ML16287A417
| ML16287A417 | |
| Person / Time | |
|---|---|
| Site: | Oregon State University |
| Issue date: | 10/06/2016 |
| From: | Reese S Oregon State University |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML16287A417 (80) | |
Text
Radiation Center usu Oregon State University, 100 Radiation Center, Corvallis, Oregon 97331-5903 T 541-737-2341 I F 541-737-0480 I http://ne.oregonstate.edu/facilities/radiation_center Oregon State UNIVERSITY October 6, 2016 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Reference:
Oregon State University TRIGA Reactor (OSTR)
Docket No. 50-243, License No. R-106 In accordance with section 6.7.l of the OSTR Technical Specifications, we are hereby submitting the Oregon State University Radiation Center and OSTR Annual Report for the period July 1, 2015 through June 30, 2016.
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: /0 ft // c.....
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Sincerely, Director Cc:
Michael Balazik, USNRC Craig Bassett, USNRC Ken Niles, ODOE Dr. Cynthia Sagers, OSU Dr. Roy Haggerty, OSU Dan Harlan, OSU
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Oregon State UNIVERSITY
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Submitted by:
Steve R. Reese, Director
- -Radiation Center Oregon State University -
Corvallis, Oregon 97331_-5903 Telephone: (541) 737-2341 Fax: (541) 737-0480 To 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.
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~.on_ t:en_ t:s Part 1-0ve:rview Executive Sum.mary..................................................................................................*.................................. 4 lntroduction.... :::.;.........................................................................................,.. :.............................................. 4 Overview of the Radiation Center.................................................... ;...........,......................................... 4 Part II-People Radiation Center Staff........ :::*::."::"................................................................. '..... :........................................... 6 Reactor Operations Committe~ *.............................................................................................................. 6 Professional & Research Faculty*:~::.*,.......................................................................................................... 7
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Part Ill-Facilities
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Research Reactor.............................................. ~i*~~:*********************::.~:**********************************************************;8 --*-- --,
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Rad101sotope lrrad1at1on Sources........................... :;,~.*...................... :.,.......................................*........... 9 Laboratories & Classrooms................................ :..........'~~~*...................... ::~..............*......................... ;..... 10 Instrument Repair & Calibration...................................... :~:":.~.................. \\-.,.......................,................. 10 Library............................................................................................. :~$;~................... ~ *...*....*......*..**.*............... 10
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Operating Stat1st1cs...................................................................................... "*********************:....................... 14 Experiments Performed............................................................................... :.~.................'::*::~.................. 14 Unplanned Shutdowns....................................................................................... ::::. *............... :~;.............. 15 Changes Pursuant. to 10 CFR 50.59..................................................................... ::~~*\\*************.':::-.......... 15 Surveillance & Maintenance.....................*..................................... :............................ :::'*--~*********:.:....,:*** 16
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Personnel Doses.................... ;.... _........................................................................,.. ::.................................... 19..
e Facility Survey Data................ ::....................................*.................................... ::.................. :..... :............... 30 ***:"'.*
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'\\z:.,., e Part VI-Work Summary ************************************************************************::.*~:~......................................................................... 50 Teaching....................................................................... t:;~'......................... :.................................................... 50 Research & Service ********************************************~~:*:;:................................................................................... 50
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Documents Published or Accept':.d*:~:.................................................................................................. 70 Presentations..................................,,.-.::.............. ;.................................. :....................................................... 73 Students.*.................................... ?.~~:*.............................................................................................................. 76
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- Tables Table Title Page 111.1 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.......................... :....-.... 35 V.5 Annual Summary of Solid Waste Generated and Transferred............................ 36 V.6 Annual Summary of Personnel Radiation Doses Received............................. 37 V.7 Total Dose Equivalent Recorded Within the TRIGA Reactor Facility. :..................... 38 V.8 Total Dose Equivalent Recorded on Area Within the Radiation Center...................... 39 V.9 Annual Summary of Radiation and Contamination Levels Within the Reactor................. 41 V. 10 Total Dose Equivalent at the TRIGA Reactor Facility Fence............................. 42 V. 11 Total Dose Equivalent at the Off-Site Gamma Radiation Monitoring Stations................. 43 V. 12 Annual Average Concentration of the Total Net Beta Radioactivity........................ 44 V.13 Beta-Gamma Concentration and Range of LLD Values............ **.................. 45 V. 14 Radioactive Material Shipments under NRC General License R-106....................... 46 V. 15 Radioactive Material Shipments under Oregon License ORE 90005....................... 47 V. 16 Radioactive Material Shipments Under NRC General License 1 O CFR 110.23................. 47 '
VI. 1 Institutions and Agencies Which Utilized the Radiation Center.......................... 53 Vl.2 Listing of Major Research & Service Projects Performed and Their Funding..................
- 56 Vl.3 Summary of Radiological Instrumentation Calibrated to Support OSU Departments............. 68 Vl.4 Summary of Radiological Instrumentation Calibrated to Support Other Agencies............. 69 Figures Table IV.1 IV.2 IV.3 IV.4 V.1 Vl.1 Title Page Monthly Surveillance and Maintenance (Sample Form)................................................................................................. 20 Quarterly Surveillance and Maintenance (?ample Form)............................................................................................... 21 Semi-Annual Surveillance and Maintenance (Sample Form)........................................................................................23 Annual Surveillance and Maintenance (Sample Form)................................................................................................... 25 Monitoring Stations for the OSU TRiGA Reactor.............................................................................................................49 Summary of the Types of Radiological Instrumentation Calibrated.......................................................................... 68
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 67 different courses this year, mostly in the Department of Nuclear Engineering and Radia-tion Health Physics. About 28% of these courses involved the OSTR. The number of OSTR hours used for academic courses and training was 21, while 3,330 hours0.00382 days <br />0.0917 hours <br />5.456349e-4 weeks <br />1.25565e-4 months <br /> were used for research projects. Seventy-three percent (73%) of the OSTR research hours were in support of off-campus research projects, reflect-ing the use of the OSTR nationally and internationally. Radia-tion Center users published or submitted 51 articles this year, and made 48 presentations on work that involved the OSTR or Radiation Center. The number of samples irradiated in the reactor during this reporting period was 1,558. Funded OSTR use hours comprised 86% of the research use.
Personnel at the Radiation Center conducted 154 tours of the facility, accommodating 1,883 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 157. Reactor related projects comprised 74% of all projects. The total research dollars in some way supported by the Radiation Center, as reported by our researchers, was $11.3 million. The actual tptal is likely considerably higher. This year the Radia-tion Center provided service to 53 different organizations/
institutions, 32% of which were from other states and 47% of which were from outside the U. S. and Canada. So while the Center's primary mission is local, it is also a facility with a national and 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.
Introduction The current annual report of the Oregon State University Radiation Center and TRIGA Reactor follows the usual for-mat by including information relating to the entire Radiation Center rather than just the reactor. However, the information is still presented in such a manner that data on the reactor may be examined separately, if desired. It should be noted that all annual data given in this report covers the period from July 1, 2015 through June 30, 2016. Cumulative reactor operating data in this report relates only to the LEU fueled core. This covers the period beginning July 1, 2008 to the present date. For a summary of data on the reactor's two other cores, the reader is referred to previous annual reports.
In addition to providing general information about the activi-ties. of the Radiation Center, this report is designed to meet the reporting requirements of the U. S. Nuclear Regulatory 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 entire OSU campus, all other institutions within the Oregon University System, and many other universities and organiza-tions throughout the nation and the world. The Center also regularly provides special services to state and federal agencies, particularly agencies dealing with law enforcement, energy, health, and environmental quality, and renders assistance to Oregon industry. In addition, the Radiation Center provides permanent office and laboratory space for the OSU Depart-ment of Nuclear Engineering and Radiation Health Physics, the OSU Institute of Nuclear Science and Engineering, and for the OSU nuclear chemistry, radiation chemistry, geochem-istry and radiochemistry programs. There is no other university facility with the combined capabilities of the OSU Radiation Center in the western half of the United States.
Located in the Radiation Center are many items of special-ized equipment and unique teaching and research facilities.
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They include a TRI GA Mark II research nuclear reactor; a 6°Co gamma irradiator; a large number of state-of-the art computer-based gamma radiation spectrometers and associ-ated germanium detectors; and a variety of instruments for radiation measurements and monitoring. Specialized facilities for radiation work include teaching and research laboratories with instrumentation and related 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 instrumen-
. tation; 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 APlOOO reactor designs. The AP600 and APlOOO are next-generation nuclear reactor designs which incorporate many passive safety features as well as considerably simplified plant systems and equipment. APEX operates at pressures up to 400 psia and temperatures up to 450°F using electrical heaters instead of nuclear fuel. All major components of the AP600 and APlOOO are included in APEX and all systems are appropriately scaled to enable the experimental measure-ments to be used for safety evaluations and licensing of the full scale plant. This world-class facility meets exacting qual-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 reac-tors currently seeking NRC certification. The Test Facility is constructed of all stainless steel components and is capable of operation at full system pressure (1500 psia), and full system temperature (600F).
All components are 1/3 scale height and 11254.7 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.
15-16 Annual Report 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 fa-cilities-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 1.0MPa and a maximum core ceramic temperature of 1600°C.
The nominal working fluid will be helium with a core power of approximately 600 kW (note that electrical heaters are used to simulate the core power). The test facility also includes a scaled reactor cavity cooling system, a circulator and a heat sink in order to complete the cycle. The HTTF can be used to simulate a wide range of accident scenarios in gas reac-tors to include the depressurized conduction coold9wn 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 temperature 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.
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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.l, while individual names and projects are listed in Table VI.2.
Radiation Center Staff Steve Reese, Director Dina Pope, Office Manager Tara DiSante, Business Manager Brittany Combs, 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 Jim Darrough, Health Physicist Leah Mine, Neutron Activation Analysis Manager Steve Smith, Development Engineer, Senior Reactor Operator Chris Ku/ah, Reactor Operator Erin Cimbri, Custodian Joshua Graves, Reactor Operator (Student)
Trevor Howard, Reactor Operator (Student)
Griffen Latimer, Reactor Operator (Student)
Quinn Miller, Health Physics Monitor (Student)
Shara Howard, Health Physics Monitor (Student)
Kien Tran, Health Physics Monitor (Student)
Sophia Uchiyama, Health Physics Monitor (Student)
Reactor Operations Committee Andrew Klein, Chair OSU Nuclear Engineering and Radiation Health Physics Dan Harlan OSU Radiation Safety Abi Tavakoli Farsoni OSU Nuclear Engineering and Radiation Health Physics S. Todd Keller OSU Radiation Center Scott Menn OSU Radiation Center Steve Reese (not voting}
OSU Radiation Center Mark Trump Penn State University Celia Oney (not voting}
OSU Radiation Center Julie Tucker OSU Mechanical, Industrial and Manufacturing Engineering HaoriYang OSU Nuclear Engineering and Radiation Health Physics 15-16 Annual Report
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- re Professional and Research Faculty Farsoni,Abi Associate Professor, Nuclear Engineering & Radiation Health Physics
]ohnDeNoma Research Assistant
- Hamby, David Professor, Nuclear Engineering and Radiation Health Physics Hart, Lucas P.
Faculty Research Associate, Chemistry
- Higley, Kathryn A.
Department Head, Professor, Nuclear Engineering and Radiation Health Physics
- Keller, S. Todd Reactor Administrator, Radiation Center Klein,Andrew C.
Professor, Nuclear Engineering and Radiation Health Physics
- Krane, Kenneth S.
Professor Emeritus, Physics
- Loveland, Uizlter D.
Professor, Chemistry Marcum, Uizde Assistant Professor uclear Engineering and Radiation Health Physics
- Menn, ScottA.
Senior Health Physicist, Radiation Center
- Minc,Leah Associate Professor, Anthropology 15-16 Annual Report Camille Palmer Research Faculty and Instructor
- Palmer, Todd S.
People Professor, uclear Engineering and Radiation H ealth Physics
- Paulenova, Alena Associate Professor, Nuclear Engineering and Radiation Health Physics Pope, Dina Office Manager, Radiation Center
- Reese, Steven R.
Director, Radiation Center Reyes,]r.,]ose N.
Professor, uclear Engineering and Radiation H ealth Physics Tack, Krystina Assistant Professor, Medical Physics Program Director
- Celia Oney Reactor Supervisor, Radiation Center Aaron Weiss Faculty Research Assistant Woods, Brian Professor, uclear Engineering and Radiation H ealth Physics Wu, Qiao Professor, Nuclear Engineer and Radiation Health Physics Yanez, Ricardo Faculty Research Associate, Chemistry Yang,Haori Assistant Professor, Nuclear Engineering and Radiation Health Physics
- OSTR users for research and/or teaching
Eacili~ies Research Reactor The Oregon State UniversityTRIGA Reactor (OSTR) is a water-cooled, swimming pool type research reactor which uses uranium/zirconium hydride fuel elements in a circular grid ar-ray. The reactor core is surrounded by a ring of graphite which serves to reflect neutrons back into the core. The core is situ-ated near the bottom of a 22-foot deep water-filled tank, and the tank is surrounded by a concrete bioshield which acts as a radiation shield and structural support. The reactor is licensed by the U.S. Nuclear Regulatory Commission to operate at a maximum steady state power of 1.1 MW and can also be pulsed up to a peak power of about 2500 MW.
The OSTR has a number of different irradiation facilities including a pneumatic transfer tube, a rotating rack, a thermal column, 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 reactor 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 col-umn 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.
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- 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-filled aluminum irradiation tube is inserted into an inner grid position of the reactor core which would normally be oc-cupied by a fuel element. It is the same as the ICIT except for the presence of the cadmium lining.
The two main uses of the OSTR are instruction and research.
Instruction Instructional use of the reactor is twofold. First, it is used significantly for classes in Nuclear Engineering, Radiation Health Physics, and Chemistry at both the graduate and un-dergraduate levels to demonstrate numerous principles which have been presented in the classroom. Basic neutron behavior is the same in small reactors as it is in large power reactors, and many demonstrations and instructional experiments can be performed using the OSTR which cannot be carried out with a commercial power reactor. Shorter-term demonstration experiments are also performed for many undergraduate stu-dents in Physics, Chemistry, and Biology classes, as well as for visitors from other universities and colleges, from high schools, and from public groups.
The second instructional application of the OSTR involves educating reactor operators, operations managers, and health physicists. The OSTR is in a unique position to provide such education since curricula must include hands-on experience at an operating reactor and in associated laboratories. The many types of educational programs that the Radiation Center pro-vides are more fully described in Part VI of this report.
During this reporting period the OSTR accommodated a number of different OSU academic classes and other academic programs. In addition, portions of classes from other Oregon universities were also supported by the OSTR.
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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.
The OSTR's irradiation facilities provide a wide range of neutron flux levels and neutron flux qualities which are suf-ficient to meet the needs of most researchers. This is true not only for INAA, but also for other experimental purposes such as the 39 Ar/40 Ar ratio and fission track methods of age dat-ing samples.
Analytical Equipment The Radiation Center has a large variety of radiation detec-tion instrumentation. This equipment is upgraded as nec-essary, 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 instrumenta-tion may be made available on a loan basis to OSU research-ers in other departments.
Radioisotope Irradiation Sources The Radiation Center is equipped with a 10,200 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 of radiation chemistry; dosimeter testing; steril-ization of food materials, soils, sediments, biological speci-men, and other media; gamma radiation damage studies; and
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other such applications. In addition to the 6°Co irradiator, the Center is also equipped with a variety of smaller 6°Co, 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 differ-ent 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.1 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 academic 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.
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.
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All of the laboratories and classrooms are used extensively dur-ing the academic year. A listing of courses accommodated at the Radiation Center during this reporting period along with their enrollments is given in Table III.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. In addition, the absence of any comparable facility in the state has led to a greatly expanded instrument calibration program for the Center, including calibration of essentially all radiation detection 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 Commission, 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 collections 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 Regulatory Commission, and other federal agencies. Therefore, the Center library maintains a current collection ofleading nuclear re-search 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.
