personnel Doses.......................................................................................................................................... 29 Facility Survey Data.................................................................................................................................... 30 Environmental Survey Data.................................................................................................................... 30 Radioactive Material Shipments........................................................................................................... 31 References..................................................................................................................................................... 31 Part VI-Work Summary....................................................................................................................................................... 48 Teaching......................................................................................................................................................... 48 Research & Service..................................................................................................................................... 48 Part VII-Words Documents Published or Accepted..................................................................................................... 71 Presentations................................................................................................................................................ 7 5 Students......................................................................................................................................................... 78
Tables Table Title Page Ill. 1 Gammacell 220 6°Co lrradiator Use............................................ 11 111.2 Student Enrollment in Courses at the Radiation Center............................... 12 IV. 1 Present OSTR Operating Statistics.................. :......................... 17 IV.2 OSTR Use Time in Terms of Specific Use Categories.................................. 18 IV.3 OSTR Multiple Use Time................................................... 18 IV.4 Use of OSTR Reactor Experiments............................................ 19 IV.5 Unplanned Reactor Shutdowns and Scrams...................................... 19 V.1 Radiation Protection Program Requirements and Frequencies.......................... 32 V.2 Monthly Summary of Liquid Effluent Releases to the Sanitary Sewer...................... 33 V.3 Annual Summary of Liquid Waste Generated and Transferred........................... 34 V.4 Monthly Summary of Gaseous Effluent Releases................................... 34 V.5 Annual Summary of Solid Waste Generated and Transferred............................ 35 V.6 Annual Summary of Personnel Radiation Doses Received............................. 36 V.7 Total Dose Equivalent Recorded Within the TRIGA Reactor Facility....................... 37 V.8 Total Dose Equivalent Recorded on Area Within the Radiation Center...................... 38 V.9 Annual Summary of Radiation and Contamination Levels Within the Reactor................. 40 V.10 Total Dose Equivalent at the TRIGA Reactor Facility Fence............................. 41 V.11 Total Dose Equivalent at the Off-Site Gamma Radiation Monitoring Stations................. 42 V. 12 Annual Average Concentration of the Total Net Beta Radioactivity........................ 43 V. 13 Radioactive Material Shipments under NRC General License R-106....................... 44 V. 14 Radioactive Material Shipments under Oregon License ORE 90005....................... 45 V. 15 Radioactive Material Shipments Under NRC General License 10 CFR 1 10.23................. 45 VI. 1 Institutions and Agencies Which Utilized the Radiation Center.......................... 50 Vl.2 Listing of Major Research & Service Projects Performed and Their Funding.................. 55 Vl.3 Summary of Radiological Instrumentation Calibrated to Support OSU Departments............ 69 Vl.4 Summary of Radiological Instrumentation Calibrated to Support Other Agencies............. 70 Figures Table Title Page IV. 1 Monthly Surveillance and Maintenance (Sample Form)................................................................................................. 20 IV.2 Quarterly Surveillance and Maintenance (Sample Form)............................................................................................... 21 IV.3 Semi-Annual Surveillance and Maintenance (Sample Forrri)........................................................................................ 23 IV.4 Annual Surveillance and Maintenance (Sample Form)................................................................................................... 25 V. 1 Monitoring Stations for the OSU TRIGA Reactor.............................................................................................................47 VI. 1 Summary of the Types of Radiological Instrumentation Calibrated.......................................................................... 69
4 Overview Executive Summary The data from this reporting year shows that the use of the Radiation Center and the Oregon State TRIGA reactor (OSTR) has continued to grow in many areas.
The Radiation Center supported 42 different courses this year, mostly in the School of Nuclear Science and Engineering.
About 33% of these courses involved the OSTR. The number of OSTR hours used for academic courses and training was 20, while 3,744 hours0.00861 days <br />0.207 hours <br />0.00123 weeks <br />2.83092e-4 months <br /> were used for research projects. Sixty-eight percent (68%) of the OSTR research hours were in support of off-campus research projects, reflecting the use of the OSTR nationally and internationally. Radiation Center users pub-lished or submitted 70 articles this year, and made 67 presen-tations on work that involved the OSTR or Radiation Center.
The number of samples irradiated in the reactor during this re-porting period was 2,315. Funded OSTR use hours comprised 88% of the research use.
Personnel at the Radiation Center conducted 172 tours of the facility, accommodating 1,617 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 139. Reactor related projects comprised 71 % of all projects.
The total research dollars in some way supported by the Radia-tion Center, as reported by our researchers, was $15.1 million.
The actual total is likely considerably higher. This year the Ra-diation Center provided service to 69 different organizations/
institutions, 32% of which were from other states and 41 % of which were from outside the U.S. and Canada. So while the Center's primary mission is local, it is also a facility with a national and international clientele.
The Radiation Center web site provides an easy way for potential users to evaluate the Center's facilities and capabili-ties as well as to apply for a project and check use charges. The address is: http://radiationcenter.oregonstate.edu.
Annual Report Introduction The current annual report of the Oregon State University Radiation Center and TRIGA Reactor follows the usual format by including information relating to the entire Radiation Center rather than just the reactor. However, the information is still presented in such a manner that data on the reactor may be examined separately, if desired. It should be noted that all annual data given in this report covers the period from July I, 2017 through June 30, 2018. Cumulative reactor operating data in this report relates only to the LEU fueled core. This covers the period beginning July I, 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 Commission, the U.S. Department of Energy, and the Oregon Department of Energy. Because of this, the report is divided into several distinct parts so that the reader may easily find the sections of interest.
Overview of the Radiation Center The Radiation Center is a unique facility which serves the en-tire OSU campus, all other institutions within the Oregon Uni-versity System, and many other universities and organizations throughout the nation and the world. The Center also regularly provides special services to state and federal agencies, particu-larly agencies dealing with law enforcement, energy, health, and environmental quality, and renders assistance to Oregon industry. In addition, the Radiation Center provides permanent office and laboratory space for the OSU School of Nuclear Science and Engineering, the OSU Institute of Nuclear Science and Engineering, and for the OSU nuclear chemistry, radiation chemistry, geochemistry and radiochemistry programs. There is no other university facility with the combined capabilities of the OSU Radiation Center in the western half of the United States.
Located in the Radiation Center are many items of specialized equipment and unique teaching and research facilities.
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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 associat-ed germanium detectors; and a variety of instruments for ra-diation measurements and monitoring. Specialized facilities for radiation work include teaching and research laboratories with instrumentation and related equipment for performing neutron activation analysis and radiotracer studies; laborato-ries for plant experiments involving radioactivity; a facility for repair and calibration of radiation protection instrumenta-tion; and facilities for packaging radioactive materials for shipment to national and international destinations.
A major non-nuclear facility housed in the Radiation Center is the one-quarter scale thermal hydraulic advanced plant ex-perimental (APEX) test facility for the Westinghouse AP600 and API 000 reactor designs. The AP600 and API 000 are next-generation nuclear reactor designs which incorporate many passive safety features as well as considerably simpli-fied plant systems and equipment. APEX operates at pres-sures up to 400 psia and temperatures up to 450°F using elec-trical heaters instead of nuclear fuel. All major components of the AP600 and APIOOO are included in APEX and all systems are appropriately scaled to enable the experimental measurements to be used for safety evaluations and licensing of the full scale plant. This world-class facility meets exact-ing qua! ity assurance criteria to provide assurance of safety as well as validity of the test results.
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.
The Multi-Application Light Water Reactor (MASLWR) is a nuclear power plant test facility that is instrumental in the development of next generation commercial nuclear reactors currently seeking NRC certification. The Test Facility is con-structed of all stain less steel components and is capable of operation at full system pressure ( 1500 psi a), and full system temperature (600F).
All components are 1/3 scale height and 1/254.7 volume scale. The current testing program is examining methods for natural circulation startup, helical steam generator heat transfer performance, and a wide range of design basis, and beyond design basis, accident conditions. In addition, the MASLWR Test Facility is currently the focus of an interna-tional collaborative standard problem exploring the operation and safety of advanced natural circulations reactor concepts.
Over 7 international organizations are involved in this stan-dard problem at OSU.
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 850oC (well mixed helium).
The design will allow for a maximum operating pressure of I.OMPa 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.
2017 - 2018 0 <
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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 Vl.2.
Radiation Center Staff Steve Reese, Director Dina Pope, Office Manager Tara DiSante, Business Manager Erica Emerson, Receptionist S. Todd Keller, Reactor Administrator Celia Oney, Reactor Supervisor, Senior Reactor Operator Robert Schickler, Reactor Engineer, Senior Reactor Operator Scott Menn, Senior Health Physicist Kyle Combs, Health Physicist Leah Mine, Neutron Activation Analysis Manager Steve Smith, Development Engineer, Senior Reactor Operator Chris Kulah, Senior Reactor Operator Erin Cimbri, Custodian Joshua Graves, Reactor Operator (Student)
Trevor Howard, Reactor Operator (Student)
Griffen Latimer, Reactor Operator (Student)
Jackson Keppen, Reactor Operator (Student)
Jadin Swarts, Reactor Oprator (Student)
Quinn Miller, Health Physics Monitor (Student)
Destry Jensen, Health Physics Monitor (Student) 6 Annual Report Reactor Operations Committee Dan Harlan, Chair OSU Radiation Safety Abi Tavakoli Farsoni OSU School of Nuclear Science and Engineering S. Todd Keller OSU Radiation Center Scott Menn OSU Radiation Center Celia Oney (not voting)
OSU Radiation Center Steve Reese (not voting)
OSU Radiation Center Julie Tucker OSU Mechanical, Industrial and Manufacturing Engineering Haori Yang OSU School of Nuclear Science and Engineering
Professional and Research Faculty Seth Caddell Assistant Professor, Senior Research, Nuclear Science and Engineering Farsoni, Abi Associate Professor, Nuclear Science and Engineering
/zabela Gutowska Assistant Professor, Senior Research, Nuclear Science and Engineering
- Hamby, David Professor, Nuclear Science and Engineering Hart, Lucas P.
Faculty Research Associate, Chemistry
- Higley, Kathryn A.
School Head, Professor, Nuclear Science and Engineering Dan LaBrier Assistant Professor, Senior Research, Nuclear Science and Engineering
- Keller, S. Todd Reactor Administrator, Radiation Center Klein, Andrew C.
Professor, Nuclear Science and Engineering
- Krane, Kenneth S.
Professor Emeritus, Physics
- Loveland, Walter D.
Professor, Chemistry Marcum, Wade Associate Professor, Nuclear Science and Engineering
- Menn, Scott A.
Senior Health Physicist, Radiation Center
- Mine, Leah Associate Professor, Anthropology Guillaume Mignot Assistant Professor, Senior Research, Nuclear Science and Engineering Palmer, Camille Research Faculty and Instructor, Nuclear Science and Engineering
- Palmer, Todd S.
Professor, Nuclear Science and Engineering
- Paulenova, Alena Associate Professor, Nuclear Science and Engineering Pope, Dina Office Manager, Radiation Center Ranjbar, Leila Instructor, Nuclear Science and Engineering
- Reese, Steven R.
Director, Radiation Center Reyes, Jr., Jose N.
Professor, Nuclear Science and Engineering
- Celia Oney Reactor Supervisor, Radiation Center Aaron Weiss Faculty Research Assistant, Nuclear Science and Engineering Woods, Brian Professor, Nuclear Science and Engineering Wu, Qiao Professor, Nuclear Science and Engineering Yanez, Ricardo Faculty Research Associate, Chem istry Yang, Haori Assistant Professor, Nuclear Science and Engineering
- OSTR users f or research and/or teaching
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Facilities Research Reactor The Oregon State University TRI GA 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-fi lied 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 column, four beam ports, five sample holding (dummy) fuel elements for special in-core irradiations, an in-core irradiation tube, and a cadmium-lined in-core irradiation tube for experi-ments requiring a high energy neutron flux.
The pneumatic transfer facility enables samples to be inserted and removed from the core in four to five seconds.
Consequently this facility is normally used for neutron activa-tion analysis involving short-lived radionuclides. On the other hand, the rotating rack is used for much longer irradiation of samples (e.g., hours). The rack consists of a circular array of 40 tubular positions, each of which can hold two sample tubes.
Rotation of the rack ensures that each sample will receive an identical irradiation.
The reactor's thermal column consists of a large stack of graphite blocks which slows down neutrons from the 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 ports are tubular penetrations in the reactor's main concrete shield which enable neutron and gamma radiation to stream from the core when a beam port's shield plugs are re-moved. The neutron radiography facility utilized the tangential beam port (beam port #3) to produce ASTM E545 category I radiography capability. The other beam ports are available for a variety of experiments.
8 Annual Report J
If samples to be irradiated require a large neutron fluence, especially from higher energy neutrons, they may be inserted into a dummy fuel element. This device will then be placed into one of the core's inner grid positions which would nor-mally be occupied by a fuel element. Similarly samples can be placed in the in-core irradiation tube (ICIT) which can be inserted in the same core location.
The cadmium-lined in-core irradiation tube (CLICIT) enables samples to be irradiated in a high flux region near the center of the core. The cadmium lining in the facility elimi-nates thermal neutrons and thus permits sample exposure to higher energy neutrons only. The cadmium-lined end of this air-fi lied 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 JCIT except for the presence of the cadmium lining.
The two main uses of the OSTR are instruction and research.
Instruction Instructional use of the reactor is twofold. First, it is used sig-nificantly 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 aca-demic programs. In addition, portions of classes from other Oregon universities were also supported by the OSTR.
Research 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.
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m The OSTR's irradiation facilities provide a wide range of CJ) 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 dat-ing samples.
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 use in both teaching and research applications. In addition, service projects also use these systems and the combined use often results in 24-hour per day schedules for many of the analytical instruments. Use 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.
2017 - 2018 9
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~ Radioisotope Irradiation Sources The Radiation Center is equipped with a I 0,200 curie (as of June, 2015) Gammacell 220 6°Co irradiator which is capable of delivering high doses of gamma radiation over a range of dose rates to a variety of materials.
Typically, the irradiator is used by researchers wishing to perform mutation and other biological effects studies; studies in the area ofradiation chemistry; dosimeter testing; steriliza-tion of food materials, soils, sediments, biological specimen, and other media; gamma radiation damage studies; and other such applications. In addition to the 6°Co irradiator, the Center is also equipped with a variety of smaller 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 III. I provides use data for the Gammacell 220 irradiator.
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 of radiation. 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.
10 Annual Report 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 II 1.2.
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. ln 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.
Library The Radiation Center has a library containing a significant col-lections of texts, research reports, and videotapes relating to nuclear science, nuclear engineering, and radiation protection.
The Radiation Center is also a regular recipient of a great vari-ety of publications from commercial publishers in the nuclear field, from many of the professional nuclear societies, from
the U. S. Department of Energy, the U. S. Nuclear Regula-tory Commission, and other federal agencies. Therefore, the Center library maintains a current collection of leading nuclear research and regulatory documentation. In addition, the Center has a collection of a number of nuclear power reactor Safety Analysis Reports and Environmental Reports specifically prepared by utilities for their facilities.
The Center maintains an up-to-date set of reports from such organizations as the International Commission on Radiologi-cal Protection, the National Council on Radiation Protection and Measurements, and the International Commission on Radiological Units. Sets of the current U.S. Code of Federal Regulations for the U.S. Nuclear Regulatory Commission, the U.S. Department of Transportation, and other appropriate federal agencies, plus regulations of various state regulatory agencies are also available at the Center.
The Radiation Center videotape library has over one hun-dred tapes on nuclear engineering, radiation protection, and radiological emergency response topics. In addition, the Radiation Center uses videotapes for most of the techni-cal orientations which are required for personnel working with radiation and radioactive materials. These tapes are reproduced, recorded, and edited by Radiation Center staff, using the Center's videotape equipment and the facilities of the OSU Communication Media Center.
The Radiation Center library is used mainly to provide ref-erence material on an as-needed basis. It receives extensive use during the academic year. In addition, the orientation videotapes are used intensively during the beginning of each term and periodically thereafter.
Table 111.1 Gammacell 220 6°Co lrradiator Use I
I Dose Range Number of Use Time Purpose of Irradiation Samples (rads)
I Irradiations (hours) wood blocks, crystals, milk, mouse diet, nano-Sterilization fibers, plant material, 5.0xl02 to 5.0xl06 66 395 polymers, serum, soil, cow serum silicon polymers, I
polymers, tourmaline, Material Evaluation gasket material, miner-3.0xl05 to 4.0x107 28 364 als, peroxide solution, plastic capsules Botanical Studies pollen, seeds, liriope 2.0xl03 to 4.0xl04 23
.54 seeds Totals I
I 117 760 2017 - 2018
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12 Course#
NSE 114*
NSE 115 NSE234 NSE235 NSE236*
NSE 311 NSE 312 NSE 319 NSE 331 NSE 332 NSE233 NSE/MP 401/501/601 NSE/MP 405/505/605 NSE/MP 406/506/606 NSE/RHP/MP 407/507/607 NSE/MP 410/510/610 NSE 415/515 NSE 451/551 NSE452/552 NSE 455/555**
NSE 456/556**
NSE 457/557**
NSE467/567 NSE 667 NSE 435/535 NSE 565 NSE473/573 Annual Report Table 111.2 Student Enrollment in Courses Which are Taught or Partially Taught at the Radiation Center Number of Students CREDIT COURSE TITLE Summer I Fall I Winter I Spring 2011 2011 J 2018 2018 I
2 Introduction to Nuclear Engineering and Radiation -
80 I
Health Physics Introduction to Nuclear Engineering and Radiation i
2 I
59 Health Physics I
i 4
Nuclear and Radiation Physics I I
70 4
Nuclear and Radiation Physics II 66 4
Nuclear Radiation Detection & Instrumentation I
56 4
Intro to Thermal Fluids 41 I
6 I
4 Thermodynamics I
34 18 I
___ _J I
Societal Aspects of Nuclear technology J_ 3 I 111 I
4 Intro to Fluid Mechanics I
37 28 I
I I
4 Heat Transfer 19 24 18 I
3 I Mathematical methods for NE/RHP l
i 32 I
1-16 I Research I
31 I
18 17
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I 1-16 I Reading and Conference 12 30 16 15 1-16 Projects,
10 1
Nuclear Engineering Seminar I
84 G_
73 1-12 Internship 1
I 1
2 Nuclear Rules and Regulations 62 I
I 4
Neutronic Analysis 56 I
4 N eutronic Analysis 55 I
3 Reactor Operator Training I I
I 3
Reactor Operator Training II I
I 3
I Nuclear Reactor Lab 42 I
4 Nuclear Reactor Thermal Hydraulics 37 4
Nuclear Reactor Thermal Hydraulics I
3 External Dosimetry & Radiation Shielding 55 3
Applied Thermal Hydraulics I
3 Nuclear Reactor Systems Analysis I
46
Table 111.2 (continued)
Student Enrollment in Courses Which are Taught or Partially Taught at the Radiation Center Course#
CREDIT COURSE TITLE NSE474/574 4
Nuclear System Design I NSE475/575 4
Nuclear System Design II NSE479*
1-4 Individual Design Project NSE481*
4 Radiation Protection NSE 582*
4 Applied Radiation Safety NSE483/583 4
Radiation Biology NSE 488/588*
3 Radioecology NSE 590 4
Internal Dosimetry NSE/MP 503/603*
1 1Thesis NSE 516*
4 Radiochemistry NSE 526 3
Numerical Methods for Engineering Analysis NSE/MP 531 3
Nuclear Physics for Engineers and Scientists NSE/MP536*
3 Advanced Radiation Detection & Measurement NSEIRHP537 3
Digital Spectrometer Design MP541 3
Diagnostic Imaging Physics NSE 550 3
Nuclear Medicine NSE 553 3
Advanced Nuclear Reactor Physics MP563 4
Applied Medical Physics NSE468/568 3
Nuclear Reactor Safety NSE/MP599 Special Topics Course From Other OSU Departments CH233*
5 General Chemistry CH233H*
5 Honors General Chemistry CH462*
3 Experimental Chemistry II Laboratory ENGRlll*
3 Engineering Orientation ENGR212H*
3 Honors Engineering ST Special Topics OSTR used occasionally for demonstration and/or experiments OSTR used heavily Number of Students Summer 1 Fall Winter Spring 2016 I 2016 2017 2017 43 I 43 I
I I
_J 62 I
9 I
I 12 I
I I
13
*-** i I
6 I
I 28 I
48 50 I 54 1-+
6 I l!Ll I
15 8
I 17 I
I I
I 1*
I 12 I
4 I
I 8
I 18 16 I
7 I
I 118 I I
873 I
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2017 - 2018 13
14 Reactor Operating Statistics During the operating period between July 1, 2016 and June 30, 2017, the reactor produced 1438 MWH of thermal power during its 1579 critical hours.