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The Center maintains an up-to-date set of reports from such org:inizations 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 ofTransportation, 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 technical orientations which are required for personnel working with radiation and radioactive materials. These tapes are repro-duced, 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 Purpose oflrradiation Sterilization Material Evaluation Botanical Studies Other Totals 15-16 Annual Report Gammacell 220 6°Co lrradiator Use Samples Dose Range
{rads) wood, soil, polymers, 1.5x106 to 3.0x106 nanofibers, carbon filter silicon polymers, 3.0x105 to 3.0x105 polymers
. pollen, hops, barley 2.0x102 to 1.2x104 sludge 4.6x107 to 4.6x107 Number of Use Time Irradiations
{hours) 15 50 17 7
17 0.09 1
66 50 123.09
Course#
NE/RHP 114*
NE/RHP 115 NE/RHP234 NE/RHP235 NE/RHP 236*
NE311 NE312 NE319 NE331 NE332 NE/RHP333 NE/RHP/MP 401/501/601 NE/RHP/MP 40515051605 NE/RHP/MP 406/506/606 NE/RHP/MP 4071507/607 NE/RHP/MP 410/510/610 NE/ RHP 4151515 NE 4511551 NE 4521552 NE 4551555**
NE 4561556**
NE 4571557**
NE 467/567 NE667 NE/RHP 4351535 NE565 NE 473/573 Table 111.2 Student Enrollment in Courses Which are Taught or Partially Taught at the Radiation Center Number of Students CREDIT COURSE TITLE Summer Fall Winter 2015 2015 2016 2
Introduction to Nuclear Engineering and Radiation 50 Health Physics 2
Introduction to Nuclear Engineering and Radiation 63 Health Physics 4
Nuclear and Radiation Physics I 60 4
Nuclear and Radiation Physics II 60 4
Nuclear Radiation Detection & Instrumentation 4
Intro to Thermal Fluids 8
23 16 4
Thermodynamics 15 3
Societal Aspects of Nuclear technology 80 4
Intro to Fluid Mechanics 19 4
Heat Transfer 14 7
3 Mathematical methods for NE/RHP 1-16 Research 2
22 18 1-16 Reading and Conference 22 1-16 Projects 1
Nuclear Engineering Seminar 76 65 1-12 Internship 1
2 Nuclear Rules and Regulations 44 4
Neutronic Analysis 57 4
Neutronic Analysis 58 3
Reactor Operator Training I 3
Reactor Operator Training II 3
Neuclear Reactor Lab 4
Nuclear Reactor Thermal Hydraulics 42 4
Nuclear Reactor Thermal Hydraulics 3
External Dosimetry & Radiation Shielding 3
Applied Thermal Hydraulics 9
3 Nuclear Reactor Systems Analysis 29 Spring 2016 55 18 13 13 65 22 1
76 1
59 12 54 15-16 Annual Report
~--**
Table 111.2 (continued)
Student Enrollment in Courses Which are Taught or Partially Taught at the Radiation Center Facilities __
Number of Students Course#
CREDIT COURSE TITLE NE/RHP 474/574 4
Nuclear System Design I NE/RHP 4751575 4
Nuclear System Design II NE/RHP479*
1-4 Individual Design Project NE/RHP481*
4 Radiation Protection NE/RHP 582*
4 Applied Radiation Safety RHP 483/583 4
Radiation Biology RHP 488/588*
3 Radioecology NE/RHP 590 4
Internal Dosimetry NE/RHP/MP 503/603*
1 Thesis NE/RHP 516*
4 Radiochemistry NE526 3
Numerical Methods for Engineering Analysis NE/RHP/MP 531 3
Nuclear Physics for Engineers and Scientists NE/RHP/MP 536*
3 Advanced Radiation Detection &Measurement NE/RHP 537 3
Digital Spectrometer Design MP541 3
Diagnostic Imaging Physics NE550 3
Nuclear Medicine NE553 3
Advanced Nuclear Reactor Physics MP563 4
Applied Medical Physics NE 468/568 3
Nuclear Reactor Safety NE/RHP/MP 599 Special Topics Course From Other OSU Departments CH233*
5 General Chemistry CH233H*
5 Honors General Chemistry CH462*
3 Experimental Chemistry II Laboratory ENGR 111*
3 Engineering Orientation ENGR212H*
3 Honors Engineering ST Special Topics OSTR used occasionally far demonstration and/or experiments OSTR used heavily 15-16 Annual Report Summer Fall Winter Spring 2015 2015 2016 2016 50 49 32 6
14 8
5 12 41 43 43 4
11 8
8 4
18 4
18 8
27 15 4
89 806 30 23 269 28 14
---~------~~-~
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Operating Statistics During the operating period between July 1, 2015 and June 30, 2016, the reactor produced 1476 MWH of thermal power during its 1566 critical hours.
Experiments Performed During the current reporting period there were ten ap-proved reactor experiments available for use in reactor-related programs. They are:
A-1 B-3 Normal TRI GA Operation (No Sample Irradia-tion).
- Irradiation of Materials in the Standard OSTR Irradiation Facilities.
B-11 Irradiation of Materials Involving Specific Qyantities of Uranium and Thorium in the Standard OSTR Irradiation Facilities.
B-12 Exploratory Experiments.
B-23 Studies UsingTRIGA Thermal Column.
B-29 Reactivity Worth of Fuel.
B-31 TRI GA Flux Mapping.
B-33 Irradiation of Combustible Liquids in LS.
B-34 Irradiation of Enriched Uranium in the Neutron Radiography Facility.
B-35 Irradiation of Fissile Materials in the Prompt Gamma Neutron Activation Analysis (PGNAA)
Facility.
Of these available experiments, five were used during the reporting period. Table IV.4 provides information related to the frequency of use and the general purpose of their use.
Inactive Experiments Presently 33 experiments are in the inactive file. This consists of experiments which have been performed in the past and may be reactivated. Many of these experi-ments are now performed under the more general experi-ments listed in the previous section. The following list identifies these inactive experiments.
A-2 A-3 A-4 A-5 A-6 A-7 B-1 B-2 B-4 B-5 B-6 B-7 B-8 B-9 Measurement of Reactor Power Level via Mn Activation.
Measurement of Cd Ratios for Mn, In, and Au in Rotating Rack.
Neutron Flux Measurements in TRI GA.
Copper Wire Irradiation.
In-core Irradiation ofLiF Crystals.
Investigation ofTRIGA's Reactor Bath Water Temperature Coefficient and High Power Level Power Fluctuation.
Activation Analysis of Stone Meteorites, Other Meteorites, 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 Measurements.
Measurements of Neutron Spectra in External Irradiation Facilities.
Measurements of Gamma Doses in External Ir-radiation Facilities.
Isotope Production.
Neutron Radiography.
B-10 Neutron Diffraction.
B-13 This experiment number was changed to A-7.
B-14 Detection of Chemically Bound Neutrons.
B-15 This experiment number was changed to C-1.
B-16 Production and Preparation of 18F.
B-17 Fission Fragment Gamma Ray Angular Cor-relations.
B-18 A Study of Delayed Status (n, y) Produced Nuclei.
B-19 Instrument Timing via Light Triggering.
B-20 Sinusoidal Pile Oscillator.
B-21 Beam Port #3 Neutron Radiography Facility.
B-22 Water Flow Measurements Through TRI GA Core.
B-24 General Neutron Radiography.
B-25 Neutron Flux Monitors.
B-26 Fast Neutron Spectrum Generator.
B-27 Neutron Flux Determination Adjacent to the OSTRCore.
B-28 Gamma Scan of Sodium (TED) Capsule.
B-30 NAA ofJet, Diesel, and Furnace Fuels.
B-32 Argon Production Facility C-1 Pu02 Transient Experiment.
Unplanned Shutdowns There were eleven unplanned reactor shutdowns during the current reporting period. Table IV.5 details these events.
Changes Pursuant to10 CFR 50-59 There was one safety evaluation performed in support of the reactor this year. It was:
15-04, Experiment B-35 ChangesDescription
Description:
This allows for encapsulation requirements for Experiment B-35, "Irradiation of Enriched Urani-um in the Prompt Gamma Neutron Activation Analy-sis Facility," to be modified or waived with permission of the Senior Health Physicist and Reactor Supervisor.
There were ten new screens performed in support of the reactor this year. They were:
15-16 Annual Report 15-04, Changes to OSTROPs 2 and 3 Description Minor updates and grammatical corrections to startup and shutdown checklist procedures.
15-05, Changes to OSTROP 1 Description Minor updates to the Emergency Operating Procedures for clarity and consistency.
15-06, Stack & Cam Upgrades Description Modifies the Reactor Top and Stack Continuous Air Monitors to have a combined Magnahelic gauge and transmitter, new flow control buttons at the pump and in the control room, and a ball valve in the Stack CAM sample line.
15-07, Changes to the Pneumatic Rabbit System Description Reverses the changes performed under screen 14-04, returning the system to its previous configuration.
15-08, Changes to OSTROPs 22 and 27 Description Cancels OSTROP 27 and moves all information in it that is still applicable to OSTROP 22. Additional corrections and updates based on recent changes to the electrical power system.
15-09, Changes to OSTROP 6 Description Updates staffing requirements so that a Reactor Opera-tor Trainee may be counted as the second person in the facility for minimum staffing if that trainee has approval from the Director, Reactor Administrator, and Reactor Supervisor.
15-10, Changes to OSTROPs 13, 14, and 15 Description Minor updates and corrections to the Monthly, Qyar-terly, and Semi-annual Surveillance procedures.
15-11, Changes to RCHPP 1 Description Minor corrections and clarifications to the Guidelines for the Radiation Protection Program at the OSU Radiation Center.
16-01, Changes to OSTROP 4 Description Changes the square wave procedure to allow this opera-tion to be performed starting from initial powers of up to lkW.
16-02, Changes to RCHPP 5 and 6 Description Updates and corrections to the procedures for receiving and shipping radioactive materials.
Surveillance and Maintenance Non-Routine Maintenance July2015 Redid the windings on the ventilation exhaust fan motor following a motor failure.
August2015 Replaced bulbs in Safety Rod ON indicator.
Replaced broken float valve in secondary cooling tower September 2015 Replaced the exhaust fan for room DlOO.
Installed a new seal on the secondary pump to stop a water leak.
-- ---=------==--~--*
October 2015 Changed out some capacitors and other small parts in the power supplies for the power channels in the console's left-hand drawer.
Replaced four connectors in the cables for the Safety Channel.
November 2015 Replaced the Safety Channel Uncompensated Ion Chamber.
Installed new Magnahelics on the Stack and CAM (combined flow gauge and transmitter). Also added new flow control switches at the pumps and in the control room.
December 2015 Replaced the Safety Rod magnet.
Replaced a broken fan belt on the air compressor in the Heat Exchanger Room.
February 2016 Put new bearings and connector tubing on the argon exhaust fan.
Installed a new rabbit blower.
March2016 Performed repairs on the ventilation supply fan (new bearings, fan belt, and motor windings).
April2016 Replaced the CAM pump motor.
Repaired the emergency generator due to issues with the fuel injection system.
June2016 Applied adhesive to a shroud that had come loose from a bearing on the ventilation exhaust fan.
Used a waterproof camera to perform a visual inspec-tion of all positions of the rotating rack.
15-16 Annual Report
~-
- -->*-~
~---~-' ---
Table IV.1 Present OSTR Operating Statistics Operational Data For LEU Core MWH of energy produced MWD of energy produced Grams 235U used Number of fuel elements added to ( +) or removed(-) from the core Number of pulses Hours reactor critical Hours at full power (1 MW)
Number of startup and shutdown checks Number of irradiation requests processed Number of samples irradiated 15-16 Annual Report Annual Values (2015/2016) 1,476 61.5 85 0
25 1,566 1,477 254 269 1,558 Cumulative Values 10,138 413.3 581 90 251 10,913 10,108 1,686 1,815 13,348
-- - - - - - - -----:----:---~-~~ -'-
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) 21 13,693 OSU research 887 19,671 Off campus research 2,443 47,466 Facility time 57 7,318 Total Reactor Use Time 3,408 88,148*
- Demonstrations and Preclude Time are no longer tracked. The cumulative hours in this table are the sum of the remaining categories listed.
Number of Users Two Three Four Five Six Seven Eight Total Multiple Use Time Table IV.3 OSTR Multiple Use Time Annual Values (hours) 631 335 108 48 15 1
0 1,138 Cumulative Values (hours) 10,011 5,203 2,752 989 256 70 3
19,284 15-16 Annual Report
Reactor Table IV.4 Use of OSTR Reactor Experiments Experiment Research Teaching Facility Use Total Number A-1 2
4 7
13 B-3 230 12 4
246 B-12 1
0 0
1 B-31 0
0 3
3 B-35 6
0 0
6 Total 239 16 14 269 Table IV.5 Unplanned Reactor Shutdowns and Scrams Type of Event Number of Cause of Event Occurrences Mannual 2
Dropped safety rod Mannual 1
Transient rod low air pressure Manual 1
CAM Particulate high activity Period 1
Operator error in square wave set-up Period 2
Noise on fission chamber during startup Safety channel high power 2
Operator error during startup Safety channel high power 1
Discrepancy between safety and linear readings at full power Safety channel high power 1
Fluctuation due to noise on channel 15-16 Annual Report
.£.
Figure IV.1 Monthly Surveillance and Maintenance (Sample Form)
OSTROP 13, Rev. LEU-5 Surveillance & Maintenance for the Month of SURVEILLANCE & MAINTENANCE TARGET DATE DATE REMARKS LIMITS AS FOUND NOTTO BE
[SHADE INDICATES LICENSE REQUIREMENT]
DATE EXCEEDED*
COMPLETED INITIALS MAXIMUM HIGH:
INCHES REACTOR TANK HIGH AND LOW WATER I
LEVEL ALARMS MOVEMENT LOW:
INCHES
+/- 3 INCHES ANN:
2 BULK WATER TEMPERATURE ALARM CHECK FUNCTIONAL Tested @ __
3A CHANNEL TEST OF STACK CAM GAS CHANNEL 8.5x l0'+/-
Ann.?
cpm Ann.
8500 cpm 3B CHANNEL TEST OF STACK CAM PARTICULATE 8.5x l0'+/-
Ann.?
Ann.
CHANNEL 8500 cpm cpm 3C CHANNEL TEST OF REACTOR TOP CAM 8.5x I 0'+/-
Ann.?
Ann.
PARTJCULATE CHANNEL 8500 cpm cpm 4
MEASUREMENT OF REACTOR PRIMARY
<5 µmho\\cm WATER CONDUCTIVITY 5
PRJMARY 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 PRJMARY PUMP BEARJNG OIL LEVEL CHECK OSTROP 13.10 NEED OIL?
NIA 11 EMERGENCY DI ESEL GENERATOR CHECKS
> 50%
Oi l ok?
NIA Total hours 12 RABBIT SYSTEM RUN TIME Total hours/Hours NIA on current brushes 13 OIL TRANSIENT ROD BRONZE BEARING WD40 NIA 14 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.
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Figure IV.2 Quarterly Surveillance and Maintenance (Sample Form)
OSTROP 14, Rev. L EU-3 Surveillance & Maintenance for the 1st I 2"d I 3 rd I 4th Quarter of 20 _
SURVEILLANCE & MAINTENANCE LIMITS AS FOUND TARGET DATE NOTTO DATE REMARKS&
[SHADE INDICATES LICENSE REQUIREMENT]
DATE BE EXCEEDED*
COMPLETED INITIALS I
REACTOR OPERATION COMMITTEE (ROC) AU DIT QUARTERLY 2
QUARTERLY ROC MEETING QUARTERLY 3
ERP INSPECTIONS QUARTERLY 4
ROTATING RACK CHECK FOR UNKNOWN SAMPLES EMPTY 5
WATER MONITOR ALARM CHECK FUNCTIONAL 6A CHECK FILTER TAPE SPEED ON STACK MONITOR
!"/HR+/- 0.2 6B CHECK FILTER TAPE SPEED ON CAM MONITOR l"/HR+/-0.2 7
INCORPORATE 50.59 & ROCAS INTO DOCUMENTATION QUARTERLY ARM SYSTEM ALARM CHECKS ARM I
2 3S 3E 4
5 7
8 9
10 11 12 AUD 8
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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(j'\\
)>
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- s c:
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0 Figure IV.2 (continued)
Quarterly Surveillance and Maintenance (Sample Form)
OSTROP 14, Rev. LEU-3 Surveillance & Maintenance for the 1 st I 2"d I 3 rd I 4 th Quarter of 2 0 SU RVEILLANCE & MAINTENANCE LIMITS AS FOUND DATE REMARKS&
[SHADE INDICATES LICENSE REQUIREMENT]
COMPLETED fNITLALS OPERATOR NAME a) TOTAL OPERATION TIME b) DATE OF OPERATING EXERCISE REMARKS & IN ITIALS a) 2:4 hours: at console (RO), at console or as Rx.
Sup. (SRO) 9 b) Date Completed Operating Exercise
1 * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *
- Figure IV.3 Semi-Annual Surveillance and Maintenance (Sample Form)
OSTROP 1 5, Rev. LEU-3 Surveillance & Maintenance for the 1 st I 2 nd Half of 2 0 SURVEILLANCE & MAJNTENANCE TARGET DATE NOT DATE REMARKS
[SHADE INDICATES LICENSE REQUIREMENT]
LIMITS AS FOUND DATE TOBE COMPLETED EXCEEDED*
INITIALS NO WITHDRAW NEUTRON SOURCE COUNT RATE INTERLOCK
~5 cps TRANSIENT ROD AIR INTERLOCK NO PULSE CHANNEL TESTS PULSE MODE ROD MOVEMENT INTERLOCK NO MOVEMENT I
OF REACTOR INTERLOCKS PULSE INTERLOCK ON RANGE SWITCH NO PULSE MAXIMUM PULSE REACTIVITY INSERTION LI MIT
~ $2.25 TWO ROD WITHDRAWAL PRHOHJBIT I ONLY PULSE PROHIBIT ABOVE I kW
~ I kW 2
SAFETY PERIOD SCRAM
~3 sec Cl RCUIT TEST PREVIOUS PULSE DATA FOR COMPARION
'.020%
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 IS.VII 8
INVERTER MAINTENANCE See User Manual 9
STANDARD CONTROL ROD MOTOR CHECKS L0-1 7 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.
Figure IV.3 (continued)
Semi-Annual Surveillance and Maintenance (Sample Form)
OSTROP 15, Rev. LEU-2 Surveillance & Maintenance for the 1 st I 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)
@ 100 V. I =
AMPS FISSION CHAMBER RESISTANCE
@ 900 V. I =
AMPS NONE II 800 v (Info Only)
CALCULATION L'.I =
AMPS R=--
L'. I R =
n HIGH 12 FUNCTIONAL CHECK OF HOLDUP TANK WATER LEVEL ALARMS OSTROP ISJUI FULL BRUSH INSPECTION INSPECTION OF THE PNEUMATIC TRANSFER 13 SYSTEM Observed SAMPLE INSERTION AND WITHDRAWAL insertion/withdrawal TIME CHECK time
- Date not to be exceeded is only applicable to shaded items. It is equa l to the date last time plus 7 1/2 months.
1 * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *
- I-'
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0
.-+
Figure IV.4 Annual Surveillance and Maintenance (Sample Form)
OSTROP 16, Rev. LEU-2 Annual Surveillance and Maintenance for 20 SURVEJLLANCE 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 JNSPECTON OSTROP 16.2 NORMAL 3
CONTROL ROD CALIBRATION:
CLJCIT OSTROP9.0
!CIT/DUMMY TRANS SAFE SHIM REG CONTROL ROD SCRAM
- 2sec WITHDRAWAL 4
INSERTION &
W/D
<50 sec SCRAM TIMES INSERT
.::;50 sec FUEL ELEMENT INSPECTION FOR SELECTED
~ LU~o tt-:'s mspected.
5 ELEMENTS No damage rl c o
- n
- or U/~ 11 6
REACTOR POWER CALIBRATION OSTROP8 7
FUEL ELEMENT TEMPERATURE CHANNEL Per Checklist CALIBRATJON 8
CALIBRATION OF REACTOR TANK WATER TEMP OSTROP 16.8 TEMPERATURE METERS CONTINUOUS Particulate Monitor 9
AIR MONITOR RCHPP18 CALIBRATJON Gas Monitor 10 CAM OIL/GREASE MAINTENANCE STACK MONITOR Particulate Monitor RCHPP 11 CALIBRATION 18 & 26 Gas Monitor 12 STACK MON ITOR 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 requirements it is equal to the date completed last time olus 2 1/2 vears.
I-"
lJ1 I
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)>
- J
- J c:
QJ
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0 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 TARG ET DATE NOT DATE REMARKS LIMITS TOBE
[SHADE INDICATES LICENSE REQUIREMENT]
FOUND DATE EXCEEDED*
COMPLETED
& INITIALS NORMAL$
14 CORE EXCESS
_:5_$7.55 ICIT $ -
CLICIT $ -
DAMPERS 15T FLOOR 15 REACTOR BAY VENTILATION SYSTEM SHUTDOWN TEST CLOSE IN <5 SECONDS 4'FLOOR -
16 DECOMMISSIONCNG COST UPDATE NIA NIA AUGUST 17 SNM PHYSICAL INVENTORY NIA NIA OCTOBER 18 MATERIAL BALANCE REPORTS NIA NIA NOVEMBER CFO TRAINING GOOD SAM TRACNING ERP REVIEW ERPDRJLL CPR CERT FOR:
CPR CERT FOR:
EMERGENCY 19
RESPONSE
FlRST AID CERT FOR:
PLAN FIRST AID CERT FOR:
EVACUATION DRILL AUTO EVAC ANNOUNCEMENT TEST ERP EQUIPMENT INVENTORY BIENNIAL SUPPORT AGREEMENTS PSPREVJEW PHYSICAL PSP DRILL 20 SECURITY OSPIDPS TRAINING PLAN LOCK/SAFE COMBO CHANGES AUTHORIZATION LIST UPDATE
- Date not be exceeded is only applicable to shaded items. It is equal to the date completed last year plus 15 months.
For biennial license requirements, it is equal to the date completed last time plus 2 112 years.
- j
1 * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *
- 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 DAI c NU I DATE REMARKS
[SHADE INDJCATES LICENSE REQUIREMENT]
LIMITS FOUND DATE TOBE COMPLETED
& INITIALS FX FF I l F I l
- 21 ANNUAL REPORT NOV I OCT I NOV I 22 KEY INVENTORY ANNUAL 23 REACTOR TANK AND CORE COMPONENT NO WHITE SPOTS INSPECTION 24 EMERGENCY LJGHT LOAD TEST RCHPP 18.0 25 NEUTRON RADJOGRAPHY FACILTIY INTERLOCKS 26 PGNAA FACILITY INTERLOCKS ANNUAL REQUALIFJCATION BIENNIAL MEDICAL EVERY 6 YEARS LICENSE REACTOR OPERATOR LICENSE CONDITIONS WRJTTEN EXPIRATION OPERATrNG TEST APPLICATION EXAM DATE DATE DATE DUE COMPLETED DUE DATE OPERATOR NAME DATE DATE DATE DUE PASSED DATE DUE PASSED DATE MAILED 27
- Date not be exceeded is only applicable to shaded items. It is equal to the date completed last year plus 15 months.
For biennial license requirements, it is equal to the date completed last time plus 2 1/2 years.
Radiation ProtectiOn Introduction The purpose of the radiation protection program is to ensure the safe use of radiation and radioactive material in the Cen-ter's teaching, research, and service activities, and in a similar manner to the fulfillment of all regulatory requirements of the State of Oregon, the U.S. Nuclear Regulatory Commission, and other regulatory agencies. The comprehensive nature of the program is shown in Table V.1, which lists the program's major radiation protection requirements and the performance frequency for each item.
The radiation protection program is implemented by a staff consisting of a Senior Health Physicist, a Health Physicist, and several part-time Health Physics Monitors (see Part II).
Assistance is also provided by the reactor operations group, the neutron activation analysis group, the Scientific Instrument Technician, and the Radiation Center Director.
The data contained in the following sections have been prepared to comply with the current requirements of Nuclear Regulatory Commission ( RC) Facility License No. R-106 (Docket
- o. 50-243) and the Technical Specifications con-tained in that license. The material has also been prepared in compliance with Oregon Department of Energy Rule No.
345-30-010, which requires an annual report of environmental effects due to research reactor operations.
Within the scope of Oregon State University's radiation pro-tection program, it is standard operating policy to maintain all releases of radioactivity to the unrestricted environment and all exposures to radiation and radioactive materials at levels which are consistently "as low as reasonably achievable" (ALARA).
Environmental Releases The annual reporting requirements in the OSTR Technical Specifications state that the licensee (OSU) shall include "a summary of the nature and amount of radioactive effluents released or discharged to the environs beyond the effective control of the licensee, as measured at, or prior to, the point of such release or discharge." The liquid and gaseous effluents released, and the solid waste generated and transferred are discussed briefly below. Data regarding these effluents are also summarized in detail in the designated tables.
Liquid Effluents Released Liquid Effluents Oregon State University has implemented a policy to re-duce the volume of radioactive liquid effluents to an absolute minimum. For example, water used during the ion exchanger resin change is now recycled as reactor makeup water. Waste water from Radiation Center laboratories and the OSTR is collected at a holdup tank prior to release to the sanitary sewer.
Liquid effluent are analyzed for radioactivity content at the time it is released to the collection point. For this reporting period, the Radiation Center and reactor made seven liquid ef-fluent releases to the sanitary sewer. All Radiation Center and reactor facility liquid effluent data pertaining to this release are contained in Table V.2.
Liquid Uiiste Generated and Transferred Liquid waste generated from glassware and laboratory experi-ments is transferred by the campus Radiation Safety Office to its waste processing facility. The annual summary of liquid waste generated and transferred is contained in Table V.3.
15-16 Annual Report
~-:.:_:~-
--~:
*-=--
Airborne Effluents Released Airborne effiuents are discussed in terms of the gaseous com-ponent and the particulate component.
Gaseous Effluents Gaseous effiuents from the reactor facility are monitored by the reactor stack effiuent monitor. Monitoring is continuous, i.e., prior to, during, and after reactor operations. It is normal for the reactor facility stack effiuent monitor to begin opera-tion as one of the first systems in the morning and to cease operation as one of the last systems at the end of the day. All gaseous effiuent data for this reporting period are summarized in Table V.4.
Particulate effiuents from the reactor facility are also moni-tored by the reactor facility stack effiuent monitor.
Particulate Effluents Evaluation of the detectable particulate radioactivity in the stack effiuent confirmed its origin as naturally-occurring radon daughter products, within a range of approximately 3x10-11
µCi/ml to 1 x 10-9 µCi/ml. This particulate radioactivity is predominantly 214Pb and 214Bi, which is not associated with reactor operations.
There was no release of particulate effiuents with a halflife greater than eight days and therefore the reporting of the average concentration of radioactive particulates with half lives greater than eight days is not applicable.
Solid Waste Released Data for the radioactive material in the solid waste generated and transferred during this reporting period are summarized in Table V.5 for both the reactor facility and the Radiation Center. Solid radioactive waste is routinely transferred to OSU Radiation Safety. Until this waste is disposed of by the Radiation Safety Office, it is held along with other campus radioactive waste on the University's State of Oregon radioac-tive materials license.
Solid radioactive waste is disposed of by OSU Radiation Safety by transfer to the University's radioactive waste disposal vendor.
15-16 Annual Report Radiation Protection_
Personnel Dose The OSTR annual reporting requirements specify that the licensee shall present a summary of the radiation exposure re-ceived by facility personnel and visitors. The summary includes all Radiation Center personnel who may have received expo-sure to radiation. These personnel have been categorized into six groups: facility operating personnel, key facility research personnel, facilities services maintenance personnel, students in laboratory classes, police and security personnel, and visitors.
Facility operating personnel include the reactor operations and health physics staff. The dosimeters used to monitor these in-dividuals include quarterly TLD badges, quarterly track-etch/
albedo neutron dosimeters, monthlyTLD (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 quarterly TLD film badge and TLD (finger) extremity dosimeters. If the possibility of neutron exposure exists, researchers are also monitored with a track-etch/ albedo neutron dosimeter.
Facilities Services maintenance personnel are normally issued a gamma sensitive electronic dosimeter as their basic monitor-ing device.
Students attending laboratory classes are issued quarterly Xi?,(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 Xi?,(y) TLD badge to be used during their patrols of the Ra-diation 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 radioactive materials.
An annual summary of the radiation doses received by each of the above six groups is shown in Table V.6. There were no per-sonnel radiation exposures in excess of the limits in 10 CFR 20 or State of Oregon regulations during the reporting period.
Facility Survey Data The OSTR Technical Specifications require an annual summary of the radiation levels and levels of contamination observed during routine surveys performed at the facility. The Center's comprehensive area radiation monitoring program encompasses the Radiation Center as well as the OSTR, and therefore monitoring results for both facilities are reported.
Area 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 plastic 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 character-istic data on the status of radiological conditions. A second objective of the program is to assure frequent on-the-spot personal observations (along with recorded data), which will provide advance warning of needed corrections and thereby help to ensure the safe use and handling of radiation sources and radioactive materials. A third objective, which is really
~ ______.--
derived from successful execution of the first two objectives, is to gather and document information which will help to ensure that all phases of the operational and radiation protection programs are meeting the goal of keeping radiation doses to personnel and releases of radioactivity to the environment "as low as reasonably achievable" (ALARA).
The annual summary of radiation and contamination levels measured during routine facility surveys for the applicable reporting period is given in Table V.9.
Environmental Survey Data The annual reporting requirements of the OSTR Technical Specifications include "an annual summary of environmental surveys 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 reactor facility stack effluent monitor described in Section V and nine environmental monitoring stations.
During this reporting period, each fence environmental sta-tion utilized an LiF TLD monitoring packet supplied and pro-cessed 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 sta-tions x 3 TLDs per station x 4 quarters). The total number of TLD 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 TRI GA 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 Labora-tory, respectively). These monitors are exchanged and processed quarterly, and the total number ofTLD samples during the 15-16 Annual Report
-~.----
- --~<--~--=~~
current one-year reporting period was 240 (20 stations x 3 chips per station per quarter x 4 quarters per year). The total number ofTLD samples for the reporting period was 240. A summary ofTLD data for the off-site monitoring stations is given in Table V.11.
After a review of the data in Table V.11, it is concluded that, like the dosimeters on the TRI GA 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.l.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.l.
There are a total of 22 sampling locations: four soil locations, 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 disin-tegration rate incorporates subtraction of only the count-ing system 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.
15-16 Annual Report Radiation P1*otecfio~
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 con-ducted if unusual radioactivity levels above natural background were detected. However, from Table V.12 it can be seen that the levels of radioactivity detected were consistent with natu-rally occurring radioactivity and comparable to values reported.
in previous years.
Radioactive Materials Shipments A summary of the radioactive material shipments originat-ing 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 ra-dioactive materials license ORE 90005 is shown in Table V.15.
A summary of radioactive material shipments exported under Nuclear Regulatory Commission general license 10 CFR 110.23 is shown in Table V.16.
References
- 1. U. S. Environmental Protection Agency, "Estimates oflonizing Radiation Doses in the United States, 1960-2000," 0 RP /CSD 72-1, Office of Radiation Programs, Rockville, Maryland (1972).
- 2. U. S. Environmental Protection Agency, "Radiologi-cal Qiality of the Environment in the United States, 1977," EPA 520/1-77-009, Office of Radiation Programs; Washington, D.C. 20460 (1977).
TableV.1 Radiation Protection Program Requirements and Frequencies Frequency Radiation Protection Requirement Daily/\\iVeekly/Monthly 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 Monthly 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.
As Required Perform and record special radiation surveys.
Perform thyroid and urinalysis bioassays.
Conduct orientations and training.
Issue radiation work permits and provide health physics coverage for maintenance operations.
Prepare, exchange and process environmental TLD packs.
Conduct orientations for classes using radioactive materials.
Q.9arterly Collect and analyze samples from reactor stack effluent line.
Exchange personnel dosimeters and inside area monitoring dosimeters, and review exposure reports.
Semi-Annual Leak test and inventory sealed sources.
Conduct floor survey of corridors and reactor bay.
Calibrate portable radiation monitoring instruments and personnel pocket ion chambers.
Calibrate reactor stack effluent monitor, continuous air monitors, remote area radiation monitors, and air samplers.
Measure face air velocity in laboratory hoods and exchange dust-stop filters and HEPA Annual filters as necessary.
Inventory and inspect Radiation Center emergency equipment.
Conduct facility radiation survey of the 6°Co irradiators.
Conduct personnel dosimeter training.
Update decommissioning logbook.
Collect and process environmental soil, water, and vegetation samples.
15-16 Annual Report
r ********************************************
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TableV.2 Monthly Summary of Liquid Effluent Release to the Sanitary Sewer<1>
Specific Activity for Total C2.1iantity of Average Percent of Applicable Total Each Detectable Ra-Date of C2.1iantity of Detectable dionuclide in Each Detectable Concentration Monthly Average Discharge Radionuclide Of Released Concentration for (Month and Radioactivity Radionuclide the Waste, Where the Released in the Radioactive Material Released Radioactive Released in the Waste Release Concentration Year)
(Curies)
Was>l x 10-7 Waste at the Point of Release Material (Curies)
(µCiml-1)
(%)(2)
(µCi ml-1)
Nov2015 9.44x10-7 Co-60 Co-60, 2.26x10-7 Co-60, 9.44x10-7 Co-60, 1.92x10-9 Co-60, 0.006 Dec2015 NIA NIA NIA NIA NIA NIA Annual Total for Radiation 9.44x10-7 Co-60 Co-60, 2.26x10-7 Co-60, 9.44x10-7 1.92x10-9 0.006 Center (1) The OSU operational policy is to subtract only detector background from the water analysis data and not background radioactivity in the Corvallis city water.
(2) Based on values listed in 10 CFR 20, Appendix B to 20.1001 - 10.2401, Table 3, which are applicable to sewer disposal.
Total Volume of Liquid Effiuent Released Including Diluent (gal) 129,712 131,723 261,435 I
'\\. j/f
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! I I
I i
I I
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I
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0 =
~
~ =
~
~\\
,F\\
'I
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¥ Table V.3 Annual Summary of Liquid Waste Generated and Transferred Volume of Liquid Detectable Total Qgantity of Dates of Waste Pickup Origin of Liquid (1)
Radionuclides Radioactivity in the for Transfer to the Waste Waste Packaged Waste Processing (gallons) in the Waste Waste (Curies)
Facility 10/12/15 Radiation Center Pu-239, U-233, Cs-134.
Laboratories 29.4 H-3, C-14, U-238,Am-241, 5.97x10-4 3/16/16 Sr-90, Ra-226 5/27/16 TOTAL 29.4 See above 5.97x10-4 (1)
OSTR and Radiation Center liquid waste is picked up by the Radiation Safety Office for transfer to its waste processing facility for final packaging.
15-16 Annual Report
TableV.4 M ont hi TRIGA R y
ea ct or G aseous w aste o* h ISC argesan dA na1ys1s Estimated
. Fraction of the Technical Total Total Atmospheric Diluted Specification Month Estimated Estimated Qyantity of Concentration of Annual Average Activity Argon-41 Argon-41 at Point of Released (Curies)
ReleasedC1> (Curies)
Release Argon-41
(µCi/cc)
Concentration Limit {%)
July 1.40 1.40 1.11x10-7 2.77 August 1.32 1.32 1.05x10-7 2.62 September 0.99 0.99 8.12x10-8 2.03 October 1.57 1.57 1.25x10-7 3.12 November 1.52 1.52 1.25x10-7 3.11 December 2.34 2.34 1.86x10-7 4.64 January 1.46 1.46 1.16x10-7 2.89 February 1.37 1.37 1.16x10-7 2.90 March 1.30 1.30 1.03x10-7 2.58 April 1.65 1.65 1.36x10-7 3.39 May 1.78 1.78 1.41x10-7 3.53 June 1.74 1.74 1.42x10-7 3.56 TOTAL
('15-'16) 18.44 18.44 1.24x10-1<2>
3.10'2>
(1) Routine gamma spectroscopy analysis of the gaseous radioactivity in the OSTR stack discharge indicated the only detectable radionu-clide was argon-41.
(2) Annual Average.