Experiments Performed During the current reporting period there were ten 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-36 Irradiation of fissionable materials in the OSTR.
Of these available experiments, four were used during the reporting period. One additional experiment (B-35, Irradiation of Fissile Materials in the Prompt Gamma Neutron Activation Analysis (PGNAA) Facility) was used during the reporting period and later discontinued (see below). 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 of TRIG A's Reactor Bath Water Tem-perature Coefficient and High Power Level Power Fluctuation.
Annual Report B-1 B-2 B-4 B-5 B-6 B-7 B-8 B-9 B-10 B-11 B-12 B-13 B-14 B-15 B-16 B-17 B-18 B-19 B-20 B-21 B-22 B-23 B-24 B-25 B-26 B-27 B-28 Activation Analysis of Stone Meteorites, Other Mete-orites, and Terrestrial Rocks.
Measurements of Cd Ratios of Mn, In, and Au in Thermal Column.
Flux Mapping.
In-core Irradiation of Foils for Neutron Spectral Mea-surements.
Measurements of Neutron Spectra in External Irradia-tion Facilities.
Measurements of Gamma Doses in External Irradia-tion Facilities.
Isotope Production.
Neutron Radiography.
Neutron Diffraction.
Irradiation of Materials Involving Specific Quantities of Uranium and Thorium in Standard OSTR Irradia-tion Facilities. (Discontinued Feb. 28th, 2018)
Exploratory Experiments. (Discontinued Feb. 28th, 2018)
This experiment number was changed to A-7.
Detection of Chemically Bound Neutrons.
This experiment number was changed to C-1.
Production and Preparation of 18F.
Fission Fragment Gamma Ray Angular Correlations.
A Study of Delayed Status (n, y) Produced Nuclei.
Instrument Timing via Light Triggering.
Sinusoidal Pile Oscillator.
Beam Port #3 Neutron Radiography Facility.
Water Flow Measurements Through TRIGA Core.
Studies Using TRIGA Thermal Column. (Discontin-ued Feb. 28th, 2018)
General Neutron Radiography.
Neutron Flux Monitors.
Fast Neutron Spectrum Generator.
Neutron Flux Determination Adjacent to the OSTR Core.
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 Pu02 Transient Experiment.
Unplanned Shutdowns There were 2 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:
18-01, Experiments Update This evaluation implemented one new experiment (B-36) and made six other experiments inactive (B-11, B-12, B-23, B-33, B-34, and B-35). The evaluation also made minor corrections to experiments B-3 and B-31 to bring them up-to-date with Technical Specifications and current practices.
There were 26 new screens performed in support of the reac-tor this year. They were:
17-10 Changes to OSTROPs 14, 17, 21, and 23 Minor updates and clarifications to the procedures for quarterly surveillance and maintenance, the reactor room ventilation system, reporting of defects and noncompliance, and crane operation.
17-11 Clamp Modifications Allowed the installation of new fixtures to secure in-core irradiation tubes to the reactor bridge.
17-12 Changes to OSTROP 11 Minor updates and clarifications to the procedure for fuel element handling.
17-13 Air Compressor Replacement Allowed a new air compressor to be installed in the heat exchanger room following the failure of the old air compressor.
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17-14 Changes to RCHPP 34
- 0 Minor updates and clarifications to the procedures for Radiation Center orientation and training.
17-15 CAM Flow Control Valves Allowed replacement of the flow control valves on both Continuous Air Monitors (reactor top and exhaust stack). The new valves have a limited range of rotation to prevent overshooting when used for automatic flow control.
17-16 Changes to OSTROP 4 Minor updates and clarifications to the procedures for reactor operation.
Moved some information from OSTROP 6 to OSTROP 4 to improve procedure organization.
17-17 Changes to OSTROP 6 Minor updates and clarifications to the administrative and personnel procedures. Moved some information from OSTROP 6 to other proce-dures to improve procedure organization.
17-18 Changes to OSTROP 10 Minor updates and clarifications to the procedures for operation of experimental facilities.
17-19 Changes to OSTROP 15 Minor updates and clarifications to the procedures for semi-annual surveillance and maintenance.
17-20 Changes to OSTROP 18 and Appendix A Minor updates and clarifications to the procedures for approval and use of reactor experiments, and for irradiating a sample in the OSTR.
17-21 Changes to OSTROP 19 Minor updates and clarifications to the procedures for equipment main-tenance and calibration.
17-22 Changes to OSTROP 22 Minor updates and clarifications to the procedures for the emergency power system.
17-23 Changes to OSTROP 25 Minor updates and clarifications to the procedures for reporting require-ments.
17-24 Changes to OSTROP 1 Minor updates and clarifications to the annunciator response procedures.
17-25 Changes to OSTROP 5 Minor updates and clarifications to the procedures for maintaining operational records.
17-26 Changes to OSTROP 9 Minor updates and clarifications to the procedures for control rod cali-bration.
2017 - 2018 15
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17-28 Changes to OSTROP 16 Minor updates and clarifications to the procedures for annual surveil-lance and maintenance.
17-29 Changes to 0STROP7 Minor updates and clarifications to the procedures for operation of reactor water systems.
17-30 Cancellation ofOSTROPs 28, 29, and 30 Cancelled the procedures for receipt of new fuel, core reload and initial startup, and replacement of the annular reflector. There are no plans to perform any of these procedures in the foreseeable future, and OSTROPs 29 and 30 were written as single-use procedures.
18-01 Changes to RCHPP 21 Minor updates and clarifications to the procedures for operating the gamma irradiation facility.
18-02 Changes to OSTROPs Minor updates and clarifications to the procedures for the reactor startup and shutdown checklists, monthly surveillance and mainte-nance, control and accounting of special nuclear material, and scan-ning documents for permanent archival storage and retrieval.
18-03 Changes to OSTROPs Minor updates and clarifications to the procedures for reactor power calibration, fuel element handling, quarterly surveillance and mainte-nance, reporting of defects and noncompliance, and crane operation.
18-04 Primary Water Temporary Makeup System Allowed removal of the demineralizer makeup and flush system in preparation for upgrading the reactor cooling water systems. Also covered the installation and operation of a temporary water makeup system, using city water passed through a temporary resin bed.
18-05 Changes to RCHPP 6 Updated the name and contact information of the company used as the Emergency Contact for hazardous materials shipments Surveillance and Maintenance Non-Routine Maintenance July 2017 The air compressor in the heat exchanger room was re-placed.
A new core configuration was implemented, with a second cadmium-lined irradiation facility in position F-20 and several additional fuel elements.
16 Annual Report August 2017 Repairs were performed on one of the new CLICIT tubes
(#4) after an imperfection in the tube caused a saddle and a fishing pole grapple to become stuck in the tube.
Septem her 2017 Some built-up corrosion was found on the safety rod's electromagnet during biennial inspection. The magnet was cleaned before the rod drive was reassembled.
October 2017 A leaking air hose on the transient rod air supply was replaced.
The flow control valve on the reactor top continuous air monitor was replaced.
November 2017 All fuses on the air compressor were replaced.
The primary demineralizer resin was replaced.
December2017 An oil change was done on the air compressor.
New bearings and a new fan pulley were installed on the Dl00 fan.
January 2018 A seal and bushing were replaced on the secondary water pump to fix a small water leak.
March 2018 A new replacement fan for D 100 was installed in the fourth floor fan room.
The "rod down" limit switch on the transient rod was replaced.
A new sink was installed in the SE comer of the reactor bay.
May2018 A faulty terminal block on the reactor top continuous air monitor was bypassed.
June 2018 A temporary resin bed was attached to the city water sup-ply and the demineralizer loop in the heat exchanger room to allow water to be added to the primary tank during the secondary system upgrade.
The resin dewatering bed, makeup tank, and some associ-ated piping were removed from the heat exchanger room.
Table IV.1 Present OSTR Operating Statistics Operational Data For LEU Core Annual Values (2016/2017)
MWH of energy produced 1,542 MWD of energy produced 64.2 Grams 235U used 87 Number of fuel elements added to ( +) or removed(-) from
+2 the core Number of pulses 22 Hours reactor critical 1,604 Hours at full power (1 MW) 1,518 Number of startup and shutdown checks 247 Number of irradiation requests processed 272 Number of samples irradiated 2315 I
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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)
I 20 13,733 1~.058 OSU research 21,374 Off campus research 2,686 52,769 Facility time 182 7,536 Total Reactor Use Time 3,946 95,412 Table IV.3 OSTR.Multiple Use Time Annual Values (hours) T-Cumulative Values Number of Users (hours)
Two 443 I
10,892 I
Three 290 5,826 Four 207 I
3,131 I
Five 107 I
1,150 Six 62 341 Seven 7
78 Eight 0
3 Total Multiple Use Time 1,116 21,421 18 Annual Report
1: * * * * * * *
- Experiment Number A-1 B-3 B-31 B-35 B-36 Total Type of Event I
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Table IV.4 Use of OSTR Reactor Experiments I I Research Teaching I
Facility Use 1
6 4
232 I
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12 2
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20 Table IV.5 Unplanned Reactor Shutdowns and Scrams r
Number of 0
Cause of Event ccurrences I
_H_ig_h_v_o_I_ta-ge_1_s_cr_am _______
1 ___ 1 Test button hit by clipboard Period scram 1
Excessive rod withdrawal on startup Total 11 246 12 2
1 272 2017 - 2018
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Figure IV.1 Monthly Surveillance and Maintenance (Sample Form)
OSTROP 13, Rev. LEU-6 Surveillance & Maintenance for the Month of SURVEILLANCE & MAINTENANCE TARGET DATE LIMITS ASFOUND NOTTO BE
[SHADE INDICATES LICENSE REQUIREMENT]
DATE EXCEEDED*
MAXIMUM HIGH:
INCHES 1
REACTOR TANKHIGHANDLOWWATER MOVEMENT LOW:
INCHES LEVEL ALARMS
+/-3 INCHES ANN:
2 BULK WATER TEMPERATURE ALARM CHECK FlJNGTIONAL Tested@ __
3A CHANNEL TEST OF STACK CAM GAS CHANNEL 8.5xl04+/-
Ann.?
_cpm Ann.
8500 cpm 3B CHANNEL TEST OF STACK CAM PARTICULATE 8.5xl04+/-
Ann.?
Ann.
CHANNEL
.8500 cpm
_cpm 3C CHANNELTESTOFREACTORTOPCAM 8.5xl04+/-
Ann.?
- Arin.
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 10 PRIMARY PUMP BEARING OIL LEVEL CHECK OSTROP 13.10 NEED OIL?
NIA 11 EMERGENCY DIESEL GENERATOR CHECKS
>50%
Oil ok?
NIA Visual Hours 12 RABBIT SYSTEM RUN TIME Total hours/Hours NIA on current brushes 13 OIL TRANSIENT ROD BRONZE BEARING WD40 NIA 14 CRANE INSPECTION Hooks Hoist NIA Rope 15 WATER MONITOR CHECK RCHPP 8 App. F.4 NIA
- Date not to be exceeded is only applicable to shaded items. It is equal to the time completed last month plus six weeks.
REACTOR in the year of 20 __
DATE REMARKS COMPLETED INITIALS
- ~****1
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00 Figure IV.2 Quarterly Surveillance and Maintenance (Sample Form)
OSTROP 14, Rev. LEU-5 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 1
REACTOR OPERAT~ON 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 1"/HR+/- 0.2 7B CHECK FILTER TAPE SPEED ON CAM MONITOR l"/HR+/-0.2 8
INCORPORATE 50.59 & ROCAS 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 IO FUNCTIONAL LIGHT PANEL ANN
- 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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REACTOR Figure IV.2 (continued>
Quarterly Surveillance and Maintenance (Sample Form)
OSTROP 14, Rev. LEU-5 Surveillance & Maintenance for the 1st / 2nd I 3rd I 4th Quarter of 20 SURVEILLANCE & MAINTENANCE LIMITS ASFOUND DATE REMARKS&
[SHADE INDICATES LICENSE REQUIREMENT]
COMPLETED INITIALS OPERATOR NAME a) TOTAL OPERATION TIME b) DATE OF OPERATING EXERCISE REMARKS & INITIALS a) 2:4 hours: at console (RO), at console or as Rx.
Sup. (SRO) 11 b) Date Completed Operating Exercise
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00 Figure IV.3 Semi-Annual Surveillance and Maintenance (Sample Form)
OSTROP 15, Rev. LEU-3 Surveillance & Maintenance for the 1st / 2nd Half of 20 SURVEILLANCE & MAINTENANCE TARGET DATE NOT DATE REMARKS
[SHADE INDICATES LICENSE REQUIREMENT]
LIMITS ASFOUND DATE TOBE COMPLETED EXCEEDED*
INITIALS NEUTRON SOURCE COUNT RATE INTERLOCK NOWITHDRAW
~5 cps TRANSIENT ROD AIR INTERLOCK NO PULSE CHANNEL TESTS PULSE MODE ROD MOVEMENT INTERLOCK NOMOVEMENT 1
OF REACTOR
. PULSE INTERLOCK ON RANGE 'SWITCH INTERLOCKS NO PULSE MAXIMUM PULSE REACTIVITY INSERTION LIMI.T
~ $2.25 TWO ROD WITHDRAWAL PRHOHIBr:r
!ONLY PULSE PROHIBIT ABOVE 1 kW
~!kW 2
SAFETY PERIOD SCRAM
~3 sec CIRCUIT TEST PREVIOUS PULSE DATA FOR COMPARION go%
PULSE# --
PULSE#
3 TEST PULSE CHANGE MW MW oc oc 4
CLEANING & LUBRICATION OF TRANSIENT ROD CARRIER INTERNAL BARREL 5
LUBRICATION OF BALL-NUT DRIVE ON TRANSIENT ROD CARRIER 6
LUBRICATION OF THE ROTATING RACK BEARINGS WD-40 7
CONSOLE CHECK LIST OSTROP 15.Vll 8
INVERTER MAINTENANCE See User Manual 9
STANDARD CONTROL ROD MOTOR CHECKS L0-17 Bodine Oil
- Date not to be exceeded is only applicable to shaded items. It is equal to the date last time plus 7 1/2 months.
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Semi-Annual Surveillance and Maintenance (Sample Form)
OSTROP 15, Rev. LEU-3 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 INITIALS EXCEEDED*
(SAFETY CHANNEL) 10 ION CHAMBER RESISTANCE MEASUREMENTS WITH MEGGAR INDUCED VOLTAGE
(%POWER CHANNEL)
@ lOOV. I=
AMPS FISSION CHAMBER RESISTANCE
@900V.I=
AMPS NONE 11 BOOV (Info Only)
CALCULATION R=--
~I=
AMPS
~I R=
n HIGH 12 FUNCTIONAL CHECK OF HOLDUP TANK WATER LEVEL ALARMS OSTROP 15.XII FULL BRUSH INSPECTION INSPECTION OF THE PNEUMATIC TRANSFER 13 SYSTEM Observed SAMPLE INSERTION AND WITHDRAWAL TIME CHECK insertion/withdrawal time
- Date not to be exceeded is only applicable to shaded items. It is equal to the date last time plus 7 1/2 months.
N 0
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00 Figure IV.4 Annual Surveillance and Maintenance (Sample Form)
OSTROP 16, Rev. LEU-2 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 OSTROP16.2 NORMAL 3
CONTROL ROD CALIBRATION:
CLICIT OSTROP9.0
!CIT/DUMMY TRANS SAFE SHIM REG CONTROL ROD SCRAM
- 2 sec 4
WITHDRAWAL INSERTION &
W!D
<50 sec SCRAM TIMES INSERT
- so sec FUEL ELEMENT INSPECTION FOR SELECTED 2
- 20% FE s mspected.
5 ELEMENTS No damage ii or wP.11 6
REACTOR POWER CALIBRATION OSTROP8 7
FUEL ELEMENT TEMPERATURE CHANNEL Per Checklist CALIBRATION 8
CALIBRATION OF REACTOR TANK WATER TEMP OSTROP 16.8 TEMPERATURE METERS CONTINUOUS Particulate Monitor 9
AIR MONITOR RCHPP 18 CALIBRATION Gas Monitor 10 CAM OIL/GREASE MAINTENANCE 11 STACK MONITOR Particulate Monitor RCHPP CALIBRATION Gas Monitor 18 &26 12 STACK MONITOR OIL/GREASE MAINTENANCE 13 AREA RADIATION MONITOR CALIBRATION RCHPP 18
- 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 reauirements it is eaual to the date comoleted last time olus 2 1/2 vears.
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REACTOR Figure IV.4 (continued)
Annual Surveillance and Maintenance (Sample Form)
OSTROP 16, Rev. LEU-2 Annual Surveillance and Maintenance for 20 SURVEILLANCE AND MAINTENANCE AS TARGET DATE NOT DATE REMARKS
[SHADE INDICATES LICENSE REQUIREMENT]
LIMITS FOUND DATE TOBE COMPLETED
& INITIALS EXCEEDED*
NORMAL$
14 CORE EXCESS
- $7.55
!CIT$
CLICIT $
DAMPERS 18TFLOOR 15 REACTOR BAY VENTILATION SYSTEM SHUTDOWN TEST CLOSEIN
C -
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m 0 -I -0 Facility operating personnel include the reactor operations and Z 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.
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.
2017 - 2018 29
z 0
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Q. The OSTR Technical Specifications require an annual sum-Z mary of the radiation levels and levels of contamination Q 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.
0::: 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 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 ofradiological 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 ofradiation sources and radioactive materials. A third objective, which is really derived from successful execution of the first two objectives, is to gather and document information which will help to ensure that all phases of the operational and radiation protection programs are meeting the goal of keeping radiation doses to personnel and releases of radioactivity to the environment "as low as reasonably achievable" (ALARA).
30 Annual Report The annual summary of radiation and contamination levels measured during routine facility surveys for the applicable reporting period is given in Table V.9.
Environmental Survey Data The annual reporting requirements of the OSTR Technical Specifications include "an annual summary of environmental surveys 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.
From Table V.10 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.1) 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 of TLD samples during the cur-rent 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. 1, 2).
Soil, Water, and Vegetation Surveys The soil, water, and vegetation monitoring program consists of the collection and analysis of a limited number of samples in each category on a annual basis. The program monitors highly unlikely radioactive material releases from either the TRI GA 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. I.
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 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 con-centration. Table V.13 gives the concentration and the range of values for each sample category for the current reporting period.
As used in this report, the LLD has been defined as the amount or concentration of radioactive material (in terms of
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 conducted 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 consis-tent with naturally occurring radioactivity and comparable to values reported in previous years.
Radioactive Materials Shipments
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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 of Ionizing 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).
2017 - 2018 31
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~
32 TableV.1 Radiation Protection Program Requirements and Frequencies Frequency Radiation Protection Requirement
+--------------*-*------------------*-----*-------*
Daily/Weekly/Monthly Monthly As Required Quarterly Semi-Annual Annual Annual Report I
Perform Routing area radiation/contamination monitoring Collect and analyze TRI GA primary, secondary, and make-up water.
Exchange personnel dosimeters and inside area monitoring 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.
Issue radiation work permits and provide health physics coverage for maintenance operations.
Prepare, exchange and process environmental TLD packs.
Conduct orientations for classes using radioactive materials.
Collect and analyze samples from reactor stack effluent line.
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.
I Calibrate portable radiation monitoring instruments and personnel pocket ion chambers.
I Calibrate reactor stack effluent monitor, continuous air monitors, remote area radiation 1
1 monitors, and air samplers.
Measure face air velocity in laboratory hoods and exchange dust-stop filters and HEPA j filters as necessary.
Inventory and inspect Radiation Center emergency equipment.
Conduct facility radiation survey of the 6°Co irradiators.
Conduct personnel dosimeter training.