15-16 Annual Report
-itaaration-P-roie_~j-~_!1
::::-~ -
TableV.5 Annual Summary of Solid Waste Generated and Transferred Volume of Detectable Total C2.!iantity Dates ofWaste Pickup Origin of Solid Waste Radionuclides of Radioactivity for Transfer to the OSU Solid Waste Packaged<1J in the Waste in Solid Waste Waste Processing (Cubic Feet)
(Curies)
Facility Co-60, Zn-65, Sc-46, Cr-51, Fe-59, 10/12/15 TRI GA Reactor 29.5 Co-58, As-7 4, Mn-54, Sb-124, 1.lxlQ-2 3/16/16 Facility Eu-154, Se-75, Hf-181, Hg-203, Pa-233,Sr-85,In-192 5/27/16 Radiation Pu-239, Am-243, Sr-85, Eu-152, 3/16/16 Center 22 1.6x10-5 Laboratories Eu-154, U-238, U-233, U-235 5/27/16 TOTAL 51.5 See Above 1.lxl0-2 (1) OSTR and Radiation Center laboratory waste is picked up by OSU Radiation Safety for transfer to its waste processing facility for final packaging.
15-16 Annual Report
- 1* * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *
~-----
:--=-~---=-----:..
RadiatiorrProtectioa_-_-
TableV.6 Annual Summary of Personnel Radiation Doses Received Average Annual Greatest Individual Dose<!)
Dose<1J Personnel Group Whole Body Extremities Whole Body Extremities (mrem)
(mrem)
(mrem)
(mrem)
Facility Operating 121 309 229 1,364 Personnel Key Facility Research 12 7
18 61 Personnel Facilities Services Maintenance
<1 N/A
<1 N/A Personnel Laboratory Class 2
30 66 622 Students Campus Police and
<1 N/A 13 N/A Security Personnel Visitors 1
N/A 12 N/A (1) "NIN.' indicates that there was no extremity monitoring conducted or required for the group.
15-16 Annual Report Total Person-mrem for the Group<1J Whole Body Extremities (mrem)
(mrem) 845 2,468 18 61
<1 N/A 686 137 13 N/A 173 N/A
~iatiou-P1~otection Table V.7 Total Dose Equivalent Recorded on Area Dosimeters Located Within the TRIGA Reactor Facility TRI GA Reactor Total Dose Equivalent<1J<2l Monitor Recorded I.D.
Facility Location XB(y)
Neutron (See Figure V.1)
(mrem)
(mrem)
MRCTNE D104:
North Badge East Wall 294 ND MRCTSE D104:
South Badge East Wall 150 ND MR CT SW D104:
South Badge West Wall 530 ND MRCTNW D104:
North Badge West Wall 333 ND MRCTWN D104:
West Badge North Wall 562 ND MRCTEN D104:
East Badge North Wall 352 ND MRCTES D104:
East Badge South Wall 1,501 ND MRCTWS D104:
West Badge South Wall 445 ND MRCTTOP D104:
Reactor Top Badge 1,168 ND MRCTHXS D104A: South Badge HX Room 652 ND MRCTHXW D104A: West Badge HX Room 246 ND MRCD-302 D302:
Reactor Control Room 457 ND MRCD-302A D302A: Reactor Supervisor's Office 142 NIA MRCBP1 D104: Beam Port Number 1 529 ND MRCBP2 D104: Beam Port Number 2 267 ND MRCBP3 D104: Beam Port Number 3 913 ND MRCBP4 D104: Beam Port Number 4 898 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 less than the vendor's threshold of 10 mrem. "NI A indicates that there was no neutron monitor at that location.
(2) These dose equivalent values do not represent radiation exposure through an exterior wall directly into an unrestricted area.
15-16 Annual Report
- --------~-~~--~-~
Radiation Protection-Monitor I.D.
MRCAlOO MRCBRF MRCA120 MRCA120A MRCA126 MRCC0-60 MRCA130 MRCA132 MRCA138 MRCA146 MRCBlOO MRCB114 MRCB119-1 MRCB119-2 MRCB119A MRCB120 MRCB122-2 MRCB122-3 MRCB124-1 MRCB124-2 MRCB124-6 MRCB128 MRCB136 MRCClOO TableV.8 Total Dose Equivalent Recorded on Area Dosimeters Located Within the Radiation Center Total Recorded Radiation Center Dose Equivalent(!)
Facility Location xg(y)
Neutron (See Figure V.1)
(mrem)
(mrem)
AlOO:
Receptionist's Office 10 NIA A102H: Front Personnel Dosimetry Storage Rack 48 NIA A120:
Stock Room 53 NIA A120A: NAA Temporary Storage 135 NIA A126:
Radioisotope Research Laboratory 358 NIA A128:
6°Co Irradiator Room 1,397 NIA A130:
Shielded Exposure Room 65 NIA A132:
TLD Equipment Room 63 NIA A138:
Health Physics Laboratory 47 NIA A146:
Gamma Analyzer Room (Storage Cave) 147 NIA BlOO:
Gamma Analyzer Room (Storage Cave) 167 NIA B114:
Lab (226Ra Storage Facility) 1,513 NIA B119:
Source Storage Room 61 NIA Bl19:
Source Storage Room 160 NIA Bl19A: Sealed Source Storage Room 4,270 811 B120:
Instrument Calibration Facility 228 NIA B122:
Radioisotope Hood 292 NIA B122:
Radioisotope Research Laboratory 104 NIA B124:
Radioisotope Research Laboratory (Hood) 126 NIA B124:
Radioisotope Research Laboratory 52 NIA B124:
Radioisotope Research Laboratory 52 NIA B128:
Instrument Repair Shop 51 NIA B136 Gamma Analyzer Room 24 NIA ClOO:
Radiation Center Director's Office 41 NIA (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 10 mrem or that each of the fast neutron dosimeters was less than the vendor's threshold of 10 mrem. "N/ A
indicates that there was no neutron monitor at that location.
15-16 Annual Report
~*-
~iation--P1~ote~ti~11 Monitor I.D.
MRCC106A MRCC106B MRCC106-H MRCC118 MRCC120 MRCF100 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<1l Facility Location (See Figure V.1)
XB(y)
Neutron (mrem)
(mrem)
C106A: Office 42 NIA C106B: Custodian Supply Storage 0
NIA C106H: East Loading Dock 40 NIA C118:
Radiochemistry Laboratory 10 NIA Cl20:
Student Counting Laboratory 26 NIA FlOO:
APEX Facility 12 NIA F102:
APEX Control Room 21 NIA B125:
Gamma Analyzer Room (Storage Cave) 65 NIA B125:
Gamma Analyzer Room 42 NIA C124:
Classroom 44 NIA C130:
Radioisotope Laboratory (Hood) 30 NIA DlOO:
Reactor Support Laboratory 40 NIA D102:
Pneumatic Transfer Terminal Laboratory 227 ND D102H: 1st Floor Corridor at D102 115 ND D106H: 1st Floor Corridor at D106 363 NIA D200:
Reactor Administrator's Office 191 ND D202:
Senior Health Physicist's Office 273 ND D200H: Rear Personnel Dosimetry Storage Rack 60 NIA D204:
Health Physicist Office 314 ND F104:
ATHRL 11 NIA D300:
3rd Floor Conference Room 186 ND A144:
Radioisotope Research Laboratory 36 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 10 mrem or that each of the fast neutron dosimeters was less than the vendor's threshold of 10 mrem. "NI R' indicates that there was no neutron monitor at that location.
15-16 Annual Report
- * * * * * * * * * * * * * * * * * * * * * *.,.I * * * * * * * * * * * * * * * * *
-.--------~
Radiation Protection TableV.9 Annual Summary of Radiation and Contamination Levels Observed Within the Reactor Facility and Radiation Center During Routine Radiation Surveys Accessible Location (See Figure V.l)
TRIGA Reactor Facility:
ReactorTop (D104)
Reactor 2nd Deck Area (D104)
Reactor Bay SW (D104)
Reactor Bay NW (D104)
Reactor Bay NE (D104)
Reactor Bay SE (D104)
Class Experiments (D104, D302)
DemineralizerTank &Make Up Water System (D104A)
Particulate Filter--Outside Shielding (D104A)
Radiation Center:
NAA Counting Rooms (A146, BlOO)
Health Physics Laboratory (A138) 6()Co Irradiator Room and Calibration Rooms (A128, B120, A130)
Radiation Research Labs (A126, A136)
(B108, B114, B122, B124, C126, C130, A144)
Radioactive Source Storage (Bl19, B119A, A120A, A132A)
Student Chemistry Laboratory (C118)
Student Counting Laboratory (C120)
Operations Counting Room (B136, B125)
Pneumatic Transfer Laboratory (D102)
RX support Room (DlOO)
Whole Body Radiation Levels (mrem/hr)
Average I Maximum 1.5 90 5.6 40
<1 42
<1 5
<1 28
<1 22.2
<1
<1
<1 9
<1 3.4
<1 1.4
<1
<1
<1 12
<1 6
<1 8
<1
<1
<1
<1
<1
<1
<1 2
<1 1.12 Contamination Levels<!)
(dpm/cm2)
Average I Maximum
<500 2,885
<500
<500
<500 1,607
<500 6,964
<500 7,500
<500 2,292
<500
<500
<500
<500
<500 1,250
<500
<500
<500
<500
<500
<500
<500
<500
<500
<500
<500
<500
<500
<500
<500
<500
<500
<500
<500
<500 (1)
<500 dpm/100 cm2 = Less than the lower limit of detection for the portable survey instrument used.
15-16 Annual Report
Radiation-Protection Table V.10 Total Dose Equivalent at the TRIGA Reactor Facility Fence Fence Total Recorded Dose Equivalent Environmental Monitoring Station (Including Background)
Based on Mirion TLDso.2>
(See Figure V 1)
(mrem)
MRCFE-1 83 +/- 8 MRCFE-2 86 +/- 6 MRCFE-3 80 +/- 6 MRCFE-4 85 +/- 3 MRCFE-5 91+/-4 MRCFE-6 84 +/- 5 MRCFE-7 87 +/- 5 MRCFE-8 87 +/- 4 MRCFE-9 85 +/- 5 (1) Average Corvallis area natural background using Mirion TLDs totals 81 +/- 11 mrem for the same period.
(2)
+/- values represent the standard deviation of the total value at the 95% confidence level.
15-16 Annual Report
c-=-~ -
-Radiation P1*otectioll.
Table V.11 Total Dose Equivalent at the Off-Site Gamma Radiation Monitoring Stations Off-Site Radiation Total Recorded Dose Equivalent Monitoring Station (Including Background)
Based on Mirion TLDs<1*2J (See Figure V.1)
(mrem)
MRCTE-2 87 +/- 6 MRCTE-3 87 +/- 6 MRCTE-4 85 +/- 6 MRCTE-5 92 +/- 6 MRCTE-6 87 +/- 7 MRCTE-7 87 +/- 4 MRCTE-8 103+/-9 MRCTE-9*
92 +/- 6 MRCTE-10 78 +/- 6 MRCTE-12 96 +/- 6 MRCTE-13 85 +/- 6 MRCTE-14 87 +/- 4 MRCTE-15 84 +/- 7 MRCTE-16 90 +/- 5 MRCTE-17 82 +/- 5 MRCTE-18 87 +/- 6*
MRCTE-19 85 +/- 5 MRCTE-20 82 +/- 5 MRCTE-21 76 +/- 6 MRCTE-22 80 +/- 5.
(1) Average Corvallis area natural background using Mirion TLDs totals 81 +/- 11 mrem for the sa~e period.
(2)
+/- values represent the standard deviation of the total value at the 95% confidence level.
15-16 Annual Report
Raaiation-P-r.-otection *
---:;":=::...::::-:-..- ---~-*-- --- -~* ---~~..:...,_
..... ~* ~__:=. -=*.::_ ~==- ~ =~.:==:::~
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 Type Of the Total Net Beta (Minus 3H)
Reporting Radioactivity<1>
Units Water NIA
µCi ml-1 Water NIA
µCi mI-1 Water 7.43x10-sc2>
µCi ml-1 Water NIA
µCi m1-1 Soil
- 1. 92x10~5 c 2>
µCi g-1 of dry soil Soil 1.64x10-s c2>
µCi g-1 of dry soil Soil 1.59x10-sc2>
µCi g-1 of dry soil Soil 1.49x10-S c2>
µCi g-1 of dry soil Grass 4.79x10-5 +/- 7.48x10-6
µCi g-1 of dry ash Grass 2.60x10-5 +/- 8.54x10-6
µCi g-1 of dry ash Grass 2.60x10-5 +/- 6. 93x10-6
µCi g-1 of dry ash Grass 4.24xio-5 +/- 1.07x10-s
µCi g-1 of dry ash Grass 1.69x10-S c2>
µCi g-1 of dry ash Grass 1.96~10-5 +/- 7.82x10-6
µCi g-1 of dry ash Grass 5.66x10-5 +/- 1.25x10-s
µCi g-1 of dry ash Grass 1.83x10-s c 2>
µCi g-1 of dry ash Grass 4.07xio-5 +/- 8.91x10-6
µCi g-1 of dry ash Grass 1.99x10-S c2>
µCi g-1 of dry ash Grass 2.23x10-s c2>
µCi g-1 of dry ash Grass 2.23xio-5 +/- 9.82x10-6
µCi g-1 of dry ash Grass 2.03x10-5 <2>
µCi g-1 of dry ash*
Grass 2.39x10-s c2>
µCi g-1 of dry ash (1)
- t: values represent the standard deviation of the value at the 95% confidence level.
(2) Less than lower limit of detection value shown.
15-16 Annual Report
..-c:::-:- ------------ --
~
_______ __:::s_
- -. --Radiation-Protection
- - *-----~--------- -- _:_ _____ ----* -----* -----~-~*::::=
TableV.13 Beta-Gamma Concentration and Range of LLD Values for Soil, Water, and Vegetation Samples Sample Average Type Value Range of Values Reporting Units Soil 1.66x10-s <iJ 1.49x10-S to 1.92x10-s <iJ
µCi g-1 of dry soil Water 7.43x1Q-8 <iJ 7.43x10-8 (IJ
µCi mI-1 Vegetation 3.52x10-S 1.96x10-s to 5.66x10-S
µCi g-1 of dry ash (1) Less than lower limit of detection value shown.
15-16 Annual Report
~~~~~~~~~~~~~~~~~~~~~~.-
~~~o_nc!'~~~~~s
. ~ =::-~=,,_~=- ** *-:--*-:~-"
~_--.~*~*= ~~~l TableV.14 Annual Summary of Radioactive Material Shipments Originating From the TRIGA Reactor Facility's NRC License R-106 Number of Shipments Total Activity Limited Yellow II Yellow III Total Shipped To (TBq)
Exempt Q!iantity Arizona Radiation Regulatory Agency 2.16x10-3 0
0 1
0 1
Phoenix, AZ USA Arizona State University 1.19x10-6 1
0 1
0 2
Tucson,AZ USA Berkeley Geochronology Center 8.8lx10-7 9
1 0
0 10 Berkelev, CA USA Lawrence Livermore National Lab 1.34x10-7 1
0 0
0 1
Livermore, CA USA Materion Corporation 3.79x10-2 0
0 0
4 4
Elmore, OH USA Materion Natural Resources 1.0lxl0-1 0
0 0
21 21 Delta, UT USA Nevada Radiation Control Program 2.65x10-3 0
0 1
0 1
Carson Citv, NV Occidental College 6.76x10-9 1
0 0
0 1
Los An!!"eles, CA USA Oregon State University 4.73x10-6 3
2 2
0 7
Corvallis, OR USA Plattsburgh State University 1.35x10-s 1
0 0
0 1
Plattsburgh, NY USA Syracuse University 7.70x10-9 2
0 0
0 2
Syracuse, NY' USA University of Arizona
- 2.17x10-6 3
0 1
0 4
Tucson, AZ USA University of Cincinnati 4.73x10-9 4
0 0
0 4
Cincinnati, OH USA University of Vermont 1.70x1Q-8 1
0 0
0 1
Burlirnrton, VT USA University ofWisconsin-Madison 4.93x10-6 5
1 1
0 7
Madison, WI USA US Army 102CST 2.14x10-3 0
0 1
0 1
Salem, OR USA Wyoming Homeland Security 2.33x10-3 0
0 1
0 1
Chevenne, WY USA Totals 1.48x10-1 31 4
9 25 69 15-16 Annual Report
---=~~ ----- --- - -----
-- -*---~ * * -
R-~i,-Cliation-P1*otection __________ _
~--------------
~------~----
TableV.15 Annual Summary of Radioactive Material Shipments Originating From the Radiation Center's State of Oregon License ORE 90005 Total Activity Number of Shipments Shipped To Limited (TBq)
Exempt White I Yellow II Qiantity Argonne National lab 1.lOxl0-7 0
1 0
0 Argonne, IL USA Lawrence Livermore National Lab 1.42x10-10 1
0 0
0 Livermore, CA USA Los Alamos National Lab 2.75x10-6 3
3 2
0 Los Alamos, NM USA Totals 2.86xl0-6 4
4 2
0 TableV.16 Annual Summary of Radioactive Material Shipments Exported Under NRC General License 10 CFR 110.23 Number of Shipments Shipped To Total Activity Exempt Limited Yellow II (TBq) 01iantity Australian National University 5.20x10-12 1
0 0
Canberra, AUSTRALIA China University of Petroleum 9.95x10-3 1
0 0
Beijing, CHINA Curtin University ofTechnology 1.16x1Q*5 0
0 2
Bently Western Australia AUSTRALIA Dalhousie University 1.35xrn-s 2
0 0
Halifax, Nova Scotia CANADA Geological Survey of japan 1.07x10-7 2
0 0
Ibaraki,JAPAN Geomar Helmholtz Center for Ocean Research 5.67x10-s 1
0 0
Kiel, GERMANY Glasgow University 5.63x10-9 1
0 0
Glasgow SCOTLAND Korean Baskic Science Institute 6.18x10-8 3
0 0
Cheongju-si, Chungcheongbuk-do KOREA Lanzhou Center of Oil and Gas Resources 1.13x10-s 2
0 0
Lanzhou, CHINA Lanzhou University 3.33x10-8 2
0 0
Lanzhou, Gansu CHINA 15-16 Annual Report Total 1
1 8
10 Total 1
1 2
2 2
1 1
3 2
2
Railiation-F~otection
---~----:~--~--
Table V.16 (continued)
Annual Summary of Radioactive Material Shipments Exported Under NRC General License 10 CFR 110.23 Number of Shipments Total Activity Limited Yellow II Shipped To (TBq)
Exempt Qyantity Lund University 1.35x10-7 1
0 0
Lund, SWEDEN Polish Academy of Sciences 2.85xrn-s 2
0 0
Krakow, POLAND QUAD-Lab, Roskilde University 3.26x10-9 2
0 0
Roskilde DEMARK Scottish Universities Research & Reactor Centre 2.61xl0-6 7
2 0
East Kilbride, SCOTLAND Universidade de Sao Paulo 6.9ixrn-s 2
0 0
San Paulo, BRAZIL Universitat Potsdam 3.36xrn-s 2
0 0
Postdam, GERMANY Universite Paris-Sud 1.51xl0-6 0
0 1
Paris, FRANCE University of Geneva 2.27x10-7 6
0 0
Geneva, SWITZERLAND University of Manitoba 4.81xl0-6 0
3 0
Winnipeg, CANADA University of Melbourne 1.60x1Q-6 2
2 0
Parkville, Victoria AUSTRALIA University ofMilano-Bicocca 4.0lxl0-9 1
0 0
Milano ITALY University of Padova 2.83xrn-s 4
0 0
Padova, ITALY University of Qyeensland 1.32xl0-6 0
3 0
Brisbane, Qyeensland AUSTRALIA University of Rennes 3.04xrn-s 2
0 0
Rennes, FRANCE University ofWaikato 1.34xrn-s 1
0 0
Hamilton, NEW ZEALAND University of Zurich 4.59x10-9 1
0 0
Zurich, SWITZERLAND Victoria University of Wellington 6.56x10-s 1
0 0
Wellington, NEW ZELAND Vrijc Universiteit 9.99x1Q-7 2
1 0
Amsterdam, THE NETHERLANDS Totals 9.98x10-3 51 11 3
-o-:-- -~-------*
Total 1
2 2
9 2
2 1
6 3
4 1
4 3
2 1
1 1
3 65 15-16 Annual Report *
- Radiation Protection Figure V.1 Monitoring Stations for the OSU TRIGA Reactor n
C4IDC4 Ult IUJIOI(
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' 11' WA'ID SW LUICW.l'TU 15-16 Annual Report llOn: U UIS LOCUm I MIUS llOVt1l OFTD MZIUDJl(Clllt'D.U
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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 III.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. l 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 pro-vides a listing of the research and service projects carried out during this reporting period and lists information relating to the personnel and institution involved, the type of project, and the funding agency. Projects which used the reactor are indi-cated by an asterisk. In addition to identifying specific projects carried out during the current reporting period, Part VI also highlights major Radiation Center capabilities in research and service. These unique Center functions are described in the fol-lowing text.