Update dec_ommissioning logbook.
Collect and process environmental soil, water, and vegetation samples.
N 0
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~
00 w
w TableV.2 Monthly Summary of Liquid Effluent Release to the Sanitary Sewer<1>
Specific Activity for I
Total E. h D t bl R d.
Total Quantity of Average Percent of Applicable
~ t 1 Vi 1 Date of ac e ecta e a 10-I o a o ume Quantity of D
bl I'd.
Each Detectable Concentration Monthly Average fL'
'd Effi t
Discharge etecta e nuc 1 e m o
tqm uen Radtonuchde Of Released Concentration for Radioactivity Radtonuchde m the Waste, Where the R 1 d. h R d.
M
. 1 R 1 d R d.. f
!Released Includmg (Month and e ease m t e a 10act1ve atena e ease a 10ac 1ve Released the Waste Release Concentration W: t t th p. t fR 1 I M t. 1 Dtluent Year)
I (Curies) 7 as e a
e om o e ease a ena Was> 1 x 10-(C. )
( C' 1_1)
(o/c )<2>
(gal)
( µCi m}-l) unes
µ 1 m I
o H-3 H-3, 2.50xlo-s H-3, 3.79x10-s H-3, 0.004 I
174,353 Aug2017 I 2.sox10-5 H-3, Co-60, H, 3.96xl0-5 H-3, 1.20x10-7 H-3, 0.0012 Jan 2018 4.lOxI0-5 H-3, 1.20x10-1 Co-60, 1.32xl 0-6 Co-60, 3.98xl0-8 Co-60, 1.33xl 0-2 87,440 U-235 U-235, l.24x10-1 U-235, 3.74x10-10 U-235, l.25x10-2 Annual Total H-3, Co-60, H-3, 6.46xl0-5 I for Radiation 6.60xl0-5 H-3, l.20xl0-1 Co-60, l.32x10-6 I l.98xl0-7 0.031 261,793 Center U-235
_ U-234, l.24x10-1 I (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.
NOll.03l.O~d NOll.'110'1~
z 0 -....
0 w 6 --------
TableV.3 a::
- a. z 0 -
~ -0 <
a::
Annual Summary of Liquid Waste Gen'!rated and Transferred Origin of Liquid Waste Volume of Liquid Detectable Total Quantity of 1
1 Dates of Waste Pickup Waste Packaged(Il Radionuclides Radioactivity in the j for Transfer to _the
(
11
)
l*n the W:aste W: t (C. )
Waste Processmg
- --------+---ga-ons l---------+----a_s_e __
u_n_es--+---F_*_r! __ _
_L -***
I ac11 3.0 I
Radiation Center Laboratories TOTAL Pu-239
__j Sr-85 3~;;---
J---~-ee-ab_o_v_e ____ _
10/31/17 2.72xl0*7 6/15/18 2.72x10*7 l
(I)
OSTR and Radiation Center liquid waste is picked up by the Radiation Safety Office for transfer to its waste processing facility for final
- packaging.
TableV.4 Monthly TRIGA Reactor Gaseous Waste Discharges and Analysis Estimated Fraction of the Technical Total Total Atmospheric Diluted Estimated Estimated Quantity of l
Specification Month Concentration of Annual Average I
Activity Argon-41 Argon-41 at Point of Released (Curies)
Released<1l (Curies)
Release Argon-41
(µCi/cc)
Concentration Limit (%)
July I
1.71 1.71 I
1.33xl0*7 3.33 August 2.07 2.07 I
l.62x10*7 4.05 September I
1.63 1.63 l.31x10:7 3.28 I
I l.70xl0*7 r
October I
2.17 L
2.17 I
4.24 November --r---
1.80 1.80 1.45xl0*1 I
3.63 I
December 2.14 2.14 l.67xl0*7 4.19 January 2.35 2.35 l.83xl0*7 I
4.58 I
I l.98xl0*7 I
February 2.27 2.27 I
4.94 I
March 2.25 2.25 l.76x10*1 I
4.39 l
April I
2.29 2.29 l.85x10*7 I
4.61 May 1.84 1.84 l.44xl0*7 3.59 June 2.26 2.26 l.82xl0*7 4.55 I
TOTAL I
('17-'18) 24.78 24.78 l.65xl0*7<2J 4.12 (I) Routine gamma spectroscopy analysis of the gaseous radioactivity in the OSTR stack discharge indicated the only detectable radionuclide was argon-41.
(2) Annua!Average.
34 Annual Report
ie I
- 1*,. i. !.
- e * * * * * * * * * * * * * * * * * * * * * * * * *
- TableV.5 Annual Summary of Solid Waste Generated and Transferred Volume of Detectable Total Quantity Dates of Waste Pickup Origin of Solid Waste Radionuclides of Radioactivity for Transfer to the OSU Solid Waste Packaged<1l in the Waste in Solid Waste Waste Processing (Cubic Feet)
(Curies)
Facility Co-60, Zn-65, Sc-46, Co-58, Mn-54, 10/31/17 TRIGA Reactor 52.9 Sb-124, Se-75, Eu-154, Ce-144, 1.67x10-2 4/24/18 Facility Am-243, Ag-llOm, H-3, Cr-51, I
Cs-134, Sr-85 I I 6/5/18 Pu-239, Am-243, Eu-152, Eu-154, 10/31/17 Radiation Cs-134, Th-228, H-3, Cf-252, Center 34 Th-232, Np-237, U-238, U-235, 5.0lxIQ-4 4/24/18 Laboratories Natural U, Co-60, H-3, Pu-242, Am-241, Cs-137, Sr-90 6/5/18 TOTAL I
86.9 See Above 1.72xl0-2 (I) OSTR and Radiation Center laboratory waste is picked up by OSU Radiation Safety for transfer to its waste processing facility for final packaging.
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c..
Table V.6 z
Q Annual Summary of Personnel Radiation Doses Received
!i -C <
a:
Personnel Group Facility Operating Personnel Key Facility Research Personnel Facilities Services Maintenance Personnel Laboratory Class Students Campus Police and Security Personnel Visitors Average Annual Dose<1>
Whole Body Extremities I
(mrem)
(mrem)
I I
I I I I
I 138 234 I
ND~J 40 I I -1 ND NIA I
I 6
I 16 I
I I I
I I
I I
ND NIA I
1 NIA Greatest Individual I
Total Person-mrem Dose(!>
I for the Group<1>
Whole Body Extremities Whole Body Extremities (mrem)
(mrem)
(mrem)
(mrem) 1 I
268 820 I
1,102 I
1,871 I
I I
ND I
357 ND 109 ---t---*-*----
I ND I
NIA I
ND NIA I
I r
248 110 I
625 369 I
I I
I I
I I
I I
I NIA I
NIA ND I
NIA I
I I
I r
90 NIA I
289 I
NIA I
I I
I I I
(I) "NIA" indicates that there was no extremity monitoring conducted or required for the group.
36 Annual Report
Table V.7 Total Dose Equivalent Recorded on Area Dosimeters Located Within the TRIGA Reactor Facility Total Dose Equivalent<1J<2l Monitor TRI GA Reactor Recorded I.D.
Facility Location XB(y)
I Neutron (See Figure V.l)
(mrem)
(mrem)
MRC1NE D104:
North Badge East Wall 196 I
ND MRCTSE D104:
South Badge East Wall 101 ND MRCTSW D104:
South Badge West Wall 641 I
ND MRCTNW D104:
North Badge West Wall 347 ND MRCTWN I D104:
West Badge North Wall 574 ND MRCTEN I D104:
East Badge North Wall I
272 ND
~---
MRCTES I D104:
East Badge South Wall 2,361 ND MRCTWS D104:
West Badge South Wall 583 ND MRCTTOP D104:
Reactor Top Badge 1,417 ND MRCTHXS I D104A: South Badge HX Room 876 ND MRCTHXW D104A: West Badge HX Room 333
~
ND MRCD-302 D302:
Reactor Control Room 504 ND I D302A:
MRCD-302A Reactor Supervisor's Office 114 ND MRCBPl I Dl04: Beam Port Number 1 I
549 ND I D104:
MRCBP2 Beam Port Number 2 202 ND MRCBP3 D104: Beam Port Number 3 1,364 ND MRCBP4 Dl04: Beam Port Number 4 1,353 ND (1) The total recorded dose equivalent values do not include natural background contribution and reflect the summation of the results of four quarterly beta-gamma dosimeters or four quarterly fast neutron dosimeters for each location. A total dose equivalent of"ND" 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 Jess 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 i:adiation exposure through an exterior wall directly into an unrestricted area. ----
2017 - 2018
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I 38 TableV.8 Total Dose Equivalent Recorded on Area Dosimeters Located Within the Radiation Center I
Total Recorded Monitor Radiation Center Dose Equivalent<1l I
Facility Location I
I.D.
I (See Figure V.l)
XB(y)
Neutron (mrem)
(mrem)
MRCAIOO I AlOO:
Receptionist's Office 0
ND MRCBRF A 102H: Front Personnel Dosimetry Storage Rack 0
ND I
MRCA120 A120:
Stock Room 21 ND MRCA120A A120A: NAA Temporary Storage 117 ND MRCA126 A126:
Radioisotope Research Laboratory 238 ND MRCC0-60 A128:
. 6°Co Irradiator Room 1,096 ND MRCA130 I A130:
Shielded Exposure Room f---
12 I
ND I A132:
MRCA132 TLD Equipment Room 0
ND I A138:
_J _____
I MRCA138 Health Physics Laboratory 0
I ND MRCA146 I A146:
Gamma Analyzer Room (Storage Cave) 86 ND MRCBIOO BIOO:
Gamma Analyzer Room (Storage Cave) i 167 I
ND I I MRCB114 Bl14:
Lab (226Ra Storage Facility)
I 0
j-ND MRCB119-l Bl19:
Source Storage Room r
31 ND MRCB119-2 Bl19:
Source Storage Room 969 ND MRCB119A B119A: Sealed Source Storage Room 2,814 I
577 j B120:
I I
MRCB120 Instrument Calibration Facility 226 I
ND MRCB122-2 B122:
Radioisotope Hood 187 I
ND MRCB122-3 B122:
Radioisotope Research Laboratory 30 I
ND MRCB124-1 I B124:
Radioisotope Research Laboratory (Hood) 158 ND MRCB124-2 Radioisotope Research Laboratory 0
ND B124:
MRCB124 6 B 124.
Rad101sotope Research Laboratory 0
ND MRCB128 B 128:
Instrument Repair Shop 0
ND MRCB136 Bl36 GammaAnalyzerRoom O
~
_MR c_c_1_o_o ___
~_c_10_0_:_R_ad_i_at_io_n_C_e_n_t_er_D_1_*re_c_to_r_'s_O_fli_c_e _______ ----'1---0---I 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 reporting period was less than the vendor's gamma dose report-ing threshold of IO mrem or that each of the fast neutron dosimeters was less than the vendor's threshold of IO mrem. "NIA" indicates that there was no neutron monitor at that location.
Annual Report
Monitor I.D.
MRCC106A MRCC106B MRCC106-H MRCC118 MRCC120 MRCFlOO MRCF102 MRCB125N MRCN125S MRCC124 MRCC130 MRCDlOO MRCD102 MRCD102-H MRCD106-H MRCD200 MRCD202 MRCBRR MRCD204 MRCATHRL MRCD300 MRCA144 Table V.8 <continued>
-Total Dose Equivalent Recorded on Area Dosimeters Located Within the Radiation Center Total Recorded Radiation Center Dose Equivalent<I)
Facility Location (See Figure V.1)
XB(y)
Neutron (mrem)
(mrem)
C106A: Office 0
ND C106B: Custodian Supply Storage 0
ND C 106H: East Loading Dock 0
ND Cl18:
Radiochemistry Laboratory 0
ND C120:
Student Counting Laboratory 0
ND FlOO:
APEX Facility 0
ND F102:
APEX Control Room 0
ND Bl25:
Gamma Analyzer Room (Storage Cave) 11 ND B125:
Gamma Analyzer Room 0
ND C124:
Classroom 0
ND C130:
Radioisotope Laboratory (Hood) 0 ND DlOO:
Reactor Support Laboratory 32 ND D102:
Pneumatic Transfer Terminal Laboratory 268 I
ND D 102H: 1st Floor Corridor at D 102 98 ND D106H: 1st Floor Corridor at D106 496 ND D200:
Reactor Administrator's Office 170 ND D202:
Senior Health Physicist's Office 276 ND D200H: Rear Personnel Dosimetry Storage Rack 12 ND D204:
Health Physicist Office 424 ND F104:
ATHRL I
0 ND D300:
3rd Floor Conference Room 165 I
ND A144:
Radioisotope Research Laboratory 0
ND (I) The total recorded dose equivalent values do not include natural background contribution and, reflect the summation of the results of four quarterly beta-gamma dosimeters or four quarterly fast neutron dosimeters for each location. A total dose equiva-lent of"ND" indicates that each of the dosimeters during the reporting period was less than the vendor's gamma dose report-ing threshold of IO 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, 2017 - 2018
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40 TableV.9 Annual Summary of Radiation and Contamination Levels Observed Within the Reactor Facility and Radiation Center During Routine ~_adiation Surveys __________ _
Whole Body
~
Contamination Accessible Location Radiation Levels LevelsO>
(See Figure V.1)
(mrem/hr)
(dpm/cm 2
)
~-A_v_erage j
Maximum Average
(
Maximum TRI GA Reactor Facility:
Reactor Top (D 104) 2.0 100 I
<500 1,250 Reactor 2nd Deck Area (D104) 7.1 35
<500
<500 Reactor Bay SW (DI04)
<1 60
<500
<500 Reactor Bay NW (D104)
<l 40
<500
<500 Reactor Bay NE (D 104)
<l 24
<500
<500 Reactor Bay SE (D104)
<l 3.8
<500 6,290 Class Experiments (D104, D302)
<l 6
<500
<500 Demineralizer Tank & Make Up Water System
<1 60
<500 1,452 (D104A)
Particulate Filter--Outside Shielding (D104A)
<l 1.7
<500
<500 Radiation Center:
NAA Counting Rooms (Al 46, BlOO)
<1 2.6
<500
<500 Health Physics Laboratory (A138)
<l
<1
<500
<500 60Co Irradiator Room and Calibration Rooms
<1 7
I
<500
<500 (A128, Bl 20, Al30)
Radiation Research Labs (A126, Al36)
<l
<1
<500 10,536 (Bl08, Bl14, Bl22, B124, Cl26, Cl30,Al44)
Radioactive Source Storage (B119, B119A,
<l 8
<500
<500 A120A, Al32A)
Student Chemistry Laboratory (Cll8)
<l
<l
<500
<500 Student Counting Laboratory (C120)
<l
<1
<500
<500 Operations Counting Room (B 136, B 125)
<l
<l
<500
<500 Pneumatic Transfer Laboratory (Dl02)
<l 6
<500
<500 RX support Room (DlOO)
<l
<l
<500 I
6,964
( 1) <500 dpm/100 cm2 = Less than the lower limit of detection for the portable survey instrument used.
Annual Report
- 1.I * * * * * * * * * * * * * * * * * * * * * * * * * * *
- Table V.10 Total Dose Equivalent at the TRIGA Reactor Facility Fence Fence Environmental Monitoring Station (See Figure V.1)
MRCFE-1 MRCFE-2 MRCFE-3 MRCFE-4 MRCFE-5 MRCFE-6 MRCFE-7 MRCFE-8 MRCFE-9 Total Recorded Dose Equivalent (Including Background)
Based on Mirion TLDs<1, 2>
(mrem) 88 +/- 3 84+/- 2 79+/- 9 87 +/- 4 83 +/- 3 82 +/- 3 86 +/- 3 82+/-2 79 +/- 3 (I) Average Corvallis area natural background using Mirion TLDs totals 78 +/- 7 mrem for the same period.
(2) +/- values represent the standard deviation of the total value at the 95% confidence level.
2017 - 2018
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42 Table V.11 Total Dose Equivalent at the Off-Site Gamma Radiation Monitoring Stations Off-Site Radiation Monitoring Station (See Figure V. l)
MRCTE-2 MRCTE-3 MRCTE-4 MRCTE-5 MRCTE-6 MRCTE-7 MRCTE-8 MRCTE-9 MRCTE-10 MRCTE-12 MRCTE-13 MRCTE-14 MRCTE-15 MRCTE-16 MRCTE-17 MRCTE-18 MRCTE-19 MRCTE-20 MRCTE-21 MRCTE-22 Total Recorded Dose Equivalent (Including Background)
Based on Mirion TLDs<1, 2l (mrem) 82 +/- 3 81 +/- 3 79+/- 2 87 +/- 3 78 +/- 3 84+/- 2 93 +/- 3 85 +/- 2 74+/- 3 93 +/- 1 80 +/- 4 79 +/- 2 75 +/- 3 87 +/- 2 78 +/- 3 81 +/- 3 83 +/- 3 78 +/- 3 53 +/- 2 74 +/- 3 (I) Average Corvallis area natural background using Mirion TL Os totals 78 +/- 7 mrem for the same period.
(2) +/- values represent the standard deviation of the total value at the 95% confidence level.
Annual Report
Sample Location (See Fig. V.1) 1-W 4-W 11-W 19-RW 3-S 5-S 20-S 21-S 2-G 6-G 7-G 8-G 9-G 10-G 12-G 13-G 14-G 15-G 16-G 17-G 18-G 22-G TableV.12 Annual Average Concentration of the Total Net Beta Radioactivity (minus 3H) for Environmental Soil, Water, and Vegetation Samples Sample Annual Average Concentration Of the Total Net Beta (Minus 3H)
LLD Type Radioactivity<ll Reporting Units I
µCi mr-1 Water 5.75xl 0-8(2) 5.75x10-8(2l
µCi mr-1 Water 8.62x I o-8<
2l 8.62xl 0-8(2)
µCi mr-1 Soil 3.2Ix10-5 +/- 7.2Ix10-6 l.46xI0*5
µCi g-1 of dry soil Soil 6.27x10-5 +/- 7.57x10-6 l.32xI0*5
µCi g-1 of dry soil Soil 9.42x10-6(2l 9.42xI0*6
µCi g-1 of dry soil Soil 2.7Ix10-5 (2l 2.7Ix10*5
µCi g-1 of dry soil Grass 7.00xl0-5 (2l 7.00xI0*5
µCi g-1 of dry ash Grass 6.43x10-5 (2l 6.43xI0*5
µCi g-1 of dry ash Grass l.63xI0-4 +/- 2.7Ix10-5 5.18xI0*5
µCi g-1 of dry ash Grass 2.14xI0-4 +/- 2.92x10-5 5.29xI0*5
µCi g-1 of dry ash Grass I
3.16xI0-4 +/- 3.5Ix10-5 5.95xI0*5
µCi g-1 of dry ash Grass 3.45x10-4 +/- 3.02x10-5 4.67xI0*5
µCi g-1 of dry ash Grass l.40xI0-4 +/- 2.05x10-5 3.78xI0*5
µCi g-1 of dry ash Grass l.64xI0-4 +/- 2.nx10-5 5.I8xl0*5
µCi g-1 of dry ash I
Grass 3.43x10-4 +/- 4.14xI0-5 7.2Ix10*5
µCi g-1 of dry ash Grass 2.34x10-4 +/- 2.89x10-5 5.07xI0*5
µCi g-1 of dry ash Grass l.74xI0-4 +/- 2.70x10-5 5.07xI0-5
µCi g-1 of dry ash Grass l.67xI0-4 +/- 2.06xI0-5 3.6Ix10-5 J
µCi g-1 of dry ash Grass l.69xI0-4 +/- 2.48x10-5 4.58xI0-5
µCi g-1 of dry ash Grass l.32xI0-4 +/- 3.2Ix10-5 6.6Ix10-5
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.
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44 Table V.13 Annual Summary of Radioactive Material Shipments Originating From theTRIGA Reactor Facility's NRC License R-106
~---------~---*----*
Number of Shipments
---~---
Total Activity E
I Limited I Yellow Yellow Shipped To Total (TBq) xempt Quantity II III Arizona State University l._l 4
_x_l0 __
5---+II 2
I 11--l --
1
---0 --+--
Tucson, AZ USA I
~
Berkeley Geochronology Center 4.12x10_7 II 5
1 0
I O
1 0
4 5
Berkeley, CA USA 0
I 3
7 17 Lawrence Livermore National Lab 6_53x10_7 I
2 I
01 ii 00 1
Livermore, CA_ U~~--------+--------1,___ __
-+j ____ _
Materion Corporation I
1*
6.72xl0*
2 I
o Elmore, OH USA Materion Natural Resources 1
0 _ __,,,----
I 9.72x10*2 0
7 17 Oregon State University 6
4 1
1 1
3 0
0 7
l.27x10*
+----
2
_-S-lx-IQ-6 I
O I
o ---0--
Piscataway, NJ USA i
1 I
2 t--
I 4
I 0
0 Syracuse University 1.06xl0-s 2
f o
1*
o Syracuse, NY USA
~
u_n_iv_e_rs-ity-of_Ar_iz-on_a __ -~~~~~-~~~:~-:-__,+1~~-~2~2~4-x_ -l_o~-1~-----t-~:_-
2_-.1 11--~----T-~----1-* __ o_---+-----
Tucson, AZ USA University of New Mexico 2_99xIQ-6 0
I 1
o Albuquerque, NM USA University of Vermont Burlington, VT USA University of Wisconsin-Madison Madison, WI USA 7.55xl0*8 3.12xl0*6 2
3 1--:-1---:----:-+-1--:--t----
Totals I
l.64x10*1 19 I 9
4 I
24 I
56 Annual Report
TableV.14 Annual Summary of Radioactive Material Shipments Originating From the Radiation Center's State of Oregon License ORE 90005 Sh.
d ~
Tota Act1v1ty
~
Number of Shipments I
1ppe o
(TBq)
Exempt Limited I Quantity I White I Yellow II I
Los Alamos National Lab I
4_62x10_6 6
4 1
0 Los Alamos, NM USA I la University of Missouri Research Reactor 2.92xl0*6 0
2 0
Columbia, MO USA Totals 7.54xl0*6 6
6 1
0 Table V.15 I
Annual Summary of Radioactive Material Shipments Exported Under NRC General License 10 CFR 110.23 Total 11 2
13
*--------*-----*1,-------------*--*--
Number of Shipments Shipped To Total Activity (TBq)
Exempt Limited I Yellow I
Total Quantity I II
~~m::.~~~~eAdministration 2.24x1Q*8 1
I O
I O
1 1
+-------;----L---
china University of Petroleum 8_93x10-s 2
I o
j' o
ii 2
Beijing, CHINA Curtin University of Technology 1.42x10.s O
o 1
j 1
I I
Bently Western Australia AUSTRALIA I
Dalhousie University 1.09x10--s--*11---2--+-jl ---
00--j, ~O ~II -
21 Halifax, Nova Scotia CANADA Geological Survey of japan 1.?9x1Q*7 1
Ibaraki, JAPAN 1
+------1-------------t-----
Geomar Helmholtz Center for Ocean Research=+/- 6.00xlO-s 2
I o
1 j
Kiel, GERMANY 0
2
f------+-----+-
ISTO 8.32xI0*7 2
1 Orleans, FANCE 0
3
+-------1-----+----1----
Korean Baskic Science Institute Cheongju-si, Chungcheongbuk-do KOREA Lanzhou Center of Oil and Gas Resources Lanzhou, CHINA 8.40xl0*8 2.2lxl0*8 5
0 0
5 0
0
1----------+------_,__ ___,__ __
--1----
Lanzhou University 3_83x10-s I
Lanzhou, Gansu CHINA LSCE-CNRS Gif-Sur-Yvette, FRANCE 2
5.77xl0*8 0
0 2
0 0
2017 - 2018
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46 Table V.15 <continued>
Annual Summary of Radioactive Material Shipments Exported Under NRC General License 10 CFR 11
__ 0
__. _2_3 _____________________ _
I Number of Shipments Total Activity Exempt Limited Yellow Total Shipped To (TBq)
Quantity II Northwest University 3.63x1Q-9 1
0 0
1 XiAn,CHINA i
I I
Polish Academy of Sciences 2.08xI0-8 I
2 0
I 0
I 2
Krakow, POLAND I
QUAD-Lab, Natural Histoyr Museum of Denmark 6.37x1Q-7 1
1 0
2 Copenhagen, DEMARK Scottish Universities Research & Reactor Centre 2.23x10-6 3
3 0
I 6
East Kilbride, SCOTLAND Tongji University l.50xI0-8 1
0 0
1 Shanghai, CHINA Universidade de Sao Paulo 9.15xl0*8 I
1 0
0 1
San Paulo, BRAZIL Universitat Gottingen 7.79x10*9 2
0 0
2 Gottingen, GERMANY Universitat Potsdam 6.88xl0*8 3
0 0
3 Postdam, GERMANY I
University of Geneva l.lOxl0-6 2
2 0
4 Geneva, SWITZERLAND I
I University of Manitoba 6.0lxlQ-6 0
3 0
3 Winnipeg, CANADA University of Melbourne 3.37x10-6 I
1 0
I 2
3 Parkville, Victoria AUSTRALIA I
I I I University of Padova 5.51x1Q-9 1
0 0
Padova, ITALY I
University of Queensland I
I 8.05xl0*7 0
1 0
+i=
Brisbane, Queensland AUSTRALIA I
University of Waikato 1.56xI0-8 1
0 0
Hamilton, NEW ZEALAND I
University of Zurich 2.72xI0-8 2
0 I
0 Zurich, SWITZERLAND I
Victoria University of Wellington 3.77xl0-8 1
0 0
1 Wellington, NEW ZELAND Vrijc Universiteit 2.87x1Q-6 I
0 2
0 2
Amsterdam, THE NETHERLANDS Zhejiang University 4.87xl0-8 I
1 i 0
I 0
I Hangzhou, CHINA I
Totals 2.98xl0*5 I
42 13 I 3
I 58 Annual Report
Figure V.1 Monitoring Stations for the OSU TRIGA Reactor
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'9Scim:Y4LUS.&mou 2017 - 2018
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-W-ork 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 111.2 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 I isting 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 48 Annual Report 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 Radia-tion Center provides a complete NAA service for researchers and others who may require it. This includes sample prepara-tion, sequential irradiation 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 response organizations and medical fa-cilities. The team can also provide assistance at the scene of any radiological incident anywhere 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 of OSU 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-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.
2017 - 2018 49
50 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 ofradiation detectors and other nuclear instrumentation. Since the Radiation Cen-ter's own programs regularly utilize a wide range of nuclear instruments, components for most common repairs are often on hand and repair time is therefore minimized.
In addition to the instrument 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 Technology (NIST) or traceable to NIST.
Table VI.3 is a summary of the instruments which were cali-brated 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 consultation ser-vices in any of the areas discussed in this Annual Report, but in particular on the subjects ofresearch 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
.,----! -~
--1 Numberof-Number of Number ofTnnes of U f C t Intuitions,Agencies and Groups I Projects Faculty Involvement seFs. o*1*t*en er
i-----t-________ 1 ___ ac111es
- Arizona State Univeristy 1
I o
. 3 Tempe, AZ USA J
-*B-er"'--k-'e-le_y_G_e_o __ c_hr_o_n_o_lo_gy_C_e_~_t_e_r---------+----l----t-.
1--*--0------i---1-0*---
Berkeley, CA USA
+------+-------t-----
Boyt Veterinary Lab I
1 o
CDM Smith Edison, NJ USA Chemical, Bilogical & Environmental Engineering Corvallis, OR USA
Tempe, AZ USA Colorado School of Mines Golden, CO USA Annual Report I
1 I
1 1
1 i
0 2
1 12 1
I-2 1
6 I
0
~
1 I
1 i
I * * * * * * * * * * * *
- e I. * * * * '*,.
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
- Dalhousie University 1
2 Halifax, Novia Scotia CANADA I
Department of Chemistry 1
1 Corvallis, OR USA Department of Forest Ecosystems and Society 1
1 Corvallis, OR USA Department of Orthopedic Surgery 1
1 Syracuse, NY USA
- ETH Zurich 1
1 Zurich, SWITZERLAND
- Geological Survey of Japan/AIST 1
0 Tsukuba, Ibaraki, JAPAN Greenberry Industrial LLC I
1 0
Vancouver, WA USA
- Helmoholtz-Zentrum fur Ozeanforschung Kiel (GEOMAR) 1 0
Kiel, GERMANY Innovative Plants LLC I
1 0
- Institute of Geology, China Earthquake Administration 1
0 Beijing, CHINA
- INSU-CNRS - Universite d'Orleans I
1 1
Orleans, FRANCE I
Johnson Crusher International Inc.
0
- Korea Basic Science Institute 1
1 Cheongwon-gun, Chungcheongbuk-do SOUTH KOREA I
- Lanzhou Center of Oil and Gas Resources, CAS 1
1 Lanzhou, CHINA
- Lanzhou University 1
0 Lanzhou City, Gansu Province CHINA
- Lanzhou University 1
0 Lanzhou, CHINA
- Lawrence Livermore National Laboratory 1
0 Livermore, CA USA
- LSCE-CNRS 1
0 Gif-Sur-Yvette Cedex FRANCE
- Materion Brush, Inc.
1 0
Elmore, OH USA I
- Materion Natural Resources 1
I 0
Delta, UT USA Number of Uses of Center Fadities 2
3 8
1 4
2 1
4 15 1
4 1
5 t
1 2
I 2
3 I
1 6
I 11 2017 - 2018 51 i
_J
~
a::
0 3:
52 Table Vl.1 (continued)
Institutions, Agencies and Groups Which Utilized the Radiation 'Center Intuitions, Agencies and Groups Nakhla Dog Meteroities Hillsboro, OR USA
- Northwest University Xi'An, CHINA
- Polish Academy of Sciences Krakow, POLAND
- Rutgers Piscataway, NJ USA
- Scottish Universities Enfironmental Research Centre East Kilbride UK
- Syracuse University Syracuse, NY USA Terra Nova Nurseries, Inc.
- The University of Waikato Hamilton, NEW ZEALAND
- Tongji University Shanghai, CHINA
- Universita' Degli Studi di Padova Padova ITALIA
- Universitat Postdam Postdam, GERMANY
1 18 1
1 1
1 1
1 1
1 2
1 1
i 1
I 1
1 1
1 3
Number of Number ofTnnes of U fC ses o enter Faculty Involvement F
T.
_acl ltrns_
1 I
1 0
1 37 106 (Z) 0 I
16 1
I 20 0
2 I
i I
0 1---!;- --
I 0
I f------
I 0
I 1
l i
I I
I 1
1 1
1 i
I 2
I 10 I
I I
i 0
10 I
2 I
2 I
T" 0
I 3
1 2
1 1
2 1
0 1
3 7
Table Vl.1 (continued)
Institutions, Agencies and Groups Which Utilized the Radiation Center Intuitions, Agencies and Groups
- University of Cambridge Cambridge, MA USA
- University of Geneva Geneva SWJTZERLAND
- University ofGoettingen Gottingen, GERMANY
- University of Manitoba Winnipeg, Manitoba CANADA
- University of Melbourne Melbourne, Victoria AUSTRALIA
- University of Postdam Postdam, GERMANY
- University of Queensland Brisbane, Queensland AUSTRALIA
- Vesta Minerals Inc.
- Victoria University of Wellington Wellington, NEW ZEALAND Number of Number of Number ofTtmes of U fC ses o enter ProJects Faculty Involvement Facilities 0
2 0
8 2
4 6
122 4
2 0
2 4
2 2
4 0
4 0
3 0
0 2
0 2
2017 - 2018 53
54 Table Vl.1 (continued)
Institutions, Agencies and Groups Which Utilized the Radiation Center Number of Number of Number of Times of U fC Intuitions, Agencies and Groups
- Vrije Universiteit Amsterdam THE NETHERLANDS
- Wayne State University Detroit, Ml USA
- Western Australian Argon Isotope Facility Perth, Western Australia AUSTRALJA
- Zhejiang University Hangzhou, CHrNA Totals Project which involves the OSTR.
Projects Faculty Involvement 93 2
0 0
82 ses o enter Facilities 2
2 3
420 (I)
(2)
Use by Oregon State University does not include any teaching activities or classes accommodated by the Radiation Center.
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 of Nuclear Engineering and Radiation Health Physics or Department of Chemistry or projects conducted by Dr. Walt Loveland, which involve daily use of the Radiation Center faci lities.
Annual Report
N 0
I-"
-..J N
0 I-"
00 Table Vl.2 Listing of Major Research and Service Projects Preformed or in Progress at the Radiation Center and Their Funding Agencies
,-I 0-rg-an-iz-a-ti-on-~-a-m_e ____ l Project Title
--1 Description I
f Funding Project I Users I
Oregon State Ar-40/Ar-39 Dating of Oceanographic Production of Ar-39 from K-39 to measure I
OSU Oceanography 444 Duncan radiometric ages on basaltic rocks from ocean University Samples basins.
I Department 815 Morrell l
Or~gon ~tate Sterilization of Wood Samples Ste,ilimtion of wood samples to 2.5 M.-ads in Co-, ~U F t p d t 60
- d
- ti fu 1
1 ores ro uc s Umvers1ty ma iator or ng~~---
920 Becker I Berkcley ______
Ar-39/Ar-40 Age Dating Production of Ar-39 from K-39 to determine ages, Berkeley I Geochronology Center in various anthroJ:?ologic and g~ol~gic materials.
Geochronology Center I
1074 Wijbrans Vrije Universiteit Ar/ Ar Dating of Rocks and Minerals Ari Ar dating of rocks and minerals.
Vrije Universiteit, Amsterdam 1191 I I Vasconcelos I
1353 Kamp 1465 I Singer I
Teaching and 1504 Tours I University of I I Queensland The University of Waikato I University of I Wisconsin
' Oregon State Umvers1ty-Educational Tours 1514 Sobel
! Universitat Potsdam I
1519 Dunk!
I University of
, Goettingen 1523 Zattin 1nivecsita' Degli Studi I
diPadova 1555 Fitzgerald Syracuse University 1617 Spikings University of Geneva Production ofAr-39 from K-39 to determine ages Earth Sciences, Ar-39/Ar-40Age Dating University of in various anthropologic and geologic materials.
Queensland Determination of history and timing of denudation Fission Track Thermochronology of of basement terranes in New Zealand and thermal University of Waikato New Zealand history of late Cretaceous-Cenozoic sedimentary basins.
Irradiation of geological materials such as volcanic I Univ~rsity of Ar-40/Ar-39 Dating ofYoung Geologic Materials rocks from sea floor, etc. for Ar-40/Ar-39 dating.
Wisconsin OSU Nuclear Engineering & Radiation I OSTR tom and reactoc lab.
NA alth Physics Department I
Age determination of apatites by fission trac~* U *
- t t p t d atite Fission Track Analysis I
1.
mvers1 a o s am
~-a_n_a. ys1s.
track dating method on apatites: use of
- Univeersity of acks from decay ofU-238 and U-235 to Tuebingen Fission Fission Track Analysis of Apatites fission tr determin e the cooling a~ of ~patites.
track dating method on apatites by fission alysis.
,NA L--------
Fission track analysis of Apatites
- 1Fission track an Fission track thermochronology on to induce U-235 fission for fission track 1*
history dating, especially for hydrocarbon Irradiati thermal explorati on. The main thrust is towards tectonics, ' Syracuse University ular the uplift and formation of mountain in partic ranges.
Ar-Ar geochronology and Fission Track~-~-
df
~ 00 a mg 1
ating of Ch_i_le_a_n_g_ra_n_i_te_s_. -------1 u_niversity of Geneva
>l~OM
- ,::J C1)
"O 0.....
WORK
~-----~~--------------------*-----------------------
Table Vl.2 (continued)
Listing of Major Research and Service Projects Preformed or in Progress at the Radiation Center and Their Funding Agencies I Orga~*-i-z--a-t-io_n_N-am-e--.-Project Title
-Fescription
. ----*-------~! F-u-~~;-**-
i ------
Project Users Blythe Occidental College!
1 Fission Track Analysis I Fissioln track Thermochronology of geological I Occidental College
:----------Jr* ---
~2 es
__J ________
1623 Oregon State Operations support of the reacto~and Operations use of the reactor in support ofreactor NA Universi~---
facilities testing________
and facilities testing;__
-**----+-------------
Radiological emergency support ot OOE related 1660 Reactor
- --*---+-0-~ratio_~_§taff to instrument calibration, radiological and I
radiological analysis laboratory at the Radiation Oregon Department of Energy J:_
I Oregon Department of 1-674 N.iles -
Energy Radiological Emergency Support RAM transport consulting, and maintenance of I
Center.
- ----:------~--*-*------------------~---*
_.,,~--*------*-----------*-*-----
This is to build up basic knowledge on 1
the efficacy of a copper based preservative in preventing decay of wood inhabiting 1692 Estell Lonza I
Lonza Screening Tests of Wood Decay l
I basidiomycetes.
,--------:---~--~-~~-~---------~-~~---------i
- '---------~---------l~-------~
1717 Baldwin Syracuse University Ar/ Ar Dating Ar/ Ar Dating.
Syracuse University 1745 I GIT. dner US National Parks Cl4 M LSC 1.
f 1 ti Cl4 US National Parks Service easurements ana ys1s o samp es or measurements.
Service 76-7-*1 Korlipara t"rerra N-~-v-a_N_u_r-se-r-ie_s_, _G_e_n--era Modifications using gamma Use of gamma and fast neutron irradiations for 1
1 Terra Nova Nurseries, i
~
irradiation genetic studies in genera.
_ Inc.
1768 I Bringman Brush-Wellman Antimony Source Production j Production of Sb-124 sources.
Brush-Wellman Quatern;zy_D_a-tm-. -g*---+-Q-u-at_e_rn_ary D_a-ti_n_g __________ l Production of Ar-39 from K-39 to determine Quaternary Dating LaboratOf¥ I radiometric ages of geological materials.
Laboratory 1777 Storey 1 This project subjects chitosan polymer in 40 and 1778 I Gislason Genis, Inc 70% DDA formulations to 9 and 18 Kgy, boundary 1*
Gamma exposure of Chitosan polymer doses for commerical sterilization for the purpose Genis, Inc.
of determine changes in the molecular weight and
+*--------+--------------+-------*---------*
_product formulat~roperites.
___ ________l __________ _
1785 Mine Oregon State Univesity INAA f M
=Frace-element analysis of ancient Maya ceramics j
-*--1--------,---------1
° aya ceramics from Pultrouser Swamp, Belize.
---L---------
1818 Sabey Brush Wellman Antimony source production (Utah)
I Brush-Wellman 1831 Fission track tliermochronometry of the Thomson University of Arizona Fission Track Patagonian Andes and the Northern Apennines, Italy.
Yale University
_1_8:,2_ Min University of Florida Ar/ Ar Dating I Ar/ Ar dating,._. ________________
u_n_iv_e_rsity of Florida 1841 S. di I
U.
fA.
Ar/ Ar dating of ordinary chondritic A /A d.
f d'
h dr'.
U.
fA.
wm e mvers1ty o nzona t
't
, r r atmg o or mary c on 1t1c meterontes.
mvers1ty o nzona me eron es j 8-5-5--A--zk--. -. -----JPolish Academy of F'.
T k S
,, 'fi fAFT d ti
.11.
h d 1* Polish Academy of
- ---~-n._c._ie_~~~~:~iences ----*---L~~!!~-~:~~v1c~---------l_v:~ cation o ----~~~*--~r 1 1te-mec te ata.
l Science_s ______ _
N 0
~
-..J N
0
~
00 Vt
-l Table Vl.2 (continued)
Listing of Major Research and Service Projects Preformed or in Progress at the Radiation Center and Their Funding Agencies
-;;~~ I Users _____ I Organization Name j Project Title
__I Descript~~~
- --------_-_-:_F~u~n~d-i_n~g---~-----:~=:-
University of University of 1864 Gans California at Santa Ar-40/Ar-39 Sample Dating Pro_ductio? ofAr-39 from ~-4o to determine California at Santa Barbara rad1ometnc ages of geologic samples.
I Barbara 1865 Carrapa University of Wyoming Fission Track Irradiations the Sevier fold and thrust belt, Nepal, and mversi O
yommg I Apatite fission track to reveal the exhilmatiof 1=------
~
istory ofrocks from the ID-WY-UY postion U.