Neutron Activation Analysis Neutron activation analysis (NAA) stands at the forefront of techniques for the quantitative multi-element analysis of major, minor, trace, and rare elements. The principle involved in NAA consists of first irradiating a sample with neutrons in a nuclear reactor such as the OSTR to produce specific radionuclides. Af-ter the irradiation, the characteristic gamma rays emitted by the decaying radionuclides are quantitatively measured by suitable semiconductor radiation detectors, and the gamma rays detected at a particular energy are usually indicative of a specific radionu-clide's presence. Computerized data reduction of the gamma ray spectra then yields the concentrations of the various elements in samples being studied. With sequential instrumental NAA it is possible to measure quantitatively about 35 elements in small samples (5 to 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.
15-16 Annual Report
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 facilities. 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 sessions 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 Emergency Response Plan, Physical Security Plan, and op-erator requalification program, the Radiation Center is also used for special training programs. Radiation Center staff are well experienced in conducting these special programs and regularly offer training in areas such as research reactor 15-16 Annual Report Work operations, research reactor management, research reactor radiation protection, radiological emergency response, reactor behavior (for nuclear power plant operators), neutron activa-tion 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 train-ing 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 Radiological 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 radioactive materials, calibration and repair of radiation monitoring instruments (discussed in detail in Part VI), radioactive waste disposal, radioactive material hood fl.ow surveys, and radia-tion safety analysis and audits.
The Radiation Center also provides services and techni-cal support as a radiation laboratory to the State of Oregon Radiation Protection Services (RPS) in the event of a radio-logical emergency within the state of Oregon. In this role, the Radiation Center will provide gamma ray spectrometric analysis of water, soil, milk, food products, vegetation, and air samples collected by RPS radiological response field teams.
As part of the ongoing preparation for this emergency sup-port, the Radiation Center participates in inter-institution drills.
Work Radiological Instrument Repair and Calibration While repair of nuclear instrumentation is a practical neces-sity, routine calibration of these instruments is a licensing and regulatory requirement which must be met. As a result, the Radiation Center operates a radiation instrument repair and calibration facility which can accommodate a wide vari-ety of equipment.
The Center's scientific instrument repair facility performs maintenance and repair on all types of radiation detectors and other nuclear instrumentation. Since the Radiation 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 radia-tion accident situations can also be calibrated in most cases.
Instrument calibrations are performed using radiation sources certified by the National Institute of Standards and Technol-ogy (NIST) or traceable to NIST Table VI.3 is a summary of the instruments which were calibrated in support of the Radiation Center's instructional and research programs and the OSTR Emergency Plan, while Table VI.4 shows instruments calibrated for other OSU de-partments and non-OSU agencies.
Consultation Radiation Center staff are available to provide consultation services in any of the areas discussed in this Annual Report, but in particular on the subjects of research reactor operations and use, radiation protection, neutron activation analysis, radia-tion 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.
15-16 Annual Report
Table Vl.1 Institutions, Agencies and Groups Which Utilized the Radiation Center Number of Number ofTimes of Intuitions, Agencies and Groups Projects Faculty Involvement
- Arizona State University 1
1 Tempe, AZ USA
0
- Berkeley Geochronology Center 1
0 Berkeley, CA USA Branch Engineering 1
0 Springfield, OR USA Chemical Bilogical &Environmental Engineering 1
- Chinga University of Petroleum - Beijing 1
1 Changping, Beijing CHINA Crystal Solutions, LLC 1
1 Portland, 0 R USA
- CSTA, USARNORTH 1
0 Fort Sam Houston, TX USA
- Dalhousie University 1
2 Halifax, Novia Scotia CANADA
- Geological Survey ofJapan/AIST 1
0 Tsukuba, Ibaraki, JAPAN
- Geologisch-Palaontologisches Institut.
1 1
Basel, SWITZERLAND
- Helmoholtz-Zentrum fur Ozeanforschung Kiel (GEOMAR) 1 0
Kiel, GERMANY
- Korea Basic Science Institute 1
1 Cheongwon-gun, Chungcheongbuk-do SOUTH KOREA
- Lanzhou Center of Oil and Gas Resources, CAS 1
1 Lanzhou, CHINA
- Lanzhou University 1
0 Lanzhou, CHINA
- Lawrence Livermore National Laboratory 1
0 Livermore, CA USA
- Lund University 1
0 Lund, SWEDEN
- Mas Oro 1
0 Sahuarita, AZ USA
- Materion Brush, Inc.
1 0
Elmore, OH USA
- Materion Natural Resources 1
0 Delta, UT USA N euraMedica 1
0 Beavercreek, OR USA 15-16 Annual Report A
Number of Uses of Center l~\\wilitif's 3
1 9
1 17 2
2 4
2 1
2 1
4 2
2 1
1 2
4 14 1
Table Vl.1 (continued)
Institutions, Agencies and Groups Which Utilized the Radiation Center Number of Number ofTimes of Intuitions, Agencies and Groups Projects Faculty Involvement
- Occidental College 1
1 Los Angeles, CA USA
- Oregon State University - Educational Tours 1
- Oregon State University Radiation Center 1
1 Corvallis, 0 R USA
- Plattsburgh State University 1
1 Plattsburgh, NY USA
- Polish Academy of Sciences 1
0 Krakow, POLAND
- OJiaternary Dating Laboratory 1
0 Roskilde, DENMARK
- Scottish Universities Enfi.ronmental Research Centre 1
0 East Kilbride UK
- Syracuse University 2
2 Syracuse, NY USA
- The University of Waikato 1
1 Hamilton, NEW ZEALAND
- Universita' Degli Studi di Padova 1
2 Padova ITALIA
- Universitat Potsdam 1
0 Potsdam, GERMANY Universite Paris-Sud 1
1 Paris, FRANCE
- Universite Rennes 1 1
1 Renn es FRANCE
- University at Albany, SUNY 1
2 Albany, NY USA
- University of Arizona 3
3 Tucson,AZ USA
- University of California at Santa Barbara 1
1 Santa Barbara, CA USA
- University of Cincinnati 1
1 Cincinnati, 0 H USA
- University of Geneva 1
1 Geneva SWITZERLAND
- University of Glasgow 1
0 Glasgow SCOTLAND Numberot Uses of Center Fa,-ilitiP.:
1 74 (l) 17 14 1
2 3
27 2
2 4
1 1
1 6
7 1
3 7
1
- ---~--- ~~~~--*
15-16 Annual Report * *
~----
- - -~--------
Table Vl.1 (continued)
Institutions, Agencies and Groups Which Utilized the Radiation Center Number of Number ofTimes of Intuitions, Agencies and Groups Projects Faculty Involvement
- University of Manitoba 1
1 Winnipeg, Manitoba CANADA
- University of Melbourne 1
1 Melbourne, Victoria AUSTRALIA
- University of Michigan 1
4 Ann Arbor, MI USA
- University of Oregon 3
- University of Postdam 1
0 Post dam GERMANY
- University of Qieensland 1
1 Brisbane, Qieensland AUSTRALIA
- University of Sao Paulo 2
1 Sao Paulo BRAZIL
- University of Vermont 1
- University of Wisconsin 1
1 Madison, WI USA US National Parks Service 1
0 Crater Lake, OR USA USDA Forest Service 1
- Victoria University of Wellington 1
0 Wellington, NEW ZEALAND
- Vrije Universiteit 1
1 Amsterdam THE NETHERLANDS
- Western Australian Argon Isotope Facility 1
0 Perth, Western Australia AUSTRALIA Totals 80 101 Pro1ect which mvolves the OSTR.
Number of Uses of Center F<irilitiP~
3 5
1 26 1
3 2
1 7
3 7
2 3
6 321 (1)
Use by Oregon State University does not include any teaching activities or classes accommodated by the Radiation Center.
(2)
This number does not include 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 facilities.
15-16 Annual Report
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Project Users 444 Duncan 815 Morrell 920 Becker 1074 Wijbrans 1191 Vasconcelos 1353 Kamp 1366 Qyidelleur 1404 Riera-Lizarau 1419 Krane 1465 Singer 1503 Teaching and Tours Teaching and 1504 Tours Teaching and 1505 Tours Listing of Major Research and Service Projects Preformed or in Progress
- ~1*
at the Radiation Center and Their Funding Agencies Organization Name Project Title Oregon State Ar-40/ Ar-39 Dating of Oceanographic University Samples Oregon State Sterilization of Wood Samples University Berkeley Ar-39/Ar-40 Age Dating Geochronology Center Vrije Universiteit Ar/ Ar Dating of Rocks and Minerals University of Ar-39/Ar-40 Age Dating Qyeensland The University of Fission Track Thermochronology of New Waikato Zealand Universite Paris-Sud Ar-Ar Geochronology Oregon State Evaluation of wheat DNA University Oregon State Nuclear Structure ofN=90 Isotones University University of Ar-40/Ar-39 Dating ofYoung Geologic Wisconsin Materials Non-Educational Non-Educational Tours Tours Oregon State OSU Nuclear Engineering & Radiation University-Health Physics Department Educational Tours Oregon State University-OSU Chemistry Department Educational Tours Description Production of Ar-39 from K-39 to measure radiometric ages on basaltic rocks from ocean basins.
Sterilization of wood samples to 2.5 Mrads in Co-60 irradiator for fungal evaluations.
Production of Ar-39 from K-39 to determine ages in various anthropologic and geologic materials.
Ar/ Ar dating of rocks and minerals.
Production of Ar-39 from K-39 to determine ages in various anthropologic and geologic materials.
Determination of history and timing of denudation of basement terranes in New Zealand and thermal history oflate Cretaceous-Cenozoic sedimentary basins.
Determination of geological samples via Ar-Ar radiometric dating.
Gamma irradiation of wheat seeds.
Study ofN=90 isotone structure (Sm-152, Gd-154, Dy-156) from decays ofEu-152, Eu-152m, Eu-154, Tb-154, and Ho-156. Samples will be counted at LBNL.
Irradiation of geological materials such as volcanic rocks from sea :floor, etc. for Ar-40/ Ar-3 9 dating.
Tours for guests, university functions, student recruitment.
OSTR tour and reactor lab.
OSTR tour, teaching labs, and/or half-life experiment.
Funding OSU Oceanography Department OSU Forest Products Berkeley Geochronology Center Vrije Universiteit, Amsterdam Earth Sciences, University of Qyeensland University of Waikato Universite Paris-Sud OSU Crop and Soil Science OSUPhysics Department University of Wisconsin NA NA NA I r
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Project Users Teaching and 1506 Tours Teaching and 1507 Tours Teaching and 1509 Tours Teaching and 1510 Tours Teaching and 1511 Tours 1512 Teaching and Tours 1514 Sobel 1523 Zattin Teaching and 1542 Tours 1544 Teaching and Tours Teaching and 1545 Tours 1555 Fitzgerald 1568 Spell Table Vl.2 (continued)
Listing of Major Research and Service Projects Preformed or in Progress at the Radiation Center and Their Funding Agencies Organization Name Project Title Description Oregon State University-OSU Geosciences Department OSTR tour.
Educational Tours Oregon State University-OSU Physics Department OSTR tour.
Educational Tours Oregon State University-HAZMAT course tours First responder training tours.
Educational Tours Oregon State Science and Mathematics Investigative University -
OSTR tour and half-life experiment.
Educational Tours Learning Experience Oregon State Reactor operation required for conduct of University -
Reactor Staff Use operations testing, operator training, calibration Educational Tours runs, encapsulation tests and other.
Linn Benton Linn Benton Community College OSTR tour and half-life experiment.
Community College Tours/Experiments Universitat Potsdam Apatite Fission Track Analysis Age determination of apatites by fission track analysis.
Universita'Degli Studi Fission track analysis of Apatites Fission track dating method on apatites by fission di Padova track analysis.
Oregon State University-Engineering Sciences Classes OSTR tour.
Educational Tours West Albany High West Albany High School OSTR tour and half-life experiment.
School Oregon State University -
OSU Educational Tours OSTR tour.
Educational Tours Irradiation to induce U-235 fission for fission track thermal history dating, especially for hydrocarbon Syracuse University Fission track thermochronology exploration. The main thrust is towards tectonics, in particular the uplift and formation of mountain ranges.
University of Nevada Ar/ Ar geochronology and Fission Track Argon dating of Chilean granites.
Las Vegas dating Funding NA NA NA NA NA NA Universitat Potsdam NA NA NA NA Syracuse University University of Nevada Las Vegas
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Project 1611 1614 1617 1623 1660 1674 1677 1717 1720 1745 1767 1768 1777 1778 1816 Users Teaching and Tours Teaching and Tours Spikings Blythe Reactor Operations Staff Niles Zuffa Baldwin Teaching and Tours Girdner Korlipara Bringman Storey Gislason Kounov Table Vl.2 (continued)
Listing of Major Research and Service Projects Preformed or in Progress at the Radiation Center and Their Funding Agencies Organization Name Project Title Description Grants Pass High Grants Pass High School OSTR tour.
School Marist High School Marist High School OSTR tour and half-life experiment.
University of Geneva Ar-Ar geochronology and Fission Track Argon dating of Chilean granites.
dating Occidental College Fission Track Analysis Fission track Thermochronology of geological samples Oregon State Operations support of the reactor and Operations use of the reactor in support of reactor University facilities testing and facilities testing.
Radiological emergency support ot OOE related Oregon Department of to instrument calibration, radiological and Radiological Emergency Support RAM transport consulting, and maintenance of Energy radiological analysis laboratory at the Radiation Center.
Universita' di Bologna Fission Track Dating Use of fission track from U-235 to determine uranium content in rock.
Syracuse University Ar/ Ar Dating Ar/ Ar Dating.
Saturday Academy OSTRTour OSTRTour.
US National Parks C14 Measurements LSC analysis of samples for C14 measurements.
Service Terra Nova Nurseries, Genera Modifications using gamma Use of gamma and fast neutron irradiations for Inc.
irradiation genetic studies in genera.
Brush-Wellman Antimony Source Production Production of Sb-124 sources.
Qpaternary Dating Qpaternary Dating Production of Ar-39 from K-39 to determine Laboratory radiometric ages of geological materials.
This project subjects chitosan polymer in 40 and 70% DDA formulations to 9 and 18 Kgy, Genis, Inc Gamma exposure of Chitosan polymer boundary doses for commerical sterilization for the purpose of determine changes in the molecular weight and product formulation properites.
Geologisch-Palaontologisches Fission Track Analysis Geochronology analysis using fission track dating.
Institut Funding NA NA University of Geneva Occidental College NA Oregon Department of Energy Universita' di Bologna Syracuse University NA US National Parks Service Terra Nova Nurseries, Inc.