- ty fW
---i--------+----------i----------------1 g_!lntina*-------------*--i-----*----
1878 Roden-Tice Plattsburgh State I Fission-track research Use of fission tracks to detrmine location of235U, Plattsburgh State
---.---*-----+-U_n_i_v_er_s_ity L_
232Th in natural rocks and minerals.
University _____ _
1882 Bray
,u St t U.
'ty ! INAA of Archaeological Ceramic:::Jfrom Trace-element analysis of Inca-period ceramics for vvayne a e mven S
h A d
Wayne State University
---,...~~--~---1 out menca~--~~~~
.2~r_o_v_en_a_n_c_e~et_e_rm~m_a_tI_o __ n_. ~~~~~~~~-i-~-----~~~*
-1=
The current project is designed to identify the LD50 rate of gamma irradiation so that large 1884 Contreras __ __,__O_r-eg-on State Mutation breeding of woody plants seed lots may be irradiated in order to develop University novel phenotypes that exhibit reduced fertility or 1 sterility.
-1886 J Coutand __
Dalhousie University I Fission Track Irradiation
IF'issi;n tra.ck irradiations of apatite sample_s
- ----rDaho~;ie University OSU Horticulture 1887 Farsoni
1-0-r_e_g;;; State I
mvers1 Production of xenon gas.
OSUNERHP 1905 j Fellin 1913 r-~,
U *
- ty I Xenon Gas Production
t--~-------+----*"---~------~-*~~~--~*~"~-----~-~----~------+--------*-
Use of fission tracks to determine location of Geologisches Institut, ETH Zurich Fission Track Analysis
, 235U, 232Th in natural rocks and minerals.
ETH Zurich Use of neutron activation to determine fission Oregon State Fl*ss1*on Yield Determination Usirig yields for various fissile and fertile materials using NI A University Gamma Spectroscopy
__ ~mma s~ectroscopy.
1914 I
IBarfod Scottish Universities Environmental Research Centre Ari Ar Age Dating Ari Ar age dating.
Scottish Universities Research and Reactor Centre 1916 I Shuste~a~
- Unl*vers1'ty of I Introduction ofNAA by activation of human hair I
UC Berkeley Chemistry/NAA UC Berkeley
__,_C_a_lifornia at Berkeley--<----*-----------
to detect tyace impurities.
1927 Seward
~~::;t~nniversity of Fission Track Dating Fission track dating of apatite samples.
~!~~~g~;;:versity of
- --*----?------------------+----------------------~~------
1929
~
Farsoni Oregon State I
Irradiation of different materials to make sources NA Source Activation
+-U_n_1_*v __ e_rs-'ity for detection experiments.
1939 Wang
--=-------J._L_at1~ou University Lanzhou University Fission Track _____
F_is_s_io_n_T_r __ a_ck_d_at __ in_,,&*_ -----*------+-L_an
__ zh_ou University 1955 Higley 1957 I Phillips Oregon State Uptake of redionuclides in plants Derermine concentration ratios in plants.
University OSUNERHP University of Melbourne r
Radiometric age dating of geologic University of I
Ar/Ar age dating.
Melbourne samp es
'--------------*-----------~---------
>4~0M
)>
- s
- s C
DJ
- o CD "C
0
- i.
Table Vl.2 (continued)
Listing of Major Research and Service Projects Preformed or in Progress at the Radiation Center and Their Funding Agencies WORK Project I Users J
Organization Name I Project Title I Description.
M.
;I Oregon State INAA f O C
J Trace-element analyses of prehistoric cera~ics I NSF Collabor. ative 1958 me U.
o axaca eram1cs fr O
M
- d R
hP
- _______ I mvers1_ry_
-***----------*~
om
- axaca, ex,co, to etermme provenance. J ese~J._e_ct __
I..
J Irradiation with fast neutrons to produce Ar-39 1965 Webb Umvers1ty of Vermont Ar/Ar age datmg -*--------- from K-39 for Ar/Mg~ochro~gy.
. Umvers1ty of Vermont 1975 IM D Id
~
'ty f GI I S 1 J l Use of fissin tracks to determine last heating event I School of Geographical c ona mvers1 o
asgow I amue aanne
~
t't d E rth s
- o a~s.
an a
c1ence 1979 Ip 1 Oregon State IM' d M tr' E tr f 11 f Multi-element, transition metal salt production for l I au enova University ixe a IX x ac ion es mg ~d matrix extraction testing.
1 Radiation Protection I
- I
- ------+-------
1980 Carpenter Services
_Sample countmg I Sample countmg.
State of Oregon RPS 1995 Camacho University of Manitoba Ar/ Ar dating I Production of Ar-39 from K-39 to determine University of Manitoba radiometric ages of geological material_s. ___ _
Alternative Nutrition Look for contamination in Taurine that was
-~.---
LLC Contamination detection in Taurine shiJ?ped from Japan.
2004 Sudo University_of Postd~ I Ar/Ar Geochronological Studies Ar/Ar dating ofnatural rocks and minerals for
- -----+'geological studies.
-+
Arizona State Fast neutron irradiation of mineral and rock l
Ari.zona.State 2007 Wartho U.
'ty Argon-Argon Geochronology
---1--------'~-n_1_v_er_s_1.,.____
I samples for 40 Ar/39Ar dating purposes.
Umvers1ty ___ _
I 1
1 University of Sao l
I University of Sao 20-~~ _Helena Hollanda. Paulo
- -*------ Ar/ Ar Geological Datmg *-*----- Ar/ Ar geologic datmg of matenals.
Pau~-
J Si02 surfaces were silanized (vapor deposition) I Chemical, Biological with TCVS to create double bonds on surface.
OSU Ch
. 1 2016 Schilke
& Environmental TCVS Silanization for EGAP coating I The surface is incubated in Polyethylene triblocks, E.
~mica Engineering once gamma irradiated it will bind the triblocks to ngrneerrng the surface.
___,_ ____. I W, ster Australian
-:------~--------,
2017 Jourdan ____
gon Isotope Facility ! Age dating of geological material
~
Af geochronology.
I Curtin University ence Livermore I
Production of neutron induced 39Ar from 39K for I Lawrence Livermore 2023 Cassata Ar/ Ar dating
+----
nal Laboratory Ar/Ar dating.
National Laboratory 2028 I Mine
~ Or~gon ~tate INAA of ceramics from the Ancient j Pro~enance determ~ation of ceramics fro~ the I OSU Anthro olo 1
Umvers1ty Near East l Ancient Near East via trace-element analysis.
--1...__
P gy 2029
I Korea Basic Science ! A / A hr 1
I Ar/ A. r analysis for age dating of geological
- Korea Basic Science nn
. Institute
~
r r geoc ono ogy samples.
Institute 203 3 -.
I China University of l..
I ** *
Ch_in_a_U_m-*v-er-s-ity_o_f_
Chang p tr 1 B...
F1ss10n Track
. Fission track dating ofrock samples.
p 1
B...
e o eum -
e11rng etro eum -
e1Jrng __
U Or~gon ~tytate
~
Sterilization of Wood Products
~rilization of wood to 2.0 Mrad for fungal OSU F t p d t 1 mvers1 eriments.
ores ro uc s 2000 Kaspar 2034 jMorrell
N 0 I-'
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\\0 Table Vl.2 (continued)
Listing of Major Research and Service Projects Preformed or in Progress at the Radiation Center and Their Funding Agencies Project I Users-I Org~nization Name _ I Project Title L
Lanzhou Center of Oil F
- 1. Description I Funding I
--~Center of Oil 2035Ln~*-----+-~-n_t_sG_as_R_es_o_u_rces, I Fission_T_r_a_c_k________
Fission track dating of rock s._a_m_p_1e_s_. ______.!-~.:c;~:..::d..:.:SG_a_s_R_e_s_o_u_rc_e_s,_
2036 Loveland University easuremen o ss1on pro uc various fissile elements.
I
1!-:U..:.:s:..::in..:.:g=..C;:;;;h:..::er..:.:e:.:.n...cko..:.:v=d.:.:et.:.:e::cct-o-rs_t_o_v_a_li-d-at_e_c_o_re----.i-2037
.Marcum I
2039 I Gombart Oregon State Core parameter Measurements using J operating history with large changes in reactor I
University Fherenkov Detection
_Jl
_p_2wer (i.e., s~e wave).
IL_
Prevention of Infections Associated with I
Combat-related Injuries by Local Sustained Co-Delivery of Vitamin D3 and Other Immune-Oregon State University Prevention of Infections Associated with Combat-related Injuries by Local Sustained Co-Delivery Boosting Compounds Award Mechanism. We are preparing nanofiber wound dressings that contain compounds that will be released over time to induce the immune response in wounds to help prevent infection and speed wound healing. The sterile. These experiments will be performed in j_
1 1 nanofibers must be irradiated so that they are cell culture and in animal models.
~----
-1 Use of neutron radiography to view degradation in I I
Oregon State N tr R d" h
f ATR C 1
aluminum ATR capsules from endurance testing of University eu on a IOgrap Y O apsu es these capsules under continuous hydraulic loading I Lover the course of a y"--e_a_r*-----*----~' ---------
2041 Marcum 2042 Walsh mvers1 o
regon o
nc1en eram1cs om orea A
fr SE K ge ceramics om or_e_a_. _______ _,_ _______ _
U.
- ty f O
~ INAA fA. t C fr K
Trace-element analyses of Neolithic and Bronze Uni*versi*ty of Oregon Helmholtz-Zentrum GEOMAR Helmholtz van den Bogaard fur Ozeanforschung GEO MAR Ar/ Ar I
Ar/ Ar dating research of geological samples Centre for Ocean Kiel (GEOMAR)
_,_R_e_se_ar_c_h ____ _
2045 fl Umvers1ty of Sao I
l University of Sao 2047 Parra ______ P_a_ulo
lf--F_i_ss_i_o_n_Tr_a_c_k_D_a_t1_*n_g ________ _.l,_F_is_s_io_n_tr_a_c_k_d_a_ti_n_g_o_f_g_e_o_10_g_i_c_m_a_te._n_*_a_ls_. ____ _;,_P_a_u_lo _______ _
2050 Lee Archaeological Ceramics fron Juju INAA to determine trace-element signature and National Geographic University of Oregon 1
Island, Korea provenance ofarchaeological c.:.:er:.:.a:::m:::i.::.c,s:.:.*-----~E;;c.:xe orer Grant 2053 Paulenova Oregon State University Measuring the uptake of strontium Measuring the uptake of strontium by inorganic (IONS IV) and organic ( chitosan-based) sorbent materials. Kinetics of uptake will also be evaluated. Natural strontium will be used as a carrier, and Sr-85 will serve as a tracer.
- ,-----*----*-------]!
Investigation into the effects of low level gam~~
___ ___,_ _______ _,__o_r_e_g_o __ n_S_t_at_e____
Reactor Irra.diation ofHLW Sludge_
and source neutrons on simulated Hanford waste University ank sludge.
I Loveland 2056
>t~OM
0\\
0
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- J
- J s::
Q)
Table Vl.2 (continued)
Listing of Major Research and Service Projects Preformed or in Progress at the Radiation Center and Their Funding Agencies WORK Proje~t~ers __ =1 Organiz~ion Name f Project Title I Description I_F_un_d_in_g_-_--_-__ -_ --~----
-t I Gamma irradiation of pollen has been used I
I successfully by plant geneticists to facilitate I
I discovery of genes and chromosomal regions that I control traits of interest in crops and trees like 2058 Cronn I
G d' t' f P rt Orfi d C d poplar. Geneticists in the US Forest Service have amma rrra ia 10n o o -
or e ar 'd
'fi d 1 bl
- I
- p o fi d USDA Forest Service pollen to generate chromosomal segment 1 enti e va ua.e smg e gene trait~ m ~rt-r or USDA Forest Service deletions Cedar, an ecologically and economically important conifer native to Oregon. We would like to test whether pollen irradiation can be used to create deletion lines that have modified traits, with the Geological Survey of Japan/AIST Ar I Ar Geochronology
~-1 Ishizuka -------~i;-
2061 2062 2064 Weiss Oregon State
! ~eu
!l_u_n_iv_ersity------l-c eutron Radiography Imaging of oncrete Reese Schaefer I
Oregon State I University ICDM Smith emporal Spectroscopy of Fissile 1,
M aterials A biotic Dechlorination of chlorinated so !vents in soil matrices.
anomaterials in Environmental ason u*.
M mvers1ty atrices I
go~l of identifying the genes controlling these traits.
I I
Ar/ Ar geochronology of volcanic and igneous rocks associated with subduction initiation of I Geological Survey of
! oceanic island arc.
Japan Tnv:stigation into the ~plicablity ofne~tron rad10graphy for evaluatmg concrete curmg processes.
I Use of PGNAA facility to perform temporal I
OSU R d' f C t a ia 10n en er spectr?scopy for the purpose of determmmg fissile ONDO Grant I matenal content
~1 We will be peITonning bench scale microcosm studies to measure the abiotic dechlorination in CDM Smith different soil matrices. Gamma irradiation will be used to sterilize the s~.!!1.ples.
INAA to determine distribution of synthesized I
gold-core, titanium dioxideshell nanoparticles to better understand the environmental fate and 2065 N
J ~eg: srate IN I
- -------. transl?_~rt of engineered nanomaterials.
e Tracer mvers1 2066 I Loveland UOr~gon ~tytate 1* C 20~~-Reese Oregon State -----*-1 N University I
C eutron Radiography of Long-Term oncrete Curing patite/zircon fission-track irradiation 2068 XU Tongji University tA r/ Ar dating of geologic samples I
INSU-CNRS-2069 Scaillet pniversite d'Qrleans Production of Ce tracer.
Use of neutron radiography and omography
~nState imaging in long-term studies of concrete curing ersity CCE used in civil construction.
---f.-*
Use of fission-track analysis to determine U content and fission track age constrains low-temperature cooling and exhumation in South China.
i Ar/ Ar analysis for age dating of geologic samples INSU-CNRS-
___ J (solid rock chip~ and minerals) --
I Universite d'Orleans L_
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00 Table Vl.2 (continued)
Listing of Major Research and Service Projects Preformed or in Progress at the Radiation Center and Their Funding Agencies
-;roject j Users ----~I O_r_g_a_m-.z-at-io_n_N_a_m_e_. ~~;le
________ J Description
-*-1*------1-*--
-*1 The purpose of this experiment is to determine 1
what color a nearly colorless Tourmaline will I
tum with dosages of 5, 10 and 20 Mr of Gamma I part of this experiment to see the color change as I Funding I *--
2070 Lowell I
I irradiation. Two Pakistan Beryl crystals are also I
well as 2 pieces of Four Peaks Amethyst that may have been faded by sunlight. For the Tourmaline, I
C 1 d G d
Gamma irradiation induced change of 1
"bTf b
11 d
- k Colorado Gema and o ora o em an color in Tourmaline from a Pegmatite in I co or poss1 1 1 1es are rown, ye ow, an pm I
Mineral Co.
i to red. The commercial value of colorless gem Mineral Co.
the Oban Massif, Nigeria I
Tourmaline is very low, but other colors of gem I Tourmaline, especially pink and red results, would I
stimulate mining of this material in Nigeria. 20 Mr is usually a dosage that will saturate the visible I
I I color, and lower dosages may be preferable if the I
l Gamma rays cause a new color other than pink or J
! red which is the desirable result.
2071 Gall~t ----~~r----__ -_-_1 1
Geoazur Ar/Ar dating
~ Geoazur Ar/Ar dating. __
-_-_:::~~--- ---,'--------
I We will be receiving shipments of dried blood spot!
I cards with bovine blood containing a chemical I I
compound from South Africa in the near future.
2072 Buckner University of Washington Trypanosoma Methionly-tRNA synthetase inhibitor development to treat neglected tropical diseases.
The USDA-APHIS are requiring us to gamma j
irradiate the samples before they will be released to our lab at the University of Washington (Se-attle, WA). We need to conduct a test to determine if the gamma irradiation, 6 Mrad (60 kGy), will degrade the chemical compound in the samples.
L I The sample will be a dried blood spot card spotted L I
I with bovine blood (US origin) with our chemical 1
__ _j_ __________ +---------*-----------' compound sent from our lab Seattle, WA).
I I
This project focuses on the controlled release I
1 I
'! delivery ofleuprolide from poly(lacticco-glycolic 1
2073 I
acid) microspheres. Leuprolide is remotely loaded I The Biointerfaces into preformed microspheres via peptide absorp-
'j The Biointerfaces Schwendeman I Institute PLGA microspheres I tion due to interactions between cationic peptides Institute I
I and PLGA. The goal of this study is to use remote loading to achieve high peptide encapsulation and
~ntinuous peptiderelease with low initial burst.
>i~OM
Table Vl.2 (continued)
Listing of Major Research and Service Projects Preformed or in Progress at the Radiation Center and Their Funding Agencies WORK
~ ------*-----------
i --------
I Project I Users Organization Name I. +~
Oregon State 2074 M_in_c _______ _
University 2075 Berns University of Texas I
f Project Title Description
- Funding
~-I~
I NAA of archaeological ceramics from the Valley I Market Exchange in Ancient Oaxaca, Mexico of Oaxaca, Mexico, to trace the origins of market NSF
-+----*-*-----------
exchange.
_J ________ _
I Biogeochemical Processes that Control Natural Attenuation ofTCE in Low Permeability Zones I Trichloroethylene can diffuse into low permeabil-1 ity materials such as clays. When there is a change 1
1 in chemical gradient, TCE can "back diffuse" out of the clay into higher permeability materials University of Texas I (such as sand) and be transported through the sub-1 surface. This project focuses on the biogeochemi-
- 1.
I cal interactions influencing the back diffusion of
--+-------t------*-----':-------------------11.... tr_i_ch_loroethylene at a sand-clay,_in
__ te_r_fa_c_e_. -----+----------
1 Helferty
,. Transition metal irradiation It's an experiment in how Frankel vacancy pairs in i dissimiliar joining of transition elements behave. I I
-+-------------------+Th-i_s_p_ro--d-e-"-ct ~ims to determine the contribu-1:-----------
1 I
tions of biotic and abiotic mechanisms involved I with nitrate driven uranium oxidation in natural Nitrate Mediated Uranium Mobilization sediments. Experiments will be conducted using I U.
f Uniersity of Nebraska-in the High Plains Aquifer, Central up-flow columns packed with gamma sterilized NnbiverskityL~
In Lincoln Nebraska d
- 1* d "ti d"
(fr I
e ras a-mco an non-sten 1ze aqm er se 1ments om centra !
2076 2077 Weber I
Nebraska) to determine the rate and contributions I I,
o~ abiotic and biotic uranium oxidation mecha-j 1 msms.
1-2078 1
1 Qu
--r;::-k-.-A---. ---+-Irr-adiation of PTFE powder mixed with l Different levels of irradiation of PTFE powder 0-.-k*-. _Am
____ ln __ _
__J~ m menca nc.
modifier I with different modifiers.
l ai m enca
- c.
2079 _I Albert l
Or~g~n ~tate Soil Geochemistry of-Playa Lakes
--JIN_AA to determine geochemical composition of 1'
Um~ers~------!.........-
-*- soils around p_~ya lak~_s of E. Oregon.
j INAA to determine traceelement geochemistry of 2080 Na-tion__
Oregon State Trace-element Geochemistry ofBehzean 1 th fr
. B 1.
d M
University
, Speleothems I
sptue e 1
o *terns om caves m e 1ze use as ayan !
l n a s1 es.
I 2081 Mine
---, Oregon S~~dard Test Method fo~ Antimony --
,. Round-robin to demonstrate utility of _IN_A_A_fi_o_r-+
1----------
, University ___ ~tent in Plastics
_______ characterizing antimony content in plastics.
1 I
j I
I Oregon State I
Oregon State S
ti D t t E 1 t*
Production of rad1oactlve sources for the purpose U.
- ty ONDO i ources or e ec or va ua 10n mvers1
1--Umvers1ty i_
___ J oftestmg radiation detection systems.
__J,_G_r_a_n_t ------
2083 l Nadel Charlotte Pipe and I ABS A f 1, f I Testing for trace antimony in ABS via INAA Charlotte Pipe &
F_o_un_dry_, Co.
l n imony es mg according to ASTM E3063.
Foundry.,__C_o_. ___ _
-=--i Nadel I Charlotte Pipe and I
ABS A f 1, f Testing for trace antimony in ABS compounds via Charlotte Pipe &
-~~.:__J __________ L~c1ryso. ______ 1 ____ n Imo~~~~~------*-*-- INAA according to ASTM E3063. --
Foundry Co. _____ _
2082 Reese
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00 Table Vl.2 (continued)
Listing of Major Research and Service Projects Preformed or in Progress at the Radiation Center and Their Funding Agencies P
- t 1u lo "f
. f roJec sers rgamza 10n ame roJec I e escnp 10n I
Lanzh~~ Univer:ity 2085 He Apatite fission track Use of fission track analysis to determine U conte!}t in the sedimentation ofXining Basin.
. The goal of this project is to induce mutations in seeds and dormant cuttings of commercially important landscape plants produced by the horti-cultural industry. Based on results by the principle researcher and published literature, it is anticipated 2086 Pounders Innovative Plants LLC Mutation Induction by Radiation in I radiation induced changes to the genome and Asexually Propagated Landscape Plants l cell cytoplasm of treated material may include I
improved environmental tolerance and/or morpho-logical changes of horticultural importance such as I
I flower color, leaf color, dwarfness, branching etc.
I Identified mutations of commercial value will be I
. asexually pn>p~gyrtedby p}lrtic}p}ltfilg nurseries.
Full spectrum irradiation of CaF2 crystals to 2087 Hecht UNM Calcuim Fluoride dosimetry studies determine changes in optical properties due to neutron ex2osure.
I l
I Baseing on the Jowtemperature China University of Tb t Pl t Lh Q"
gt t
thermochronological dating and modeling, the 2088 Dai 1 e an a eau asa-mn ang errane,
Geosciences th hr 1
- 1 project want to explore the plateau uphft and ermoc ono og1ca survey xh d
"fi e
umation amounts, an prospectmg s1gm cance of mineral deposits.
I 2089 Jvang Oregon State Irradiation of Material for check sources Irradiation of different materials to make check University sources for detector characterization.
I I This funding is intended to build a collaborative effort between faculty and students in biological I
sciences, chemistry, and engineering, investigate the diversity and capability of marine Biodegradation of crude oil in arctic microbial communities to degrade oil constituents 2090 I Duddleston University of Alaska waters and development of dynamic and respond to chemical remediation tools. We bioremediation responses will use this information to develop innovative ap-proaches ( e.g. prescriptive microbial applications I _l and methods, models ofresponse and degradation, rapid monitoring strategies) for appropriate oil spill respoi:ise in arctic waters.
un mg Lanzhou University Innovative Plants LLC China University of Geosciences NSE University of Alaska
>t~OM
WORK Table Vl.2 (continued)
Listing of Major Research and Service Projects Preformed or in Progress at the Radiation Center and Their Funding Agencies Project I Users I Organiz~t~~n Name I Project Title r;;escrip;ion
- --1-F-un-~:-g ______ _
--~*--*---+----
,-T-um-~r cells which succes._sfu_ll_y_p_r-es_e_n_t -an-t-ig_e_n--+-*
I 1
1 will result in the activation of tumor-specific I
CDS T cell responses. In order to measure T cell I The Role ofUbiquitin and Ubiquitin-Department of responses in vitro without the confounding effects Department of 2091 Dolan 2094 Sathuvalli Like Molecules in Direct Antigen Biomedical Sciences of tumor cell growth, we will irradiate tumor Biomedical Sciences Presentation cells with gamma irradiation which will arrest the growth of the cell line and allowing only T cells to I
-*-----+------*-------*---,* E!.2.!iferate if antigen presentation was successful.
1 1
f Fission track dating of Qaidam Basin, China to Northwest University Fission Track Dating ofQaidam Basin I
determine its age.
OSU Crop and Soil Science Cytoplasmic male sterility (male sterility caused I by ~itochondria and/or chloroplasts) poses a 1 maJor barrier to crossing many potato varieties I
in a potato breeding program. One possible tool I
to eliminate cytoplasmic male sterility is somatic I OSU C d S.1 Use of Somatic Cybridization to Remove rop an 01 cybridization, where protoplasts of male-sterile I S.
Barrier Cytosplasmic Male Sterility 1
. h.
fu d. h c1ence c ones wit nnportant genes are se wit proto-plasmic elements that are known to promote male 1
J plasts of cytoplasm donors (protoplasts with cyto-I.
fertility, and that have had their nuclear genome
---i---*---*-----1----------:-----------------*-
destroyed using ~amma radiation).
I Oregon State
-,Gamma irradiation of PGNAA rabbit tubes to Reese Gamma Irradiation of Rabbit Tubes DNDO ARI Grant University harden them in order to increase tube lifetime:
1
:-----~~--------------------
I i
I Oregon State i'
Cross l~ing polymers by use of gamma 11 NSE I Reese -------:1 U~!~e,_s.... ity"-------
Cross linking of polymers adiation.
oject is designed to irradiate liquid donor bovine I rum contained in vinyl bags to a minimum level 2097 Boyt I Boyt Veterinary Lab Donor Bovine Serum Irradiation 25 kGy to inactivate any adventitious agents I Boyt Veterinary Lab I
! that may be present in 0.2 um sterile filtered I
_ _J___-+-1 --------:-------------------+1"-pr_o __
duct.
__J I
Institute of Geology,
~
2098 Pang Chm. a Earthquake tudying the thermal history oftlle northeast Tibet China Earthquake Fission-Track dating Administration lateau by the fission-track dating method.
Administration
*--*--*--------1------------------1 Use of gamma spectroscopy to verify authentisity 2099 Wesel Nakhla Dog Meteroites Gamma Spectroscopy of Hiroshima of_watch claimed to have been exposed to the Watch I Hiroshima bombing. __ _
2095 2096
-~-------~---------*-L---------
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00 Table Vl.2 (continued)
Listing of Major Research and Service Projects Preformed or in Progress at the Radiation Center and Their Funding Agencies Projec; I Users ------, Org-an-iz-a-ti*o--n-N_a_m_e_. -
Project Title Description I Funding 2100 Palmer
~Yang 2102 Shulzhenko 2103
!Higgins 2104 Oest I
I School of Nuclear Science and Engineering Soft Safe Robotic Applications for Nuclear guards This project is a collaboration-with OSU Robotics. I We are investigating the performance of PDMS materials, which are used to fabricate soft robotics, Id h N t' 1
.: 11 d'
- w, Id l'k a o a 10na
~o owmg ra iation exposure.
e wou i e L b t
to characterize any changes in hardness, tensile a ora ory strength, and recovery after exposure to high radiation environments.
Fission-track analysis for dating geological material.
microbiota modi~tes the interpl~y J To identify microbial taxa and thefr genes th.a_t _ ____,. _________ _
~iang University ___ I Fiss ion-track thermochronometry Zhejiang University I
1 College of Veterinary Medicine Colorado School of Mines Department of Orthopedic Surgery I
I I
tween immunity and glucose affect glucose metabolism and immune response
~~~i~:~erinary abolism ---*-------- using mouse model of diet-induced diabetes. -----1,........--------
Gut be met SE RDPER-2720 The project is SERDP ER-2720, Key Fate and Transport Processes Impacting the Mass Discharge, Attenuation, and Treatment of Poly-and Perfluoroalkyl Substances and Comingled Chlorinated Solvents or Aromatic Hydrocarbons.
The overall goal of this research is to attain improved insight into the fundamental fate and transport processes that control per-and polyfluoroalkyl substance (PFAS) fate and transport as well as comingled chlorinated solvents and/or fuel hydrocarbons in groundwater at aqueous film forming foam (AFFF)-impacted sites. This research will particularly focus on the release and transformation of polyfluorinated PFASs to the more problematic perfluoroalkyl acids (PFAAs) in source zones as well as the impact of commonly employed remediation
- technologies for co-contaminants on PFAS fate.
The goal of this project is to explore the use of shape-memory polymer constructs to deliver and retain bioactive agents within complex bone Colorado School of Mines Shape-memory polymers for accelerated fractures and defect sites. Bioa~sorbable sha~e-SUNY Upstate Medical memory polymer constructs will be doped with U.
repair of complex bone defects b' 1 d h
d mverstty anttmicro ta an osteogemc agents, t en triggere by a local temperature change to conform to the bone defect site, effectively containing the bioactive agents within the area to be repaired.
gon State Evaluation of Moisture Content in Wood r Use of neut~on radiography to determin~ the ---+---
versity, ______ ~P_r_o_d_uc_t_s_
__Lmoisture content o_f_v_a_ri_o_u_s _w_o_o_d_c_o_m_.p,_o_s1_*te_s_. _ __,_ _________ _
2105 ! Way
__ __t__
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- I
- I C:
QJ
- 0 rt)
"'O 0
- i WORK Table Vl.2 (continued)
Listing of Major Research and Service Projects Preforme d or in Progress at the Radiation Center and Their Funding Ag encies
- Funding I
oncentrations of PGE and -r
~~;s----1 Orga~~ation ~~me
! Proj-;ct Ti~---------~~~~~;~n 2106 IR d
- , Vi M"
l In I PGE D rINA~ to ~ete~ine C 2107 2108 2109 2110 2111 2112 2113 enau esta mera s C.
etermmat1on I
--1 School ofNuclear Soft Robotic Applications ofr Nuclear Palmer Science and Engineering Safegaurds I
Walker I Johnson Crushers Int f
1 1 Charactenzabon of Zircon sand erna ma nc
~
School of Biological I Alternative Techniques for Ensuring Dallas and Population health 1 Microbiological Safety of Donor Breast Sciences Milk Stewart-Smith r--
Sample counting Turrin I Rutg~~-------- Ari Ar Geochronology ___
Carpenter University of Michigan INAA of Formative Zapotec Ceramics
- REE m mmeral ores aboration with OSU Robotics.
--;I-This project is a coll We are investigating 1
1 materials, which are following radiation e to characterize any c strength, and recove radiation environme Determination of Ra the performance of PDMS used to fabricate soft robotics, xposure. We would like hanges in hardness, tensile ry after exposure to high nts.
-228 in Zircon sand used for ine the effects of five ion of bacteria and viruses I welding flux.
j Objectiv'-e-1-* s_t_o_d-et_e_rm I treatments on reduct
, and on the activity o f milk digestive enzymes, I
particularly bile salt-treatments being test stimulated lipase. The ed are HTST and LTLT l
pasteurization, high pressure processing, gamma cell irradiation, and UV -C exposure.
erent isotopes in variable I
Determination of diffi hronology.
1 samp_l_es_. ____ _
i Lunar/solar system c I INAA to determine p I Valley of Oaxaca.
rovenance of pottery from the ng LLC I
P l
Radiation aging testi I Mills Greenberry Industrial Bechtel-S ecial Relief Devices I
Idaho National Laboratory I
j Johnson Crushers I International School of Bio And Pop Sciences NASA Greenberry Industrial LLC I
i---
jWe do a great deal o fwork with sterile plant tissue
- ing to use non-sterile plants ermine if would it be possible ies where we see at what obial contaminants killed but able.
e dating of Geologic
____l::scE-CNRS
"~--~------~*---
Department of Forest I
cultures, ~ostly need 2114 Strauss Ecosystems and Sterilization of Plant tissue cultures I tfordexpet~1me/dnts. Det S.
o o a 1me ose ser
- ~
L
_______ I
--1 ::~~;:;~ g! ~~i:r~'
1 I
Ar/ Ar analysis for ag Scao LSCE-CNRS I Age datmg of geologic matenals t. 1
_ __________ l ___________ J. ______________________ ~a ena s.
N 0
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00 Project Users 2116 Nyman 2117 2118 2119 2120 2121 Fronk Reese Blackmore Li Jia Table Vl.2 (continued)
Listing of Major Research and Service Projects Preformed or in Progress at the Radiation Center and Their Funding Agencies I Organization Name Department of Chemistry Sch of Mech/Ind/Mfg Engr Oregon State University University of Cambridge Institute of Tibetan Plateau Research, Chinese Academy of Sciences Beijing Research lnstitue of Uranium Geology Project Title Determine if the oligomerization of uranyl peroxide can be driven by radiation High-Flux Microchannel Receiver Development NRF Beam Purity INAA of Korean Ceramics Alpha-particle induced annealing effects of fission tracks in apatite Fission track analysis to determine U content in South China I Description We would like to determine if the oligomerization of uranyl peroxide can be driven by radiation, in solution. We will prepare solutions of lithium uranyl triperoxide monomers and apply different radiation doses (time of radiation) until change is observed by visual inspection and spectroscopic characterization. We estimate 3 samples, irradiated for one day, and TBD for the other two samples.
Irradiation of all wi ll start simultaneously.
This project seeks to reduce the size, weight and thermal losses from high temperature solar receivers by the application on microchannel heat transfer technology to solar receiver design. Our objective is to design and test on-sun a supercritical CO2 microchannel receiver commercial module operating at a fluid exit temperature of 720 °C capable absorbing an average flux of 140 W/cm2 with a receiver efficiency of 90 percent or higher.
Use of beam quality indicators to categorize the NRF beam.
fNAA to determine trace-element composition of Korean archaeo_!2gical ceramics.
Using the in situ TEM ion irradiation faci lity at Argonne National Laboratory, we already observed He ions (simulating alpha-particles) induced annealing effects on 80 MeV ion tracks (sim ulating fission tracks) in apatite. For the next step, we are planning to use chemical etching to 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, as compared to naturally occurring fission tracks, have no thermal history (or thermal annealing effects).
Fis ion track dating of areas of South China.
Funding Department of Chemistry Chinese Academy of Sciences Beijing Research lnstitue of Uranium Geology
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Project Users 2122 Jia 2123 Dick 2 125 Marksthaler Table Vl.2 (continued)
Listing of Major Research and Service Projects Preformed or in Progress at the Radiation Center and Their Funding Agencies I Organization Name Beijing Research lnstitue of Uranium Geology Sch of Environ &
Natural Res Project Title I Description Ar-Ar analysis for age dating of geologic Ar-Ar analysis for age dating of geologic materials materials.
(solid rock grains and minerals).
Effect of soil type on bioavailabi lity of aminomethylphosphonic acid to microorganisms This research will test the effect of three different soi l textures and mineralogy on the bioavailability of aminomethylphosphonic acid to soil microorganisms. Different concentrations of AMPA will be applied to soil, and chemical extractions and microbial properties will be measured at different time intervals. Chemical extractions from sterilized and unsterilized soil samples wi ll be compared at each time interval to determine the chemical vs. biological degradation effects.
WORK Funding Sch of Environ &
Natural Res Jensen Hughes NRF Images of Balance Valve Multiple images of carbon steel balance valve with EPDM rubber 0 -rings.
Jensen Hughes
e Figure Vl.1 e
Summary of the Types of Radiological Instrumentation Calibrated to Support the OSU TRIGA Reactor and Radiation Center
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Air Alpha Detectors Detectors Chambers Micro Meters Dosimeters Samplers TableVl.4 Summary of Radiological Instrumentation Calibrated to Support Other Agencies Agency Number of Calibrations Clair Company I
Columbia Memorial Hospital 3
Columbia Steel Casting 3
Doug Evans, DVM 2
EPA I
Fire MarshalVHazmat 118 Health Division 109 Knife River 3
NETL, Albany 4
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371 TableVl.3 Summary of Radiological Instrumentation Calibrated to Support OSU Departments OSUDepartment I Number of Calibrations Animal Science 2
Biochem/Biophysics I
Botany I
Microbioloby 2
Nutrition/Food Science 2
Pharmacy I
Radiation Safety Office 28 Total 37 2017 - 2018 69
-W-ords Publications A. Wakhle, K. Hammerton, Z. Kahley, D.J. Morrissey, K. Stiefel, J. Yurkon, J. Walshe, K. J. Cook, M.
Dasgupta, D.J. Hinde, D.J. Jeung, E.Prasad, D.C.
Rafferty, C. Simenel, E.C. Simpson,K. Vo-Phuoc, J.
King, W. Loveland, and R. Yanez. (2018). Capture cross sections for the synthesis of new heavy nuclei using radioactive beams. Phys. Rev. C, 97, 021602(R).
B.M.S. Amro, C.J. Lister, E.A. Mccutchan, W. Loveland, P.
Chowdhury, S. Zhu, A.D. Ayangeakaa, J.S. Barrett, M.P. Carpenter, C.J. Chiara, J.P. Greene, J.L. Harker, R.V.F. Janssens, T. Lauritsen, A.A. Sonzogni, W.B.Walters and R. Yanez. (2017). Gamma-ray spectroscopy of209TI. Phys. Rev. C, 95, 014330.
Baldwin, S., Fitzgerald, P., & Malusa, M. (2018). Crustal exhumation ofplutonic and metamorphic rocks:
Constraints from fission track thermochronology.
Chapter 13. In M. Malusa, & P. Fitzgerald (Eds.),
Fission track thermochronology and its application to geology (pp. 235-257). Springer.
Bari, E., Sistani, A., Taghiyari, H., Morrell, J., & Cappellazzi, J. (2017). Influences of test method on biodegradation of bamboo/plastic composites by fungi. Madera Ciencia y Tecnologia, 19(4): 455-462.
Betsi, T., Ponce, M., Chiaradia, M., Ulianov, A., & Camacho, A. (2017). Insights into the gensis of epithermal Au-Ag mineralization at Rio Blanco in the Occidental Cordillera of southwestern Ecuador: constraints from U-Pb and Ar/Ar geochronology. Journal of South American Earth Sciences, 80, 353-374.
Catto, S., Cavazza, W., Zattin, M., & Okay, A. (2018). No significant Alpine-age tectonic overprint of the Cimmerian Strangja Massif (SE Bulgaria and NW Turkey). International Geology Review, 60, 513-529.
Cavazza, W., Catto, S., Zattin, M., Okay, A., & Reiners, P.
(2018). The Miocene Arabia-Eurasia collision zone of southeastern Turkey. Geosphere, 14/5.
Chang, J., Qiu, N., Zhao, X., & et al. (2018). Mesozoic and Cenozoic tectono-thermal reconstruction of the western Bohai Bay Basin (East China) with implications for hydrocarbon generation and migration. Journal of Asian Earth Sciences, 160, 380-395.
70 Annual Report Cordova, J., Mulcahy, S., Schermer, E., & Webb, L. (n.d.).
Subduction initiation and early evolution of the Easton Metamorphic Suite, Northwest Cascades, Washington. Lithosphere, Accepted, in revision.
Czyz, S., & Farsoni, A. (2017). A Radioxenon Detection System Using CdZnTe, an Array of SiPMs, and a Plastic Scintillator. Journal ofRadioanalytical and Nuclear Chemistry, 313(1), 131-140.
Czyz, S., Alhawsawi, A., Farsoni, A., Ranjbar, L., Gatley, H., & Mannino, M. (2018). A Radioxenon Detection System Using PIPS and CZT. Journal of Radioanalytical and Nuclear Chemistry, Under review.
Czyz, S., Farsoni, A., & Ranjbar, L. (2018). A Prototype Detection System for Atmospheric Monitoring of Xenon Radioisotopes. Nuclear Instruments and Methods in Physics Research A, 884, 64-69.
Engelhardt, J., Sudo, M., Stockhecke, M., & Oberhansli, R. (2017). Feldspar 40Ar/39Ar dating of ICDP PALEOVAN cores. Geochimica et CosmochimicaActa, 217, 144-170.
Evolution and provenance of the Xuefeng intracontinental tectonic system: constraints from detrital zircon fission track thermochronology. (n.d.). Journal of Asian Earth Sciences, Submitted.
Faisal, S., Larson, K., Camacho, A., & Coutand, I. (2018).
Cooling, exhumation, and deformation in the Hindu Kush, NW Pakistan: new constrains from preliminary 40Ar/39Ar and fission track analyses.
Journal of Asian Earth Sciences, 15 8, 415-427.
Fitzgerald, P., & Malusa, M. (2018). Concept of the exhumed partial annealing (retention) zone and age-elevation profiles in thermochronology. In M. Maluda, & P. Fitzgerald (Eds.), Fission track thermochronology and its application to geology (pp. 165-189). Springer.