Brush-Wellman Qpaternary Dating Laboratory Genis, Inc.
Geologisch-Palaontol-ogisches Instut
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Project 1818 1819 1820 1823 1826 1831 1840 1841 1852 1855 1861 1864 1865 1878 1883 1886 1887 Users Sabey Vetter Jolivet Harper Teaching and Tours Thomson Burgess Swindle McGuire Anczkiewicz Page Gans Carra pa Roden-Tice Wright Coutand Farsoni Table Vl.2 (continued)
Listing of Major Research and Service Projects Preformed or in Progress at the Radiation Center and Their Funding Agencies Organization Name Project Title Description Brush Wellman Antimony source production (Utah)
University of NE-104A INAA source Stainless Steel disk source for INAA lab.
California at Berkeley Universite Montpellier Fission Track Analysis Use of fission track analysis for geochronology.
II Oregon State Evaluation of Au nanoparticle uptake INAA of gold concentrations in zebrafish embryos University to evaluate nanoparticle uptake.
North Eugene High OSTRTour OSTR Tour and half-life experiment.
School Fission track thermochronometry of the University of Arizona Fission Track Patagonian Andes and the Northern Apennines, Italy.
University of Ar/ Ar Dating Production of Ar-39 from K-39 for Ar-40/Ar-39 Manchester dating of geological samples.
University of Arizona Ari Ar dating of ordinary chondritic Ar/ Ar dating of ordinary chondritic meterorites.
meterori tes Antimicrobial activity of silanized silica co-polymer and nisin association.
The project Oregon State microspheres with covalently attached is aimed at finding effective methods for coating University PEO-PPO-PEO surfaces to enhance protein repellant activity and antimicrobial activity using nisin.
Polish Academy of Fission Track Services Verification of AFT data for illite-mechte data.
Sciences Lund University Lund University Geochronology Ar/ Ar Geochronology.
University of Production of Ar-39 from K-40 to determine California at Santa Ar-40/Ar-39 Sample Dating radiometric ages of geologic samples.
Barbara Apatite fission track to reveal the exhumation University of Fission Track Irradiations history of rocks from the ID-WY-UY postion Wyoming of the Sevier fold and thrust belt, Nepal, and Argentina.
Plattsburgh State Fission-track research Use of fission tracks to detrmine location of 235U, University 2321h in natural rocks and minerals.
University of Michigan *The Uruk Expansion INAA of ceramics from Uruk-period sites in Mesopotamia and adjacent areas.
Dalhousie University Fission Track Irradiation Fission track irradiations of apatite samples.
Oregon State Xenon Gas Production Production of xenon gas.
University Funding Brush-Wellman University of California at Berkeley University of Montpellier II OSU Environmental Health Sciences Center NA Yale University University of Manchester University of Arizona Chemical,Biological &
Env Engineering Polish Academy of Sciences Lund University University of California at Santa Barbara University ofWyoming Plattsburgh State University OSU Radiation Center Dahousie University OSUNERHP
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Project 1894 1904 1905 1907 1913 1914 1916 1927 1929 1933 1939 1957 1958 1959 1965 1971 1975 Users Greene Mine Fellin Tanguay Reese Barfod Shusterman Seward Farsoni Loveland Wang Phillips Mine Mu tin Webb Shaik McDonald Table Vl.2 (continued)
Listing of Major Research and Service Projects Preformed or in Progress at the Radiation Center and Their Funding Agencies Organization Name Project Title Description University of Chicago INAA of Late Bronze-Age Ceramics, Trace-element analyses of ceramics from Armenia Tsaghkahovit, Armenia, to determine provenance.
Oregon State INAA of Archaeological Ceramics Trace-element analyses of ceramics from University from Ecuador Ecuador for provenance determination.
ETH Zurich Fission Track Analysis Use of fission tracks to determine location of 235U, 2321h in natural rocks and minerals.
Oregon State Nanoparticle Uptake in Zebrafish INAA to determine the uptake by zebrafish University Embryos embryos of various metals in nanoparticle form.
Oregon State Fission Yield Determination Using Use of neutron activation to determine fission yields for various fissile and fertile materials using University Gamma Spectroscopy gamma spectroscopy.
Scottish Universities Environmental Ari Ar Age Dating Ari Ar age dating.
Research Centre University of UC Berkeley Chemistry/NAA Introduction ofNAA by activation of human hair California at Berkeley to detect trace impurities.
Victoria University of Fission Track Dating Fission track dating of apatite samples.
Wellington Oregon State Source Activation Irradiation of different materials to make sources University for detection experiments.
Oregon State Pt radiochemistry Production of tracer for testing chemical University separation of Pt from Pb.
Lanzhou University Lanzhou University Fission Track Fission Track dating.
University of Radiometric age dating of geologic Ari Ar age dating.
Melbourne samples Oregon State INAA of Oaxaca Ceramics Trace-element analyses of prehistoric ceramics University from Oaxaca, Mexico, to determine provenance.
Benjamin Mutin Tepe Yahya INAA of archaeological ceramics from Tepe Yahya, Iran.
University of Vermont Ar/Ar age dating Irradiation with fast neutrons to produce Ar-39 from K-3 9 for Ar/ Ar geochronology.
New Earth Testing Blue Green Algae Testing of blue green algae to determine if it is contaminated with radioactive material.
University of Glasgow SamuelJaanne Use of fissin tracks to determine last heating event of apatites.
Funding University of Chicago NIA Geologisches Institut, ETH Zurich OSU Environmental and Molecular Toxicology NIA Scottish Universities Research and Reactor Centre UC Berkeley Vitoria University of Wellington NA Lanzhou University University of Melbourne NSF Collaborative Research Project NSF Collaborative Research Project University ofVermont New Earth School of Geographical and Earth Science
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Listing of Major Research and Service Projects Preformed or in Progress at the Radiation Center and Their Funding Agencies Organization Name Project Title Description Oregon State Mixed Matrix Extraction Testing Multi-element, transition metal salt production for University mixed matrix extraction testing.
Oregon State INAA of Archaeological Ceramics from Trace-element analyses of ancient ceramics and clays from Yaasuchi, Oaxaca to examine ceramic University Yaasuchi, Oaxaca technology and trade.
Field Museum INAA of Archaelogical Ceramics from Trace-element analyses of Classic-period ceramics El Palmillo, Oacaca from the site of El Palmillo, Oaxaca.
University of Michigan Kunji Cave Trace-element determination via INAA of ceramic from Kunji Cave, Iran.
University of Mamasani Trace-element analyses via INAA of Cambridge archaeological ceramics from Mamasani.
Oregon State Tell Hadidi, Syria INAA of Late Uruk ceramic containers.
University The induction of genetic mutations in hop Oregon State (Humulus lupulus L.) will be attempted using University Hop irradiation radiation treatment. Generated stable mutations may lead to new hop varieties and assist with genetic research.
University of Fission Track Dating Apatite fission track dating, study ofYukon and Cincinnati southeastern Alaska geological evolution.
INAA of samples from mineralized fault zone, University of Oregon Structure of Amargosa Chaos Virgin Spring Phase of the Amargosa Chaos, Southern Death Valley, California.
Oregon State Sedementary deposits relted to Trace-element analysis of sedimentary deposits University earthquake hazards left by 2004 Sumatra-Andaman earthquake to determine details about the earthqueake rupture.
Najing University Apatite Fission Track Apatite Fission track for Durango samples.
University of Manitoba Ar/ Ar dating Production of Ar-39 from K-39 to determine radiometric ages of geological materials.
Kinetic Force Inc Shielding Evaluation Material shielding evaluation.
This project is studying the interactions between microorganisms that inhabit fl.owback fluid Oregon State Shale and Flowback Ambient Pressure/
from hydraulic fracturing and Marcellus shale University Temperature Microcosm Incubations samples obtained from the subsurface. The shale samples are being irradiated to remove microbial contamination without altering the chemical or mineralogical composition of the shale.
Funding NSF Collaborative Research Project NSF Collaborative Research Project NSF Collaborative Research Project NSF Collaborative Research Project NSF Collaborative Research Project OSU Crop and Soil Science University of Cincinnati OSUCOAS Nanjing University University of Manitoba
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Project 2000 2001 2002 2003 2004 2005 2006 2007 2008 Users Kaspar Derrick Sosa Paul Sudo Stewart-Smith Van Tassel Wartho Pahle Table Vl.2 (continued)
Listing of Major Research and Service Projects Preformed or in Progress at the Radiation Center and Their Funding Agencies Organization Name Project Title Description Alternative Nutrition Contamination detection in Taurine Look for contamination in Taurine that was LLC shipped from Japan.
Branch Engineering Densitometer Leak Test Wip counts for leak test of densitometer sources.
Universidad de Iridium in Soil Samples Epithermal INAA to determine Ir content in soils Granada at the K-T boundary.
The membrane (polyacrylonitrile or PAN) which I am going to irradiate is used in kidney dialyzer.
At present Medical agencies use ETO to sterilize the membrane. The other technique to sterilize is by using gamma irradiation. Recently some researchers used low dosage of gamma irradiation Oregon State Effect of gamma irratiation on to cross link this membrane with other organic mass transport and mech prop of compound which makes membrane biocompatible University polyacrylonitrile copolymer membrane and repel protein to make it more effective in blood purification. So our research question is whether we can both sterilize and graft the organic compound I n the membrane at the same time?
Therefore I would be test the membrane for its mass transfer and mechanical properties for our research objective.
University of Postdam Ari Ar Geochronological Studies Ari Ar dating of natural rocks and minerals for geological studies.
Determination of radon concentration from Radon Daugheter Detection daughter products from samples collected around Oregon.
Silphium integrifolium is a native, perennial prairie plant with potential as a new source of vegetable oil. We have begun making selections The Land Institute Silphium mutagenesis using natural variation, but would also like to induce mutations in this species as a sourve new genetic variation such as dwarfing, early flowering, reduced seed dormancy, reduced seed shattering, reduced branching, etc.
Arizona State Argon-Argon Geochronology Fast neutron irradiation of mineral and rock University samples for 40 Arl39Ar dating purposes.
Kinetic Force Inc Shiled Testing Material evaluation for use in shielding different types radioactive elements.
Funding i
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& Manufacturing Engineering The Land Arizona State University Kinetic Force
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Listing of Major Research and Service Projects Preformed or in Progress at the Radiation Center and Their Funding Agencies Organization Name Project Title Description Zhejiang University Durango apatite fission track Fission track apatite irradiation.
University of Sao Ar/ Ar Geological Dating Ar/ Ar geologic dating of materials.
Paulo Oregon State INAA of Archaeological Ceramics from Trace-element analyses of ancient ceramics and clays fromJalieza, Oaxaca to examine ceramic University J alieza, Oaxaca techology and trade.
University of Debromination during Organic Matter INAA of deep sea organic samples to determing Washington Degradation in the Deep Biosphere Br content.
Rainier Farmer Decommissioning Surveys Detector use for decommissioning surveys.
Oregon State Barley Irradiation Barley irradiation to determine growth potential.
University Investigation of irradiation on biological A solution of purified fibronectin in PBS and Akron Biotech activity of human plasma-derived lyophilized powder sampe of fibronectin will be fibronectin.
irradiated and the activity tested.
Si02 surfaces were silanized (vapor deposition)
Chemical, Biological with TCVS to create double bonds on surface. The
& Environmental TCVS Silanization for EGAP coating surface is incubated in Polyethylene triblocks, once Engineering gamma irradiated it will bind the triblocks to the surface.
Wester Australian Age dating of geological material Ar/ Af geochronology.
Ar?;on Isotope Facility Oregon State Gamma Irradiation of Zebra Fish Gamma irradiation of zebra fish to induce specific University growth.
The use oflow-temperature thermochronology to Calfornia State constrain the exhumation history of the Eastern University-Bakersfield Sierra Geomorph Sierra Nevada. This data will also be used as a tracer to examine the relationship between grain size and the elevation of the sediment source area.
Carpenteria californica (Hydrangeaceae) is a shrub with large white flowers and yellow eyespots. It is prized for its large flowers but often the growth form is poor. There are few cultivars available, with 'Elizabeth' being reported as a double-Oregon State Mutagenesis of carpenteria californica flowered form but most often it is a weak semi-University using varying rates of gamma radiation double at best. Our goal is to induce mutations in Carpenteria californica to select for mutations in growth form and flowering traits. A superior selection would be one that exhibits compact growth form (shortened internodes compared to the type) and is extremely floriferous.
Funding Zhejiang University University of Sao Paulo NIA University of Washington Rainier Farmer OSU Crop and Soil Science Akron Biotech OSU Chemical Engineering Curtin University NIA Calfornia State University-Bakersfield OSU Horticulture I,
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Listing of Major Research and Service Projects Preformed or in Progress at the Radiation Center and Their Funding Agencies Organization Name Project Title Description Oregon State Neutron radiography of heater rods Use of neutron radiography to determine precise University location of the internal components of heater rods.
Cypress Grove Chevre Dill pollen irradiation Gamma irradiation of dill pollen to sterlize yeast.
Lawrence Livermore Ari Ar dating Production of neutron induced 39Ar from 39K for National Laboratory Ar/ Ar dating:.
This study involves bone marrow transplantation followed by hindlimb-unloading (a ground-based model of spaceflight). Four groups of mice will be studied: (1) weight-bearing WT mice transplanted with WT bone marrow derived hematopoietic stem cells, (2) hindlimb unloaded WT mice Oregon State Role of bone marrow adipocytes in bone transplanted with WT bone marrow derived University loss during simulated spaceflight hematopoietic stem cells, (3) weight-bearing Kitw/
w-v mice transplanted with WT bone marrow derived hematopoietic stem cells, and (4) hindlimb unloaded Kitw/w-v mice transplanted with bone marrow derived hematopoietic stem cells; the mice will be hindlimb unloaded for 14 days and sacrificed.
Oregon State INAA of Niobium Neutron activation analysis of Niobium for University characterization of impurities.
- CSTA, Source production for training purposes Source production to be used for training purposes USARNORTH for response teams.
Oregon State Neutron Radiography of Antennae Neutron radiography of radio antennae.
University Oregon State INAA of ceramics fro111 the Ancient Provenance determination of ceramics from the University
- Near East Ancient Near East via trace-element analysis.
Korea Basic Science Ar/ Ar geochronology Ar/ Ar analysis for age dating of geological Institute samples.
Northstar Glassworks, Uranium glass testing for alpha, beta, Determination of alpha, beta, gamma Inc.
gamma radiation contamination, dose and activity of uranium glass sample.
Funding OSUNERHP Lawrence Livermore National Laboratory Lawrence Livermore National Laboratory OSU Nutrition and Exercise Sciences OSU Mechanical Industrial and Manufacturing Eng:ineerin_g U.S. Army NIA OSU Anthropology Korea Basic Science Institute Northstar Glassworks, Inc.
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Project 2031 2032 2033 2034 2035 2037 2038 2039 2040 2041 2042 Users Malusa Parham Chang Morrell Wang Marcum Blakes tad Gombart Tucker Marcum Walsh Table Vl.2 (continued)
Listing of Major Research and Service Projects Preformed or in Progress at the Radiation Center and Their Funding Agencies Organization Name Project Title Description University of Milano-Fission track dating Use of fission tracks from U-235 to determine age Bicocca of rocks.
PECO, Inc., an Leaktest of Po-210 sources Leaktest of Po-210 sources used for static Astronics Company discharge.
China University of Fission Track Fission track dating of rock samples.
Petroleum - Beijing Oregon State Sterilization of Wood Products Sterilization of wood to 2.0 Mrad for fungal University experiments.
Lanzhou Center of Oil and Gas Resources, Fission Track Fission track dating of rock samples.
CAS Oregon State Core parameter Measurements using Using Cherenkov detectors to validate core operating history with large changes in reactor University Cherenkov Detection power (i.e., square wave).
Mas Oro PGE determination of placer samples PGE determination of placer samples via INAA.
Prevention oflnfections Associated with Combat-related Injuries by Local Sustained Co-Delivery of Vitamin D3 and Other Immune-Boosting Compounds Award Mechanism. We are Oregon State Prevention of Infections Associated preparing nanofiber wound dressings that contain with Combat-related Injuries by Local compounds that will be released over time to University Sustained Co-Delivery induce the immune response in wounds to help prevent infection and speed wound healing. The nanofibers must be irradiated so that they are sterile. These experiments will be performed in cell culture and in animal models.
PGNAA of Niobium for characterization of Oregon State Niobium Impurity Determination impurities. This technique will be evaluated University against current standard methods for impurity determination.
Use of neutron radiography to view degradation in Oregon State Neutron Radiography of ATR Capsules aluminum ATR capsules from endurance testing University of these capsules under continuous hydraulic loading over the course of a year.
University of Oregon INAA of Ancient Ceramics from Korea Trace-element analyses of Neolithic and Bronze Age ceramics from SE Korea.
Funding Universita degli Studi di Milano-Bicocca China University of Petroleum - Beijing OSU Forest Products Lanzhou Center of Oil and Gas Resources, CAS NIA University of Oregon
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Project 2044 2045 2046 2047 2048 2050 2051 2052 2053 2054 2055 2056 2057 Users Olson van den Bogaard Cann Parra Christensen Lee Perez Rodriguez Stone-Sundberg Paulenova Buffington Loveland Loveland Dreilinger Table Vl.2 (continued)
Listing of Major Research and Service Projects Preformed or in Progress at the Radiation Center and Their Funding Agencies Organization Name Project Title Description point-of-use devices as incubators of This project investigates the bacterial colonization, University of Michigan halogenated phenol-mediated antibiotic changes of bacterial community structures, and development of antibiotic resistance in a drinking resistant bacteria water point-of-use filtration device.