Fitzgerald, P., Malusa, M., & Munoz, J. (2018). Detrital thermochronology using conglomerates and cobbles. Chapter 17. In M. Malusa, & P.
Fitzgerald (Eds.), Fission track thermochronology and its application to geology (pp. 295-314).
Springer.
.1 * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *
- * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *
- I. * * * * *
- Gatley, H., Farsoni, A., Feng, P., Ranjbar, L., & Czyz, S.
(2018). Gamma Spectrum Enhancement in a Metal Loaded Plastic Scintillator Using Digital Pulse Shape Discrimination. IEEE Trans. Nucl. Sci., Under review.
He, P., Song, C., Wang, Y., & et al. (2017). Cenozoic exhumation in the Qilian Shan, northeastern Tibetan plateau: Evidence from detrital fission track thermochronology in the Jiuquan Basin. Journal of Geophysical Research: Solid Earth, 122, 6910-6927.
He, P., Wang, X., Song, C., Wang, Q., Deng, L., & Zhong, S. (2017). Cenozoic evolution of the Western Qinling Mt. Range based on thermochronologic and sedimentary records from the Wudu Basin, NW Tibetan Plateau. Journal of Asian Earth Sciences, 138:484-494.
Homrighausen, S., Hoernle, K., Geldmacher, J., Wartho, J-A., Hauff, F., Portnyagin, M., Werner, R., van den Bogaard, P., and Garbe-Schonberg, D. (2018).
Unexpected HIMU-type late-stage volcanism on the Walvis Ridge. Earth and Planetary Science Letters, 492, 251-263.
Huston, R., Heisel, C., Vermillion, V., Christensen, J., & Mine, L. (2017). Aluminum Content of Neonatal Parenteral Nutrition Solutions: Options for Reducing Aluminum Exposure. Nutrition in Clinical Practice, 32(2):266-270.
R. J. Casperson, D. M. Asner, J. Baker, R. G. Baker, J.
S.Barrett, N. S. Bowden, C. Brune, J. Bundgaard, E.
Burgett, D. A. Cebra, T. Classen, M. Cunningham, J. Deaven, D. L. Duke, I. Ferguson, J. Gearhart, V. Geppert-Kleinrath, U. Greife, S. Grimes, E.Guardincerri, U. Hager, C. Hagmann, M. Heffner, D. Hensle, N. Hertel, D. Higgins, T. Hill, D.
Isenhower, J. King, J. L. Klay, N. Kornilov, R. Kudo, A. B. Laptev, W. Loveland, M. Lynch, S. Lynn, J.
A. Magee, B. Manning, T. N. Massey, C. McGrath, R. Meharchand, M. P. Mendenhall, L. Montoya, N.
Pickle, H. Qu, J. Ruz, S. Sangiorgio, K. T. Schmitt, B. Seilhan, S. Sharma, L. Snyder, S. Stave, A. Tate, G. Tatishvili, R.T. Thornton, F. Tovesson, D. Towell, R. S. Towell, N. Walsh, S. Watson, B. Wendt, L.
Wood, L. Yao, and W. Younes. (2018). Measurement of the normalized 238U(n,f)/235U(n,f) cross section ratio from threshold to 30 MeV with the fission Time Projection Chamber. Physical Review C, 97, 034618.
L.Snyder, B. Manning, N.S. Bowden, J. Bundgaard, R, Casperson, D.A. Cebra, T. Classen, J. Gearhart, U. Greife, C. Hagemann, M. Hefner, D. Hensle, D. Higgins, D. Isenhower, J. King, J.L. Klay, W. Loveland, J.A. Magee, M.P. Mendenhall, S.
Sangiorgio, B. Seilhan, F. Tovesson, R.S. Towell, S.
Watson, L. Yao, and W. Younes. (2018). Performance of a MICROMEGAS-based TPC in a high-flux high-energy neutron beam. Nuclear Instruments and Methods A, 881, 1.
V. Geppert-Kleinrath, F. Tovesson, N. Bowden, J. Bundgaard, R. Casperson, T. Claussen, D. L. Duke, U. Greife, C. Hagemann, U. Hager, M. Heffner,D. Hensle, D. Isenhower, J.L. Klay, H. Leeb, W. Loveland, B. Manning, J. Ruz, S. Sangiorgio, B. Seilhan, L.
Snyder, R.S. Towell, and S. Watson. (n.d.). Fission Fragment Angular Anistropy in Neutron-Induced Fission of235U Measured with a Time Projection Chamber. Phys. Rev. C, Submitted.
Jiang J, Zhang Y, Indra AK, Ganguli-Indra G, Le MN, Wang H, Hollins RR, Reilly DA, Carlson MA, Gallo RL, GombartAF, Xie J. (2018, June). lalpha,25-dihydroxyvitamin D(3)-eluting nanofibrous dressings induce endogenous antimicrobial peptide expression.
Nanomedicine, 13(12):1417-1432. doi:10:2217/nnm-2017-0011 Karo, N., Oberhansli, R., Aqrawi, A., Elias, E., Aswad, K., &
Sudo, M. (2018). New 40Ar/39Ar age constraints on cooling and umoofing history of the metamorphic host rocks (and igneous intrusion associates) from the Bulfat Complex (Bulfat area), NE-Iraq. Arabian Journal of Geosciences, 11 :234.
Kaulfuss, U; Lee, DE; Wartho, J-A; Bowie, E; Lindqvist, JK; Coman, JG; Bannister, JM; Mildenhall, DC; Kennedy, EM; Gorman, AR. (2018). Geology and palaeontology of the Hindon Maar Complex: A Miocene terrestrial fossil Lagerstatte in southern New Zealand. Palaeogeography, Palaeoclimatology, Paleoecology, 500, 52-68.
King, J., Loveland, W., Barrett, J., Oscar, B., Fotiadis, N.,
Toves son, F., & Lee, H. (2017). The total kinetic energy release in the fast neutron-induced fission of 232Th. Eur. Phys. J. A, 53, 238.
Lang, K., Ehlers, T., Kamp, P., & Ring, U. (2018). Sediment storage in the Southern Alps of New Zealand:
New observations from tracer thermochronology.
Earth and Planetary Science Letters, 493: 140-149.
doi: 10.1016/j.epsl.2018.04.016 2017 - 2018
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Lang, K., Ehlers, T., Kamp, P., Ring, U., Glotzbach, C.,
& Stubner, K. (n.d.). Westward migration of the SouthemAlps drainage divide, New Zealand.
Geology, Submitted.
Larson, K., Camacho, A., Cottle, J., Coutand, I., Buckingham, H., Ambrose, T., & Rai, S. (2017). Cooling, exhumation and kinematics of the Kanchenjunga Himal, far east Nepal. Tectonics, 36, 1037-1052.
Li, C., Xiao, R., Morrell, J., Zhou, X., & Du, G. (2017).
Improving the performance of hemp hurd/
polypropylene composites using pectinase pre-treatments. Industrial Crops and Products, 97:465-468.
Lossada, A., Giambiagi, L., Hoke, G., & Fitzgerald, P. (n.d.).
Modem river sand thermochronology unravels a complex exhumation evolution for the Andes in the transition between flat slab and normal subduction segment (33* - 33.5* S). Submitted.
Lossada, A., L. Giambiagi, G. Hoke, P.G. Fitzgerald, C.
Creixell, I. Murillo, D. Mardonez, R. Velasquez and J. Suriano. (2017). The late Eocene constructional phase in the Andes at 30*S: evidence from thermochronology. Tectonics, 36.
Loveland, W., & King, J. (2017). Total kinetic energy release in the fast neutron induced fission of232Th and 235U. In J. Hamilton, A. Ramayya, & P. Talou (Eds.),
Fission and Properties of Neutron-Rich Nuclei (p.
361). Singapore: World.
Loveland, W., & Yao, L. (2017). Survival mediated heavy element capture cross sections. EPJ Web of Conferences, 163, 00033.
Loveland, W., Morrissey, D., & Seaborg, G. (2017). Modem Nuclear Chemistry (2nd ed.). New York: Wiley.
Loveland, W., Vinodkumar, A., Yanez, R., Yao, L., King, J.,
Lassen, J., & Rojas, A. (n.d.). Sub-barrier fusion of 1 lLi with 208Pb. European Physics Journal A, Accepted.
Malusa, M., & Fitzgerald, P. (2018). Application of thermochronology to geologic problems: Approaches and conceptual models. Chapter 10. In M. Malusa, &
P. Fitzgerald (Eds.), Fission track thermochronology and its application to geology (pp. 191-209).
Springer.
Malusa, M., & Fitzgerald, P. (2018). Fission-track thermochronology and its application to geology.
Springer. doi:10.1007/978-3-319-89421-8 72 Annual Report Malusa, M., & Fitzgerald, P. (2018). From cooling to exhumation: setting the reference frame for the interpretation of thermochronologic data. In M.
Malusa, & P. Fitzgerald (Eds.), Fission track thermochronology and its application to geology (pp.
147-164). Springer. doi: 10.1007/978-3-3 l 9-89421-8 8 Mine, L. (2017). Assessing Compositional Variation in Ubaid and LC Ceramics from Surezha, Kurdistan. Final technical report submitted to Dr. Gil Stein, Director, Oriental Institute, Chicago, for chemical analyses completed at OSU-RC (9 pp+ 12 figures).
Mine, L. (2017). Early Ceramic Technology, Jeju Island, Korea: Clay Survey and Archaeometric Analyses of Neolithic Ceramics. Final technical report circulated to collaborators for analyses supported by NGS Explorer Grant to Gyoung-Ah Kim (23 pp+ figures).
Mine, L., & Sterba, J. (n.d.). Instrumental Neutron Activation Analysis (INAA) in the Study of Archaeological Ceramics. In A. Hunt (Ed.), Oxford Handbook of Archaeological Ceramic Analysis. Oxford University Press.
Mutin, B., Mine, L., Lamberg-Karlovsky, C., & Tosi, M.
(2017). Regional and Long-Distance Exchange of an Emblematic "Prestige" Ceramic in the Indo-Iranian Borderlands: Results of Neutron Activation Analysis.
Ms. Paleorient, 43(1): 141-162.
Neville, D.R., & Higley, K. A. (2017). Lack of Cesium Bioaccumulation in Gelatinous Marine Life in the Pacific Northwest Pelagic Food-Web. In Resilience:
A New Paradigm of Nuclear Safety (pp. 311-315).
Springer, Cham.
Palmer, CJ; Oshiro, T; Hollinger, G; Menguc, Y; Palmer, T; Courier, T; Yirmibesoglu, OD; Morrell, S; Rynes, A. (2018). An Assessment of Potential Soft Robotic Applications in Radiation Environments via Mechanical Evaluation of Major Component Polydimethylsiloxane (PDMS). Nuclear Physics B, Submitted, under review.
Palmer, CJ; Oshiro, T; Hollinger, G; Menguc, Y; Palmer, T; Courier, T; Yirmibesoglu, OD; Morrell, S; Rynes, A.
(July 2017). Soft Robotics in Radiation Environments for Safeguard Applications. Proceedings of the 58th Annual Meeting - Institute for Nuclear Materials Management.
Pengju He, Chunhui Song, Yadong Wang, Qingquan Meng, Lihao Chen, Lijie Yao, Yitong Liu, Ruohan Huang, Wei Feng, Shuo Chen. (2018). Cenozoic deformation history of the Qilian Shan (northeastern Tibetan plateau) constrained by detrital apatite fission-track thermochronology in the northeastern Qaidam Basin.
Tectonophysics, Under review.
Perez Rodriguez, V., Martinez Tufi6n, A., Mine, L.,
Stiver Walsh, L., & Navarro Rosales, M. (2017).
Chronological trends in the use of Valley of Oaxaca ceramics and ceramic styles at Cerro Jazmin, Mixteca Alta, Oaxaca. Journal of Archeological Science:
Reports, 12:580-590.
Pokorny, R., Knnicek, L., & Sudo, M. (2017). An endemic ichnoassemblage from a late Miocene paleolake in SE Iceland. Palaeogeography, Palaeoclimatology, Palaeoecology, 485, 761-773.
SCHITO A., ANDREUCCI B., ALDEGA L., CORRADO S., DI PAOLO L., ZATTIN M., SZANIAWSKI R.,
JANKOWSKI L. & MAZZOLI S. (2018). Burial and exhumation of the western border of the Ukrainian Shield (Podolia): a multi-disciplinary approach. Basin Research, 20, 532-549.
Shabaga, B., Fayek, M., Quirt, D., Jefferson, C., & Camacho, A. (2017). Mineralogy, geochronology, and genesis of the Andrew Lake uranium deposit, Thelon Basin, Nunavut, Canada. Canadian Journal of Earth Sciences, 54, 850-868.
Shorten, C., & Fitzgerald, P. (n.d.). Post-orogenic thermal history and exhumation of the Northern Appalachian Basin: Low-temperature thermochronologic constraints. Basin Research, In revision.
Siron, C., Rhys, D., Thompson, J., Baker, T., Veligrakis, T., Camacho, A., & Dalampiras, L. (2018).
Structural controls on porphyry Au-Cu and Au-rich polymetallic carbonate-hosted replacement deposits of the Kassandra Mining District, northern Greece.
Economic Geology, 113, 309-345.
Spinola, D., Pi-Puig, T., Solleiro-Rebolledo, E., Egli, M.,
Sudo, M., Sedov, S., & Kuhn, P. (2017). Origin of clay minerals in Early Eocene volcanic paleosols on King George Island, Maritime Antarctica. Scientific Reports, 7:6368.
T. Welsh, W. Loveland, R. Yanez, J.S. Barrett, E. A.
Mccutchan, A. A. Sonzogni, T. Johnson, S. Zhu, J.P. Greene, A.D. Ayangekaa, M.P. Carpenter, T.
Lauritsen, J.L. Harker, W. B. Walters, B.A. Amro, and P. Copp. (2017). Modeling Multi-Nucleon Transfer in Symmetric Collisions of Massive Nuclei.
Phys. Lett. B, 771, 119.
TADAYON M., ROSSETTI F., ZATTIN M., CALZOLARI G., NOZAEM R., SALVINI F., FACCENNA C.
& KHODABAKHSHI P. (2018). The long-term evolution of the Doruneh Fault region (Central Iran):
a key to understand the spatio-temporal tectonic evolution in the hinterland of the Zagros convergence zone. Geological Journal, 1-26.
Tadayon, M., Rossetti, F., Zattin, M., Nozaem, R., Calzolari, G., Madanipour, S., & Salvini, F. (2017). The post-Eocene evolution of the Doruneh Fault region (Central Iran): the intraplate response to the re-organization of the Arabia-Eurasia collision zone.
Tectonics, 36, 3038-3064.
Walsh, R., Lee, G.-A., & Lee, Y.-C. (Spring 2019). Ceramics and society in Magan and Baekje. Asian Perspectives, In press.
Wang, X., Deng, L., Zattin, M., Ji, M., & Li, J. (2017).
Palaeogene growth of the northeastern Tibetan Plateau: Detrital fission track and sedimentary analysis of the Langzhou basin, NW China. Journal of Asian Earth Sciences, 147: 322-331.
Wang, X., Deng, L., Zattin, M., Ji, M., & Li, J. (2017).
Paleogene growth of the northeastern Tibetan Plateau: detrital fission track and sedimentary analysis of the Lanzhou basin, NW China. Journal of Asian Earth Sciences, 147, 322-331.
Wang, Y., Zheng, J., & Zheng, Y. (2018). Mesozoic-Cenozoic exhumation history of the Qimen Tagh Range, northeastern margins of the Tibetan Plateau: Evidence from apatite fission track analysis. Gondwana Research, 58C: 16-26.
Webb, L., & Klepeis, K. (n.d.). 40Ar/39Ar constraints on the Tectonic evolution of the Late Paleozoic and Early Mesozoic accretionary complex of coastal Central Chile. In B. Horton, & A. Folguera (Eds.), Andean Tectonics. Submitted. Elsevier.
Willner, A., van Staal, C., Zagorevski, A., Glodny, J., Romer, R., & Sudo, M. (2018). Tectonometamorphic evolution along the lapetus suture zone in Newfoundland: Evidence for polyphase Salinic, Acadian and Neoacadian very low-to medium-grade 2017 - 2018
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metamorphism and deformation. Tectonophysics, 742-743, 137-167.
Yanez, R., King, J., Barrett, J., Loveland, W., Fotiades, N., &
Lee, H. (2018). The total kinetic energy release in the fast neutron-induced fission of235U. Nucl. Phys. A, 970, 65.
Yao, L., & Loveland, W. (2018). Survival mediated capture and fusion cross sections for heavy element synthesis.
Phys. Rev. C, 97, 014608.
Presentations Aiken, C., & Webb, L. (2018). Geochronologic Constraints on the Timing of Metamorphism and Exhumation of the Tillotson Peak Complex in Northern Vermont.
Geological Society of America Abstracts with Programs, 50(2). doi: I 0.113 O/abs/20 l 8NE-3 l 0829 Alden, J., & Mine, L. (4 January 2017). Ceramic Production and Distribution in the Kur River Basin of Iran during the Kaftari Era, ca. 2200-1600 BC. Scientific Analytical Approaches: Ceramic, Clay, and Mud-Brick. Glasgow: 2017 Annual Meeting of British Association of Near Eastern Archaeology.
Alhawsawi, S., Farsoni, A., Becker, E., Czyz, S., & Ranjbar, L. (21-29 October 2017). Compact High-resolution Silicon CZT Beta-gamma Detection System for Nuclear Weapon Test Monitoring. Atlanta, Georgia:
IEEE Nuclear Science Symposium.
Baldwin, S., Malusa, M., & Fitzgerald, P. (20-29 August 2017). Geochemical kinetics and the geodynamics of (U)HP terranes. Invited Keynote (p. 8). Are, Sweden:
12th International Eclogite Conference, High-and Ultrahigh-pressure rocks keys to lithosphere dynamics through geologic time.
Brombin, V; Marsoli, A; Roghi, G; Fred, J; Coltorti, M; Bonadiman, C; Webb, L; Sara, C; Guiliano, B; De Vecchi, G; Roberto, S;. (2018). The temporal evolution of the Cenozoic Southalpine magmatic activity in North-East Italy: evidence from 40Ar/39Ar geochronology. European Geosciences Union (p. I). European Geosciences Union.
Caswell, B., Gilotti, J., Webb, L., Jones, D., & McClelland, W. (2018). 40Ar/39Ar Geochronology ofBiotite from Ductile Shear Zones of the Ellesmere-Devon Crystalline Terrant, Nunavut, Canadian Arctic.
Geological Society of America Abstracts with 74 ProE!:ams, 50(2). doi:I0.1130-abs-2018NE-310455 Annual Report Chang, J., & Qiu, N. (3-8 June 2018). Late Cretaceous to Cenozoic exhumation of the Fuping Complex, Trans-North China Orogen: new insights from apatite and zircon (U-Th)/He and apatite fission track analysis.
AOGS.
Chen, Z. (16-21 September). Evolution and provenance of the Xuefend intracontinental tectonic system constrained by zircon FT analysis. Germany: 16th International Conference on thermochronology.
Condon, C. (June 2018). Pine Tree Dosimetry: Development of Geometric and Compositionally Specific Sectional Models for Organ Dose Assessment. Preliminary exam. Oregon State University.
Condon, C., & Higley, K. (9-13 July 2017). Dose Assessment Comparison for Animals and Plants Based on Phylogeny. Raleigh, North Carolina: 62ndAnnual Meeting, Health Physics Society.
Cordova, J., Schermer, E., Mulcahy, S., & Webb, L. (2017).
Initiation and early evolution of a subduction zone:
T-t-D history of the Easton metamorphic suite, northwest Washington State. Geological Society of America Abstracts with Programs, 49(6). doi: 10.1130/
abs/2017AM/303853 Czyz, S., Farsoni, A., & Alhawsawi, S. (29-30 November 2017). Preliminary Evaluation of Two Beta-Gamma Radioxenon Detection Systems. Ann Arbor, Michigan: 2017 CVT Workshop, University of Michigan.
Czyz, S., Farsoni, A., & Gadey, H. (5-7 June 2018).
Investigation of High-Resolution Srl-2(Eu)
Scintillators + SiPMs and PIPSBox for Radioxenon Detection. Ann Arbor, Michigan: University Performance Review.