Helmholtz-Zentrum fur Ozeanforschung GEOMARAr/Ar Ari Ar dating research of geological samples.
Kiel (GEOMAR)
Oregon State Determination of oxygen content in Investigation into PGNAA to determine oxygen University metal alloys content in BaTi03.
University of Sao Fission Track Dating Fission track dating of geologic materials.
Paulo Oregon State INAA of IV Fluids INAA to determine trace metal in TPN and University additives.
University of 0 regon Archaeological Ceramics fron Juju INAA to determine trace-element signature and Island, Korea provenance ofarchaeological ceramics.
University at Albany, Archaeological Ceramics from Cerro INAA to determine trace-element composition SUNY Jazmin and provenance of ceramics from Cerro Jazmin, Oaxaca.
Crystal Solutions, Dopants in Synthetic Sapphire INAA to verify trace-element content of synthetic LLC saoohires.
Measuring the uptake of strontium by inorganic Oregon State (IONSIV) and organic (chitosan-based) sorbent University Measuring the uptake of strontium materials. Kinetics of uptake will also be evaluated.
Natural strontium will be used as a carrier, and Sr-85 will serve as a tracer.
Oregon State 137-Cs activity in coastal sediments 137-Cs activity in coastal sediments.
University Oregon State Gamma Irradition Effects on HLW Evaluation of the effects of high levels of gamma University Sludge radiation on simulated Handord waste tank sludge.
Oregon State Investigation into the effects oflow level gamma University Reactor Irradiation of HLW Sludge and source neutrons on simulated Hanford waste tank sludge.
We're developing a resorbable polymer surgical NeuraMedica Dural Clip Development clip and applicator for durotomy closure (closure of incisions of the dura mater, membrane covering brain and spinal cord).
Funding University of Michigan GEOMAR Helmholtz Centre for Ocean Research University of Sao Paulo OSU College of Pharmacy National Geographic Explorer Grant Crystal Solutions, LLC osu NeuraMedica I
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Project 2058 2059 2060 2061 2062 2063 2064 2069 Users Cronn Alanko Ishizuka Weiss Reese Bohanan Schaefer Scaillet Table Vl.2 (continued)
Listing of Major Research and Service Projects Preformed or in Progress at the Radiation Center and Their Funding Agencies Organization Name Project Title Description Gamma irradiation of pollen has been used successfully by plant geneticists to facilitate discovery of genes and chromosomal regions that control traits of interest in crops and trees Gamma irradiation of Port-Orford like poplar. Geneticists in the US Forest Service USDA Forest Service Cedar pollen to generate chromosomal have identified valuable single gene traits in Port-Orford Cedar, an ecologically and economically segment deletions 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 goal of identifying the genes controlling these traits.
Use of neutron radiography to determine the ATI Detection of Boron in Niobium Metal presense of boron minerals in niobium metal ingots samples Geological Survey of Ari Ar geochronology of volcanic and igneous Ari Ar Geochronology rocks associated with subduction initiation of JapanlAIST oceanic island arc.
Oregon State Neutron Radiography Imaging of Investigation into the applicablity of neutron University Concrete radiography for evaluating concrete curing processes.
Oregon State Temporal Spectroscopy of Fissile Use of PGNAA facility to perform temporal University Materials spectroscopy for the purpose of determining fissile material content The plant microbiome is composed of bacteria and fungi that are vertically transmitted via the University of Oregon Microbial Inheritance in Seeds seed and horizontally transmitted via the soil.
The goal of this project it to understand the relative contribution of seedborne versus soilborne microbes in producing the corn microbiome.
We will be performing bench scale microcosm CDM Smith Abiotic Dechlorination of chlorinated studies to measure the abiotic dechlorination in solvents in soil matrices.
different soil matrices. Gamma irradiation will be used to s!_erilize the sa~les.
I SU-CNRS-Ari Ar dating of geologic samples Ari Ar analysis for age dating of geologic samples Universite d'Orleans (solid rock chips and minerals)
Funding USDA Forest Service Geological Survey of Japan OSU Radiation Center, DNDO Grant University of Oregon CDM Smith INSU-CNRS-Universite d'Orleans
Figure Vl.1 Summary of the Types of Radiological Instrumentation Calibrated to Support the OSU TRIGA Reactor and Radiation Center 40 35 30 25 20 15 10 5
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Alpha GM ION Micro Personal Air Detectors Detectors Chambers Meters Dosimeters Samplers Table Vl.3 Summary of Radiological Instrumentation Calibrated to Support OSU Departments OSUDepartment Number of Calibrations Biochem/Biophysics 1
Civil Engineering 2
COAS 1
Linus Pauling Institute 2
Microbiology 3
Nutrition & Exercise Science 1
Physics 3
Radiation Safety Office 22 Veterinary Medicine 1
Total 36 15-16 Annual Report e***.
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TableVl.4 Summary of Radiological Instrumentation C l"b t d t S t 0th A
a I ra e 0
uppor er lgenc1es Agency Number of Calibrations Clair Company 1
Columbia Steel Casting 3
Doug Evans, DVM 2
Epic Imaging 2
ESCO Corporation 6
Eugene Sand and Gravel 1
Fire Marshall/Hazmat 120 Gene Tools 3
Health Division 108 Hollingsworth & Vose 1
Knife River 3
NETL, Albany 4
Occupational Health Lab 1
ODOT 8
Oregon Health and Sciences University 40 PSU 19 Republic Services 2
Salem Hospital 12 Samaritan Health 37 Silverton Hospital 5
Weyerhaeuser 1
Total 379 15-16 Annual Report
--==-Work
Publications Alden,J.R., and L.D. Mine 2016. "Itinerant Potters and the Transmission of Ceramic Styles during the Proto-Elamite Period." In Trade and Interaction in the Uruk Expansion: Recent Insights from Archaeometric Analyses (guest editors L.D. Mine and G. Emberling), Special Section ofJournal of Archaeological Science: Reports 7C. doi:l0.1016/j.
jasrep.2016.03.022.
Ault, A.K., M. Frenzel, P.W. Reiners, N.H. Woodcock, and S.N. Thomson. 2016. A Record of Paleofluid Circulation in Faults Revealed by Hematite (U-Th)/
He and Apatite Fission-track Dating: an Example from Gower Peninsula Fault Fissures, Wales."
Lithosphere 8: 379-385. doi:l0.1130/1522.1.
Baldwin, S.L., and J.P. Das. 2015. Atmospheric Ar and Ne Returned from Mantle Depths to the Earth's Surface via Forearc Recycling." Pro. of the National Academy of Sci. http://www.pnas.org/cgi/doi/10.1073/
pnas.142412211.
Ballouard, C., M. Poujol, P. Boulvais,J. Mercadier, R. Tartese, T. Venneman, E. Deloule, M.Jolivet, I. Kere, M.
Cathelineau., and M. Cuney. n.d. "Magmatic and Hydrothermal Behavior of Uranium in Syntectonic Leucogranites: the Uranium Mineralization Associated with the Hercynian Guerande Granite (Armorican Massif, France)." Ore Geology Review, in press.
Bande, A., E.R. Sobel, A. Mikolaichuk, A. Schmidt, and D.F. Stockli. In review. "Exhumation History of the Western Kyrgyz Tien Shan: Implications for Intramontane Basin Formation." Submitted to Tectonics. Preprint.
Barrett, JS, R. Yanez, W. Loveland, S. Zhu, A.D. Ayangeakaa, M.P. Carpenter,J.P. Greene, R.V.F.Janssens, T.
Lauritsen, E.A. McCutchan, A.A. Sonzogni, C.J.
Chiara,J.L. Harker, and W.B. Walters. 2015. "The 136Xe + 208Pb Reaction: a Test of Models of Multi-nucleon Transfer Reactions." Phys. Rev. C 91:
064615.
15-16 Annual Report
-~--.
Behyari, M., M. Mohajjel, E.R. Sobel, M. Rezaeian, M.
Moayyed, and A. Schmidt. In second review.
Analysis of Exhumation History in Misho Mountains, NW Iran: Insights, Structural and Apatite Fission Track Data." Submitted to Neues Jahrbuch fur Geologie und Palantologie.
Preprint.
Bertsch, G.F., W. Loveland, W. Nazarewicz, and P. Talou.
2015. "Benchmarking Nuclear Fission Theory." J.
Phys. G; Nucl. Part. Phys 42: 077601.
Britsch, K. Marcum, W.R., Harmon, P.L., Liu, S.Y.,
Weiss, A., Howard, T.K., Moussaoui. M. In review. "Numeric Benchmark Study of Plate Vibration Experiments in Air and Water."
Submitted to Nuclear Engineering and Design.
Preprint.
Carrapa, B., X. Robert, P.G. Decelles, D.A. Orme, S.N. Thomson, and L.M. Schoenbohm. 2016.
Asymmetric Exhumation of the Mount Everest Region: Implications for the Tectono-topographic Evolution of the Himalaya."
Geology 44: 611-614. doi:10.1130/g37756.l.
Das, J.P., S.L. Baldwin, andJ.W. Delano. 2016.
"40Ar/39Ar and Cosmic Ray Exposure Ages of Plagioclase-rich Lithic Fragments from Apollo 17 Regolith, 78461." Earth Planets Space.
doi:10.1186/s40623-016-0381-9.
Dorsett, S.F., and K.S. Krane. 2015. "The Decay of 194Au to Levels in 194Pt." Applied Radiation and Isotopes 103, 135.
Emberling, G., and L.D. Mine. 2016. "Ceramics and Long-distance Trade in Early Mesopotamian States." In Trade and Interaction in the Uruk Expansion: Recent Insights from Archaeometric Analyses (guest editors L.D.
Mine and G. Emberling), Special Section of Journal of Archaeological Science: Reports 7C.
doi:l0.1016/j.jasrep.2016.02.024.
"WOrds:-----~~--
Gates, J.M., K.E. Gregorich, O.R. Gothe, E.C. Uribe, G.K.
Pang, D.L. Bleuel, M. Block, R.M. Clark, C.M.
Campbell, H.L. Crawford, M. Cromaz, A. Di Nitto, Ch.E. Diillmann, N.E. Esker, C. Fahlander, P.
Fallon, R.M. Farjadi, U. Forsberg,]. Khuyagbaatar, W. Loveland, A.O. Macchiavelli, E.M. May, P.R.
Mudder, D.T. Olive, A.C. Rice,}. Rissanen, D.
Rudolph, L.G. Sarmiento,J.A. Shusterman, M.A.
Stoyer, A. Wiens, A. Yakushev, and H. Nitsche. 2015.
"Decay Spectroscopy of Element 115 Daughers:
280Rg--7 276Mt and 276Mt--7 272Bh." Phys. Rev. C 92: 021301(R).
Gombosi, D.J., S.L. Baldwin, and E.B. Watson, et al. 2015.
"Argon Diffusion in Apollo 16 Impact Glass Spherules: Implications for 40Ar/39Ar Dating of Lunar Impact Events." Geochim Cosmochim Acta 148: 251-268. doi:l0.1016/j.gca.2014.09.031.
Gopnik, H., C. Reichel, L. Mine, and R. Elendari. 2016.
A View from the East: the Godin VI Oval and the Uruk Sphere." In Trade and Interaction in the Uruk Expansion: Recent Insights from Archaeometric Analyses (guest editors L.D. Mine and G. Emberling), Special Section of Journal of Archaeological Science: Reports 7C. doi:l0.1016/j.
jasrep.2016.02.020.
Holschuh, T.V., Marcum, W.R. In review. "A Two Region Prompt Jump Model." Submitted to Annals of Nuclear Energy. Preprint.
Howard, T.K., Marcum, W.R., Jones, W.F. 2015. "A Novel Approach to Modeling Fluid Structure Interactions."
Nuclear Engineering and Design 293: 1-15.
Huston, R.L., C. Heisel, B. Vermillion, J.M. Christensen, and L.D. Mine. In second review. Aluminum Content of Neonatal Parenteral Nutrition Solutions: Options for Reducing Aluminum Exposure." Submitted to Nutrition in Clinical Practice. Preprint.
Jia, Y., B. Fu, M. J olivet, and Sh. Zheng. 2015. "Cenozoic Tectono-geomorphological Growth of the SW Chinese Tian Shan: Insight from AFT and Detrital Zircon U-Pb Data." Journal of Asian Earth Sciences 111: 395-413.
Jolivet, M., F. Roger, Z.QXu,J.-L. Paquette, and H. Cao.
2015. "Mesozoic - Cenozoic Evolution of the Danba Dome (Songpan-Garze, East Tibet) as Inferred from LA-ICP-MS U-Pb and Fission-track Data." Journal of Asian Earth Sciences 102: 180-204.
Krane, K.S. 2015. "The Decays of109,111Pd and lllAg Following Neutron Capture by Pd." Applied Radiation and Isotopes 105, 278.
Krane, K.S. 2016. "Gamma-ray Spectrometry in the Decay of 194Ir to 194Pt." Applied Radiation and Isotopes 115,
- 32.
Kratz,J.V., W. Loveland, and K.J. Moody. 2015. "Syntheses of Transuranium Isotopes with Z<l03 in Multi-nucleon Transfer Reactions."Nucl. Phys.A 944: 117.
Labaume, P., F. Meresse, M.Jolivet, A. Teixell, and A.
Lahfid. 2015. "Tectono-thermal History of an Exhumed Thrust-sheet-top Basin: an Example from the South Pyrenean Thrust Belt."Tectonics 35.
doi:10.1002/2016TC004192.
Labaume, P., F. Meresse, M.Jolivet, and A. Teixell. n.d.
"Exhumation Sequence of the Basement Thrust Units in the West-Central Pyrenees. Constraints from Apatite Fission Track Analysis." Geogaceta, in press.
Loveland, W. 2015. An Experimentalist's View of the Uncertainties in Understanding Heavy Element Synthesis." Eur.}. Phys. A 51: 120.
Loveland, W. 2016. "High Qyality Actinide Targets." J.
Radioanal. Nucl. Chem. 307: 1591.
Loveland, W. n.d. "Characterizing the Mechanism(s) of Heavy Element Synthesis Reactions." Submitted to Nobel Symposium 160 Proceedings. Preprint.
Loveland, W., D.J. Morrissey, and G.T. Seabord. n.d. Modern Nuclear Chemistry. (Submitted to John Wiley &
Sons). Preprint.
Marcum, W.R., Brigantic, A.J. 2015. "Applying Uncertainty and Sensitivity on Thermal Hydraulic Subchannel Analysis for the Multi-Application Small Light Water Reactor." Nuclear Engineering and Design 293: 272-291.
Marcum, W.R., Hallman, L., Wachs, D.M., Robinson, A.B.,
Lillo, M.A. 2016 Aluminum Cladding Oxidation ofln-Pile Fueled Experiments." Journal of Nuclear Materials 471: 136-148 Marcum, W.R., Harmon, P.L. n.d. A New Measurement Technique for Characterizing Fluid Structure Interactions of a Helical Coil in Cross Flow." Journal of Fluids and Structures, in press.
15-16 Annual Report
Marcum, W.R., Holschuh T.V., Howard, T.K. 2015. "On the Steady Mechanical Response of a Heterogeneous Fuel Plate." Invited article, Nuclear Technology, Special Issue 190(2): 359-375.
Mine, L.D. 2016. "Trace-element Analyses ofUruk Ceramics: Establishing a Database to Track Interregional Exchange." In Trade and Interaction in the Uruk Expansion: Recent Insights from Archaeometric Analyses (guest editors L.D. Mine and G. Emberling), Special Section of Journal of Archaeological Science: Reports 7C: 798-807.
doi:l0.1016/j.jasrep.2016.03.025.
Mine, L.D., and G. Emberling. 2016. "Trade and Interaction in the Uruk Expansion: Recent Insights from Archaeometric Analyses." In Trade and Interaction in the Uruk Expansion: Recent Insights from Archaeometric Analyses (guest editors L.D. Mine and G. Emberling), Special Section of Journal of Archaeological Science: Reports 7C: 793-797.
doi:l0.1016/j.jasrep.2016.03.032.
Mine, L.D.,J. Pink, and}. Sherman. 2016. "Trace-element and Mineralogical Analysis of Field Clays, Valley of Oaxaca, Mexico, as a Basis for Archaeological Provenance Determination." Oregon State University Libraries. Dataset. http://dx.doi.org/10.7267/
N9MS3QNO.
Mine, L.D., R.J. Sherman, C. Elson, M. Winter, E. M.
Redmond, and C.S. Spencer. 2016. "Ceramic Provenance and the Regional Organization of Pottery Production during the Later Formative in the Valley of Oaxaca, Mexico: Results ofTrace-element and Mineralogical Analyses." In Trade and Interaction in the Uruk Expansion: Recent Insights from Archaeometric Analyses (guest editors L.D. Mine and G. Emberling), Special Section of Journal of Archaeological Science: Reports 8: 28-46.
doi:l0.1016/j.jasrep.2016.05.016.
Murray, K.E., P.W. Reiners, and S.N. Thomson. 2016. "Rapid Plio-Pleistocene Erosion in the Central Colorado Plateau Documented by Apatite Thermochronology from the Henry Mountains." Geology 44: 483-486.
doi:10.1130/g37733.l.
15-16 Annual Report
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Mutin, B., C.C. Lamberg-Karlovsky, and L.D. Mine. 2016.
"Investigating Ceramic Production during the Proto-Elamite Period at Tepe Yahya, Southeastern Iran:
Results oflnstrumental Neutron Activation Analysis
- of Periods I CV and IVB Ceramics." In Trade and Interaction in the Uruk Expansion: Recent Insights from Archaeometric Analyses (guest editors L.D.
Mine and G. Emberling), Special Section of Journal of Archaeological Science: Reports 7C. doi:l0.1016/j.
jasrep.2016.02.019.