Czyz, S., Farsoni, A., & Ranjbar, L. (21-28 October 2017).
Evaluation of a Compact Radioxenon Detection System to Support the Nuclear Test-Ban Treaty.
Atlanta, Georgia: IEEE Nuclear Science Symposium.
Czyz, S., Farsoni, A., Gatley, H., & Mannino, M. (12-14 June 2018). A Beta-gamma Coincidence Radioxenon Detection System Using a Silicon Beta Cell and SrI2(Eu) + SiPMs. Ann Arbor, Michigan: IEEE Symposium on Radiation Measurements and Applications.
Fitzgerald, P., Benowitz, J., Ridgway, K., Warfel, T., & Allen, W. (2017). The role of terrane rheology vs fault geometry for mountain formation and exhumation
along the Denali fault of south-central Alaska.
Geological Society of America Abstracts with Programs, 49(6). doi: 10.1130/abs/2017 AM-305797 Fitzgerald, P; Baldwin, S*, Bermudez*, Webb L* Little T*
Miller, S; Malusa, MG; Seward, D. (20-29 August 2017). Rift-triggered exhumation of eclogite-bearing gneiss domes in eastern Papua New Guinea: Geologic and thermochronologic constraints. Are, Sweden:
12th International Eclogite Conference.
Gatley, H., Farsoni, A., & Czyz, S. (12-14 June 2018). Design of a Prototype Radioxenon Detection System Using Stilbene and CdZnTe. Ann Arbor, Michigan:
IEEE Symposium on Radiation Measurements and Applications.
Gatley, H., Farsoni, A., & Czyz, S. (5-7 June 2018). CdZnTe and Stilbene Based Radioxenon Detection System.
Ann Arbor, Michigan: University Performance Review.
Gatley, H., Farsoni,A., Czyz, S., & Ranjbar, L. (21-28 October 2017). Pulse Shape Discrimination between Photoelectric and Compton Events in a Metal Loaded Plastic Scintillator. Atlanta, Georgia: IEEE Nuclear Science Symposium.
Gladfelder, G., & Higley, K. (9-13 July 2017). Exploring How the Stress-Inducing Mechanisms from Radioisotopes of Cesium are Related. Raleigh, North Carolina: 62nd Annual Meeting, Health Physics Society.
Higgins, C. (12 February 2018). Data obtained from OSU RC-irradiated samples presented at invited seminars.
Queensland Alliance for Environmental Health Services.
Higgins, C. (18 January 2018). The Consortium for Research and Education on Emerging Contaminants.
Higgins, C. (24 June 2018). Combined analytical approaches to assess poly-and perfluoroalkyl substances in the environment. Gordon Research Seminar on Environmental Sciences: Water.
Higgins, C. (26 June 2018). Semi-quantitative suspect screening of PFAS in AFFF-Impacted soils. Po~ter.
Gordon Research Conference on Environmental Sciences: Water.
Kamp, P. (19-21 March 2018). Review of East Coast Basin (North Island) structure and development: New insights from integration ofthermochronology data with regional geology. New Zealand Petroleum Conference.
Klepeis, K., Webb, L., Blatchford, H., Schwartz, J., Turnbull, R., & Jongens, R. (2017). Unraveling a history of repeated fault reactivations and differential uplift above a young subduction zone in SW New Zealand.
Geological Society of America Abstracts with Programs, 49(6). doi:10.1130/abs/2017AM-306155 Klepeis, K., Webb, L., Merson, M., & Kim, J. (2018).
Unraveling Fault Reactivations and Their Tectonic Significance Using Integrated Structural Data and 40Ar/39Ar Geochronology, Examples from N Vermont and SW New Zealand. Geological Society of America Abstracts with Programs, 50(2). doi: 10.1130/
abs/2018NE-3 l 1301 Lipeh, S., & Morrell, J. (2017). Rapid detection of Alaska cedar ( Calliptropsis nootkatensis) ( Cupressaceae) extractives using Fourier transform infrared (FT-IR) spectroscopy). (pp. Document No. IRG/WP/17-20612). Stockholm: International Research Group on Wood Protection.
Liu, R. U., & Higley, K. (9-13 July 2017). Development of an Integrated Spatial and Temporal Stochastic Model for Computational Radiation Biology. Raleigh, North Carolina: 62nd Annual Meeting, Health Physics Society.
Liu, R., Higley, K., & Swat, M. (n.d.). Development ofa Coupled Simulation Toolkit for Computational Radiation Biology Based on GEANT4 and CompuCell3D. 60th Annual Meeting AAPM.
Loveland, W. (April 2017). Total kinetic energy release and fission product mass distributions for the fast neutron induced fission of232Th, 233U, 235U, and 239Pu.
San Francisco: 253rdACS National Meeting.
Loveland, W. (April 2017). Total kinetic energy release in fission. Naperville, Illinois: SSAA Symposium.
Loveland, W. (February 2017). Survival mediated heavy element capture cross sections. Hobart, Tasmania:
FUSI0N17.
Loveland, W. (March 2017). Target Preparation. Livermore, California: TPC Meeting.
Mannino, M., Becker, E., & Farsoni, A. (21-28 October 2018).
Real-time Temporal Gamma Spectroscopy in Field-Programmable Gate Array. Atlanta, Georgia: IEEE Nuclear Science Symposium.
2017 - 2018
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Maydagan, L., Franchini, M., Zattin, M., & Dimieri, L. (7-11 August 2017). Dataciones (U-Th)He en apatito en la region de Altar (31 °30'S), Cordillera Principal de San Juan, Argentina. Relacion entre exhumacion tectonica y emplazamiento de los cuerpos subvolcanicos.
Tucuman, Argentina: Congreso Geologico Argentino.
Mercer, C., Hodges, K., Joliff, B., van Soest, M., Wartho, J.-
A., Young, K., & Weirich, J. (2018). Taking a close look at dating old impact melt rocks: High spatial resolution 40Ar/39Ar geochronology of some Apollo 17 samples. Houston: Lunar and Planetary Science Conference.
Mine, L., Feinman, G., Nicholas, L., Faulseit, R., & Markens, R. (April 2017). Producci6n e intercambio de ceramica en el estado zapoteco del periodo Clasico Tardio: Resultados nuevos del analisis de elementos traza en el valle de Oaxaca. Oaxaca: Tercera Conferencia Intercontinental de SAA.
Morgun, A. (May 2018). Seminar. Nutrition Graduate Program, Oregon State University.
Neville, D. (26 July 2018). Discount Albacore Radioecology:
Hunting Cs-137 on a Budget. National Analytical Management Program Young Investigators Webinar.
Neville, D. (3 May 2018). Faster, Sharper, and Open: A New Pipleline for Biota Phantoms. Cascade Chapter Health Physics Society.
Neville, D., & Higley, K. (n.d.). United States Marine Radioecology for the North Pacific Ocean in the post-Fukushima Era. Country report. PICES.
Ng, G., & Higley, K. (9-13 July 2017). Modeling the Fate of Radio-cesium in a Modern-day Urban Water-recycling Scenario. Raleigh, North Carolina: 62nd Annual Meeting, Health Physics Society.
Olivetti, V; Rossetti, F; Balestrieri, ML; Pace, D; Cornamusini, G; Talarico, F; Balsamo, F; Zattin, M. (8-13 April). Variability in the topography, exhumation, and structural style through a 600km transect along the Transantarctic Mountains Front, Antarctica. Wien: EGU General Assembly.
Oshiro, T., Palmer, C., Hollinger, G., Menguc, Y., Courier, T., & Yirmibesoglu, D. (May 2018). Soft Robotics in Radiation Environments for Nuclear Safeguard Applications. American Nuclear Society Student Conference.
Palmer, CJ; Oshiro, T; Hollinger, G; Menguc, Y; Palmer, T; Courier, T; Yirmibesoglu, OD; Morrell, S; Rynes, A;.
76 Annual Report (July 2017). Soft Robotics in Radiation Environments for Safeguard Applications. The 58th Annual Meeting Institute for Nuclear Materials Management.
Samrock, L., Hansteen, T., & Wartho, J.-A. (2017). 40Ar-39Ar age clustering in the active phonolitic Cadamosto Seamount (Cape Verdes): Indications for periodic magmatic activity. New Orleans: American Geophysical Union Conference.
Samrock, L., Hansteen, T., & Wartho, J.-A. (2018). 40Ar-39Ar age clustering in the active phonolitic Cadamosto Seamount (Cape Verdes): Indications for periodic magmatic activity. Kiel, Germany: Physics of Volcanoes Conference.
Shinjoe, H., Sudo, M., Orihashi, Y., & Sumii, T. (2017).
Miocene alkaline magmatism in the region close to trench of SW Japan. New Orleans: 2017 AGU Fall Meeting.
Shorten, C., & Fitzgerald, P. (19-21 March 2017). Post-orogenic thermal history and exhumation of the Northern Appalachian Basin constrained through low-temperature thermochronology. Pittsburgh:
Geological Society of America Joint Northeastern &
North-Central Section Meeting.
Shorten, C., & Fitzgerald, P. (20-23 May 2018). Post-orogenic exhumation of the Northern Appalachian Basin and Timing of Hydrocarbon Generation: Low-Temperature Thermochronological Constraints from New York and Pennsylvania. Salt Lake City:
American Association of Petroleum Geologists 2018 Annual Convention & Exhibition.
Sudo, M., Strecker, M., Friese, A., Hahne, K., Reidl, S.,
Lopeyok, T., & Mibei, G. (2017). Temporal change in geochemistry of volcanic rocks along the volcano-tectonic axis of the northern Kenya Rift: Insights from the Ar/ Ar geochronology and whole-rock chemistry at Paka. Portland, Oregon: IAVCEI 2017 Scientific Assembly.
Tam, E., Webb, L., & Aiken, C. (2017). Role of the Prospect Rock Fault in the Exhumation of High Pressure Rocks in North-Central Vermont. EOS, Transactions, American Geophysical Union.
Tam, E., Webb, L., &Aiken, C. (2018). Geochronologic Constraints on the Timing of Deformation in the Footwall of the Prospect Rock Fault in North-Central Vermont. Geological Society of America Abstracts with Programs, 50(2). doi:10.1130/
abs/2018NE-310928
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- Walsh, R. (11-15 April 2018). Discussant for Lighning Round:
Geochemistry and Identity. Washington, DC: 83rd Meeting for the Society for American Archaeology.
Wang, X. (n.d.). Cenozoic multi-stage exhumation of NE Tibetan Plateau revealed by fission-track thermochronology from longzhong basin. 6th National Sedimentological Congress.
Warfel, T., Fitzgerald, P., Benowitz, J., Ridgway, K., &
Allen, W. (11-15 December2017).Applying low-temperature thermochronology to constrain exhumation patterns along the eastern Denali fault comer, Alaska. (pp. T23C-0618). New Orleans:
American Geophysical Union Annual Meeting.
Warfel, T., Fitzgerald, P., Benowitz, J., Ridgway, K., &
Allen, W. (18-20 March 2018). Low-temperature thermochronology constraints on exhumation along and across the east-central Denali Fault, Alaska.
Burlington, Vermont: Geological Society of America Northeastern Section Meeting.
Way, D. (n.d.). Moisture transport in wood composites. Wood Science and Engineering Spring 2018 Seminar Series.
Webb, L. (2017). Strange results, or: How I learned to stop worrying and love complicated 40Ar/39Ar apparent age spectra. Geological Society of America Abstracts with Programs, 49(6). doi:10.1130/
abs/2017 AM-306106 Webb, L. (April 2018). Punctuated melt-enhanced deformation and tectonic reactivation above a long-lived subduction zone, Coastal Andes, Central Chile.
Seminar. University of Miami Ohio, Department of Geology and Environmental Earth Science seminar series.
Webb, L., Klepeis, K., & Kim, J. (2018). New Insights on Acadian Deformation and Reactivation in Northern Vermont from Integrated Structural and Geochronological Studies. Geological Society of America Abstracts with Programs, 50(2).
doi: 10.1130/abs/20 l 8NE-3 l 1032 White, K. ( 6 September 2018). Student presentation. Summer Undergraduate Research Program, College of Veterinary Medicine, Oregon State University.
Yu, B., Raman, R., & Schilke, K. (19 January 2017). High-density non-fouling bioactive coatings: Development and characterization. Poster. Provo, Utah: 2017 BME Western Regional Conference.
Yu, B., Raman, R., & Schilke, K. (19 January 2017). Towards a bioselective surface for treatment of sepsis. Provo, Utah: 2017 BME Western Regional Conference.
Students Aiken, Cheyne. MS Geology (October 2018), University of Vermont. "Geochronologic Constraints on the Timing of Metamorphism and Exhumation of the Tillotson Peak Complex in Northern Vermont."
(Advisor L. Webb).
Alhawsawi, Abdulsalam. PhD Radiation Health Physics (September 2017), Oregon State University.
"Development of a CZT-Silicon Detection System in Support of the Comprehensive Nuclear Test-Ban Treaty." (Advisor A. Farsoni).
Barchers, Faith. BA Anthropology (2018), Oregon State University. (Supervisor L. Mine).
Barrientos, Anne. BA Anthropology student, Oregon State University. (Supervisor L. Mine).
Caswell, Brandon. MS (2018), University ofldaho.
"40Ar/39Ar Geochronology ofBiotite from Ductile Shear Zones of the Ellesmere-Devon Crystalline Terrane, Nunavut, Canadian Arctic." (Advisor J.
Gilotti).
Chen, Zheng. PhD. "Fission-track analyses for the tectonothermal history of eastern Sichuan basin in Mesozoic." (Advisor C. Xu).
Condon, Caitlin. PhD student, Oregon State University.
"Pine Tree Dosimetry: Development of Geometric and Compositionally Specific Sectional Models for Organ Dose Assessment." (Advisor K. Higley).
Deng, Linzhen. Lanzhou University. "Cenozoic tectonic activity of the West Qinling orogenic belt revealed by apatite fission-track thermochronology of Linxia basin." (Advisor X. Wang).
Demoncourt, John. MS student, Oregon State University.
"Assessing Preclassic Ceramic Exchange Networks at Pulltrouser Swamp, Belize" (provisional title).
(Advisor L. Mine).
Faisal, S. MSc. (Advisor K. Larson).
Gadey, Harish. MS Nuclear Engineering (June 2017), Oregon State University. "Gamma Spectrum Enhancement 2017 - 2018
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78 in a Metal Loaded Plastic Scintillator using PSD."
(Advisor A. Farsoni).
Genge, Marie Catherine. PhD, University of Padova.
"Structural evolution of the Central Patagonia: a source-to-sink approach." (Advisor M. Zattin).
Ghani, Humaad. PhD student, Universitaet Potsdam.
"Structural Geology and Thermochronology of Kohat-Potwar fold thrust belt, Pakistan." (Advisor E. Sobel).
Gladfelder, Garth. MS student, Oregon State University.
"Measuring stress response to low level radiation in Hordeum vulgare using chlorophyll fluorescence" (working title). (Advisor K. Higley).
Heidarzadeh, Ghasem. PhD student, Universitaet Potsdam.
"Fault interactions on different time and length scales, the North-Tehran-Thrust and the Mosha-Fasham-Fault, Alborz mountains, Northern Iran."
(Advisor M. Strecker).
Homrighausen, Stephan. PhD (June 2018). "Insights into the temporal and geochemical evolution of the Walvis Ridge - a connection between HIMU and EM 1 end members in the South Atlantic." (Supervisor K.
Hoernle).
Hulscher, Julian. PhD student, Frei Universitaet Berlin.
"Towards the inversion of tectonic signals from deep-marine archives: Competing tectonic signal propagation from across the Alps into the marine sink." (Advisors A. Bernhardt, E. Sobel).
Hunter, Kye. BS student, Oregon State University.
(Supervisor W. Loveland).
King, Jamie. BA Anthropology student, Oregon State University. (Supervisor L. Mine).
King, Jonathan. PhD (2018), Oregon State University. "Fast neutron induced fission of232Th." (Advisor W.
Loveland).
Lamont, Ellen. PhD student, Oregon State University.
"Exhumation of the sub-Himalayan foreland fold-and-thrust belt." (Advisor A. Meigs).
Li, Xia. PhD, University of Padova. "From bedrock to sediments: insights on Ross Sea ice-flow dynamics inferred from detrital data." (Advisor M. Zattin).
Lossada, A. PhD, Instituto Argentino de Nivologia, Glaciologia, y Ciencias Ambientales. (Advisor L.
Giambiagi).
Mannino, Mitchell. MS Nuclear Engineering (October 2017),
Oregon State University. "Real Time Temporal Annual Report Spectroscopy for Characterizing Special Nuclear Material." (Advisor A. Farsoni).
Mccaleb, Kyle. MS (2017), Oregon State University.
"Reaction of I32Xe with 198Pt." (Advisor W.
Loveland).
Morrow, Max. BS student, Oregon State University.
(Supervisor W. Loveland).
Nation, Humberto. MS student, Oregon State University.
"Speleothems and Maya Cave Ritual in Central Belize" (provisional title). (Advisor L. Mine).
Neville, Delvan. PhD student, Oregon State University.
(Advisor K. Higley).
Oshiro, Tyler. MS, Oregon State University. "Soft Robotics in Radiation Environments: A Prospective Study of an Emerging Automated Technology for Existing Nuclear Applications." (Advisor C. Palmer).
Perotti, Matteo. PhD, University of Siena. "The Antarctic Ice Sheets dynamics during and after the Last Glacial Maximum revealed by provenance of clasts and sand fraction in Ross embayment glacial tills." (Co-tutor M. Zattin).
Pink, Jeremias. PhD student, Oregon State University.
(Advisor L. Mine).
Portnoy, Samantha. BS Geology student, University of Vermont. "Relationship between rapid exhumation and fault patterns in Fiordland, New Zealand."
(Advisor K. Klepeis ).
Raman, Ram ya. PhD (summer 2018). "Towards a Selectively Bioactive Surface for the Removal of Circulating Endotoxin in Blood."
Rodgers, Amaris. BS Geology (2018), University of Dayton Ohio. "40Ar/39Ar constraints on the exhumation of the East Humboldt mountain range in Elko, Nevada."
(Advisor A. McGrew).
Savignano, Elisa. PhD, University of Padova. "Apatite (U-Th)/He and Fission Track thermochronometry in the Northern Patagonian Andes: new insights into the exhumation history of the thrust belt foreland sector."
(Advisor M. Zattin).
Shorten, Chilisa. PhD, Syracuse University. "Post-orogenic Thermal History and Exhumation of the Northern Appalachian Basin: Low-Temperature Thermochronologic Constraints." (Advisor P.
Fitzgerald).
Siron, C.R. PhD. (Advisor J. Thompson).
e:1
Tam, Evan. MS Geology (October 2018), University of Vermont. Yao, Liangyu "Larry". PhD (2018), Oregon State University.
"Geochronological Constraints on the Timing of Deformation: An Examination of the Prospect Rock Fault Footwall in North-Central Vermont." (Advisor L.
Webb).
Victor, Ashley. BS. (Advisor David Dallas).
Warfel, Thomas. MS, Syracuse University. "Low Temperature "Survival mediated heavy element capture cross sections." (Advisor W. Loveland).
Yao, Xiao. MS. "Tectonic-thermal evolution of the Kuqa Depression in the northern Tarim Basin and its implication for hydrocarbon migration." (Advisors N.
Qiu, J. Chang).
Theromochronologic Constraints across the East-Central Yu, Bonan. PhD student. " In Situ Polymerization of Highly-Denali Fault: Evaluating Vertical Tectonics along a Transpressive Orogen." (Advisor P. Fitzgerald).
Way, Danny. PhD (August 20 I 8), Oregon State University.
Branched, Bioactive and Non-Fouling Polymer Coatings for Medical Devices, Biosensors, and Other Applications" (provisional title).
"Multi-scale approach to evaluating moisture durability Zapata, Sebastian. PhD student, Universitaet Potsdam. "The of wood-based composites." (Advisor A. Sinha).
influence of inherited extensional structures on the growth of basement-cored ranges and their fore land basins." (Advisor E. Sobel).
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Oregon State University Radiation Center, 100 Radiation Center, Corvallis, OR 96331 www.radiationcenter.oregonstate.edu I * *.
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