Pfeifer, L.S., G.S. Soreghan, S. Pochat,J. Van Den Driessche, and S.N. Thomson. 2016. "Rapid Permian Exhumation of the Montagne Noire Metamorphic Core Complex Recorded in Provenance of Upper Paleozoic Clastic Strata in the Graissessac-Lodeve Basin, France." Basin Research. doi:l0.1111/
bre.12197.
Ranjbar, L., A. Farsoni, and E.M. Becker. 2016. A CZT-based Radioxenon Detection System in Support of the Comprehensive Nuclear-Test-Ban Treaty." Journal of Radioanalytical and Nuclear Chemistry. doi:l0.1007/
s10967-016-4872-8.
Ring, U., LT. Uysal,J. Glodny, T. Little, S. Cox, S.N. Thomson, K. Stiibner, and 0. Bozkaya. n.d. "Fault-gouge Dating in the Southern Alps, New Zealand." Submitted to Tectonics. Preprint.
Thomson, S.N. 2016. "Fission Track Analysis." In Encylopedia of Geochemistry, edited by W.M. White. Springer, Berlin. In press.
Thomson, S.N., G.S. Soreghan, P.W. Reiners, S.L. Peyton, and K.E. Murray. n.d. A Definitive 6 Ma Onset Age for Carving of the Northeastern Colorado Plateau Canyonlands (Utah and Colorado)." Submitted to Geology. Preprint.
V. Bosch, G., A. Teixell, M.Jolivet, P. Labaume, D. Stockli, M.
Domenech, and P. Monie. 2016. "Timing ofEocene-Miocene Thrust Activity in the Western Axial Zone and Chainon Bearnais (West-Central Pyrenees)
Revealed by Multi-method Thermochronology."
Comptes Rendus Geoscience 348: 246-256.
Wang, X., C. Song, M. Zattin, P. He, A. Song,]. Li, and W.
Wang. 2016. "Cenozoic Pulsed Deformation History of Northeastern Tibetan Plateau Reconstructed from Fission-track Thermochronology." Tectonophysics 672-673: 212-227.
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Yanez, R., and W. Loveland. 2015. "Predicting the Production of Neutron-rich Heavy Nuclei in Multi-nucleon Transfer Reactions Using a Semi-Classical Model Including Evaporation and Fission Competition, GRAZING-F."Phys. Rev. C 91: 044608.
Yanez, R., W. Loveland,]. King,J.S. Barett, N. Fotiades, and H.Y. Lee. n.d. "Total Kinetic Energy in the Fast Neutron-induced Fission of235U." Submitted to Phys. Rev. C. Preprint..
Yang, W., G. Dupont-Nivet, M.Jolivet, Zh. Guo, L.
Bougeois, R. Bos boom, Z. Zhang, B. Zhu, and G.
Heilbronn. 2015. "Magnetostratigraphic Record of the Early Evolution of the Southwestern Tian Shan Foreland Basin (Ulugqat Area), Interactions with Pamir Indentation and India-Asia Collision."
Tectonophysics 644-645: 122-137.
Zhou, R., L.M. Schoennohm, E.R. Sobel, B. Carrapa, and D.W. Davis. 2016. "Sedimentary Record of Regional Deformation and Dynamics of the Thick-skinned Southern Puna Plateau, Central Andes (26-27°S)."
Earth and Planetary Science Letters 433: 317-325.
doi:doi.org/10.1016/j.epsl.2015.11.012.
Presentations Ault, A.K., M. Frenzel, P.W. Reiners, N.H. Woodcock, and S.N. Thomson. 2015. "Hematite (U-Th)/He and Apatite Fission-track Dating Constrain Paleofluid Circulation in Faults: an Example from Gower Peninsula Fissure Fills, Wales." Eos Transactions AGU. AGU Fall Meeting. V51H-07.
Ault, A.K., P.W. Reiners, J.P. Evans, and S.N. Thomson. 2015.
"Linking Hematite (U-Th)/He Dating with the Microtextural Record of Seismicity in the Wasatch Fault Damage Zone, Utah." GSA Abstracts with Programs 47: 224.
Ault, A.K., P.W. Reiners, S.N. Thomson, and G.H. Miller.
2015. "Inverted Apatite (U-Th)/He and Fission-track Dates from the Rae Craton, Baffin Island, Canada, and Implications for Apatite Radiation Damage-He Diffusivity Models." Eos Transactions AGU. AGU Fall Meeting. V32B-04.
Baldwin, S.L. February 25, 2016. "Discovering the World's Youngest Exhumed Ultrahigh-pressure Terrane."
Christchurch, New Zealand: Department of Geological Sciences, University of Canterbury.
Baldwin, S.L. March 31, 2016. "Geodynamic Evolution of New Zealand." Christchurch, New Zealand:
. Department of Geological Sciences, University of Canterbury.
Baldwin, S.L. October 1, 2015. "Discovering the World's
-Youngest Exhumed Ultrahigh-pressure Terrane."
University of Pittsburgh: Department of Geology and Planetary Science Colloquium Series.
Baldwin, S.L., M. G. Malusa, P. G. Fitzgerald, and L.E.
Webb. November 1-4, 2015. "Deciphering the 4-D Evolution of Cenozoic (U)HP Terranes." Invited, Geological Society of America Abstracts with Programs. Baltimore, MD.
Ballouard, C., M. Poujol, M.Jolivet, C. Dubois, E. Hallot, P. Boulvais, M.P. Dabard, and R. Tartese. 2015.
"Geochronological and Thermochronological Constraints on the Carboniferous Magmatism of the Armorican Massif: from the Source to the Exhumation." Rennes: Variscan Meeting.
Ballouard, C., M. Poujol, P. Boulvais,J. Mercadier, R.
Tartese, D. Gapais, P. Yamato, M.Jolivet, T.
Vennemann, E. Deloule, M. Cathelineau, and M. Cuney. 2015. "Tectonic Record, Magmatic History and Hydrothermal Alteration in the Guerande Carboniferous Leucogranite, Armorican Massif, France: Implications on the Genesis ofU Mineralization." Florianopolis, Brazil: 8th Hutton Symposium on Granites and Related Rocks.
Betka, P.M., S.N. Thomson, L. Seeber, M.S. Steckler, and R.
Sincavage. Submitted abstract, 2016. "The Indo-Burma Ranges: Eocene - Pliocene Coevolution of the Paleo-Brahmaputra Fluvial-deltaic System and Indo-Burma Accretionary Prism." San Francisco, CA: AGU Fall Meeting.
Brigantic, A., Marcum, W.R. August 30-September 4, 2015.
"Applying Uncertainty and Sensitivity on Thermal Hydraulic Subchannel Analysis for the Multi-Application Small Light Water Reactor." Chricago, IL: 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics 5512-5525.
15-16 Annual Report
Darin, M.H., P.J. Umhoefer, S.N. Thomson, and C. Lefebvre.
2015. "Structural Geology and Exhumation of the Paleogene Southern Sivas Fold and Thrust Belt, Central Anatolia, Turkey." Eos Transactions AGU.
AGU Fall Meeting. T13B-2988.
Darin, M.H., P.J. Umhoefer, S.N. Thomson, and C. Lefebvre.
Abstract accepted, 2016. "Orogen-parallel Variations in Structural Style and Tectonic Exhumation during the Miocene Collision-escape Transition in Anatolia."
Denver, CO: GSA Annual Meeting.
Farsoni, A.T., E. Becker, L. Ranjbar, S. Czyz, and D.M.
Hamby. October 15-16, 2015. "Radioxenon Detection via Beta-Gamma Coincidence Technique." University of Michigan, Ann Arbor, MI: 2015 CVT Workshop.
Fitzgerald, P.G., S.L. Baldwin, M.A. Bermudez, L.E. Webb, T.A. Little, M.G. Malusa, S.R. Miller, and D.
Seward. November 1-4, 2015. "Constraints from Low Temperature Thermochronology on Exhumation of (U)HP Terranes: the Eastern Papuan New Guinea Example." Geological Society of America Abstracts with Programs. Baltimore, MD.
Hansman, R., U. Ring, S.N. Thomson, B. den Brok, P.W.
Reiners, and K. Stiibner. Submitted abstract, 2016.
"Constraining the Uplift History of the J abal Akhdar and Saih Hatat Culminations, Al Hajar Mountains, Oman, with Fission-track and (U-Th)/He Ages." San Francisco, CA: AGU Fall Meeting.
Harmon, P.L., Marcum, W.R. August 30-September 4, 2015.
"Comprehensive Characterization of a Helix Motion due to Flow Induced Vibration." Chicago, IL: 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics 7701-7713.
Hemming, S.R., S.A. Brachfeld, C.P. Cook, K.J. Licht, E.L. Pierce, P.W. Reiners, S.N. Thomson, T. van der Flierdt, and T.J. Williams. 2015. "Detrital Thermochronology of Antarctic Glacigenic Sediments: Insights into Past Ice Sheet Behavior and Antarctica's Hidden Geology." GSA Abstracts with Programs 47(7): 292.
Holschuh, T.V., Marcum, W.R., Chichester, D.L., Watson, S.M.,Morrell, S.R.May 1-5,2016. "Using Cherenkov Light to Qyantify Reactor Kinetics Parameters and Infer Fissile Material Inventory for Nuclear Nonproliferation." Sun Valley, ID: The Physics of Reactors Conference, PHYSOR 2016 1-12.
15-16 Annual Report
--woro:S.~~~~lf Holschuh, T.V., Marcum, W.R., Morrell, S., Chichester, D.L.
July 12-16, 2015. "Qyantifying Kinetics Parameters using Cherenkov Light for Nonproliferation."
Atlanta, GA: Institute of Nuclear Materials Management Annual Meeting 1-10.
Howard, T.K., Marcum, W.R., Jones, W.F.June 12-16, 2016.
"Scaling Analysis of Vortex Shedding Frequency between Inline Plates." New Orleans, LA: American Nuclear Society Annual Meeting. Accepted.
Howard, T.K., Marcum, W.R., Latimer, G.D., Weiss, A.,Jones, W.F., Phillips, AM., Woolstenhulme, N., Holdaway, K., Campbell,}. June 12-16, 2016. Accelerometers in Flow Fields: A Structural Analysis of the Chopped Dummy In-Pile Tube." New Orleans, Louisiana:
Advances in Thermal Hydraulics, 2016 American Nuclear Society Annual Conference, Accepted.
King,]., R. Yanez,J.S. Barrett, W. Loveland, F. Tovesson, and N. Fotiades. February 2016. "Measurement of the Total Kinetic Energy Release as a Function of Bombarding Neutron Energy for 2321h(n,f)."
Baltimore, MD: SSAA Symposium.
Latimer, G.D., Marcum, W.R., Jones, W.F.June 12-16, 2016.
Advanced Test Reactor Mini-Plate Hydraulic Testing." New Orleans, LA: American Nuclear Society Annual Meeting, Accepted.
Lefebvre, C., S.N. Thomson, D.L. Whitney, and C. Teyssier.
2015. "Uplift and Exhumation in Central Anatolia:
New Results from Low-Temperature Chronometry in a Deeply Incised Granite in the Central Tauride Mountains, Turkey." Eos Transactions AGU. AGU Fall Meeting. T13B-2988.
Long, S.P., S.N. Thomson, P.W. Reiners, and R.V. DiFiori.
2015. "The Role of Upper-crustal Thickening in Spatially-focusing Synorogenic Extension: a Case Study from the Late Cretaceous-Paleocene Nevadaplano." Eos Transactions AGU. AGU Fall Meeting. T21B-2812.
Loveland, W. April 2016. "Large Scale Nuclear Collective Motion: Fusion, Fission, and Heavy Elements."
College Station, TX: TAMU Student Selected Seminar.
Loveland, W.June 2015. "Heavy Element Fusion/Fission."
New London, NH: 2015 Nuclear Chemistry Gordon Conference.
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Loveland, W.June 2015. "The O!iest for Superheavy Elements."Tahoe, CA: National Nuclear Physics Summer School.
Loveland, W.June 2016. "Characterizing the Mechanism(s) of Heavy Element Synthesis Reactions." Lund, Sweden:
Proceedings of the 160th Nobel Symposium.
Loveland, W. May 2016. "Fission Product Yields and Nuclear Forensics." Corvallis, OR: OSU Nuclear Physics Program.
Mine, L.,J. Pink, and V. Perez Rodriguez. April 2016.
"Evaluating the Evidence for Ceramic Exchange with the Valley of Oaxaca during the Late to Terminal Formative."The Cerro Jazmin Archaeological Project 2008-2015 - Discussing Early Urbanism and City Life in the Late and Terminal Formative Mixteca Alta, Mexico. Orlando, FL: 81st Annual Meeting, Society for American Archaeology.
Mine, L.D. October 30, 2015. "Pots, Clays, and Wasters:
Mapping Out Ceramic Exchange Networks in the Late Classic Valley of Oaxaca." Invited lecture for the University of Oregon Anthropology Colloquium Series.
Murray, K.E., P.W. Reiners, X. Robert, S.N. Thomson, and K.X. Whipple. Abstract accepted, 2016. "Ogliocene Rock Cooling of the North-Central Colorado Plateau Region: Erosion or a Variable Geothermal Gradient?" Denver, CO: GSA Annual Meeting.
Painter, C.S., B. Carrapa, P.G. DeCelles, G.E. Gehrels, and S.N. Thomson. 2015. "Cretaceous Exhumation of the North American Cordillera Measured through Mineral Multi-dating: Insights into Basin Filling Models and Orogenic Architecture." Eos Transactions AGU. AGU Fall Meeting. V52C-04.
Ranjbar, L., A.T. Farsoni, and E.M. Becker. October 31 -
November 7, 2015. "Development of a Two-channel CZT-based Detection System for Atmospheric Radioxenon Measurement." San Diego, CA: The IEEE Nuclear Science Symposium.
Ranjbar, L., A.T. Farsoni, E. Becker, and D.M. Hamby.
October 15-16, 2015. "Coincidence Simulation of a Two-channel CZT-based Radioxenon Detector."
University of Michigan, Ann Arbor, MI: 2015 CVT Workshop.
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Ring, U., K. Gessner, S.N. Thomson, and V. Markwitz. 7015.
"Why Lithospheric Extension Separated the Aegean from Turkey." Eos Transactions AGU. AGU Fall Meeting. T23F-05.
Sobczyk, A., and E.R. Sobel. October 4-7, 2015. Apatite Fission-track Dating Reveals post-Variscan History of the Orlica-Snieznik Dome, Eastern Sudetes Mts. (Bohemian Massif, SW Poland)." Berlin:
GeoBerlin2015 - Dynamic Earth from Alfred Wegener to Today and Beyond. doi:l0.2312/gfz.
lis.2015.003.
Sobel, E.R. October 4-7, 2015. "Cenozoic Evolution of the North Pamir and the Tien Shan." Berlin:
GeoBerlin2015 - Dynamic Earth from Alfred Wegener to Today and Beyond. doi:l0.2312/gfz.
lis.2015.003.
Thomson, S.N. Submitted abstract, 2016. "Constraining the Uplift History of the J abal Akhdar and Saih Hatat Culminations, Al Hajar Mountains, Oman, with Fission-track and (U-Th)/He Ages." San Francisco, CA: AGU Fall Meeting.
Thomson, S.N., C. Lefebvre, P.J. Umhoefer,M.H. Darin, D.L.
Whitney, and C. Teyssier. Submitted abstract, 2016.
"Late Cenozoic Thermochronology and Exhumation History of Central Anatolia: Implications for the Timing and Nature of Transition from Collision to Escape Tectonics." San Francisco, CA: AGU Fall Meeting.
Thomson, S.N., G.S. Soreghan, P.W. Reiners, S.L. Peyton, and K.E. Murray. Abstract accepted, 2016. "A Definitive 6 Ma Start Date for Carving of the Northeastern Colorado Plateau Canyonlands." Denver, CO: GSA Annual Meeting.
Thomson, S.N., G.S. Soreghan, P.W. Reiners, S.L. Peyton, and K.E. Murray. 2015. "A Precise 6 Ma Start Date for Fluvial Incision of the Northeastern Colorado Plateau Canyonlands." Eos Transactions AGU. AGU Fall Meeting. EP41A-0914.
Veselovskiy, R.V., S.N. Thomson, A.A. Arzamastsev, and V.S. Zakharov. 2015. "Apatite Fission-track Thermochronology of Khibina Massif (Kola Peninsula, Russia): Implications for post-Devonian Tectonics of the NE Fennoscandia." Eos Transactions AGU. AGU Fall Meeting. T13A-2953.
15-16 Annual Report
Walker,K.L., B. Carrapa, S.N. Thomson, and A.L. Stevens.
Abstract accepted, 2016. "Climatic and Tectonic Control on Erosion across the Alpine Fault, South Island, New Zealand." Denver, CO: GSA Annual Meeting.
Webb, L.E., and K.A. Klepeis. 2015. "Punctuated Melt-enhanced Deformation and Tectonic Reactivation Above a Long-lived Subduction Zone, Coastal Andes, Central Chile." Geological Society of America Abstracts with Programs 47 (7): 495.
Whitney, D.L., M.J. Meijers, C. Lefebvre, M.A. Cosca, S.N.
Thomson, and A. Mulch. 2016. "Tracking Anatolian Lithosphere Evolution with 'Tectonochemistry'."
Goldschmidt Conference Abstracts. 3409.
Students Ballouard, C. PhD thesis, December 2016. "Geochronology and Thermochronology of the Carboniferous High Heat Production Belt Granites, Armorican Massif (France)." University ofRennes. (Advisors M. Poujol and M.Jolivet).
Bande, Alejandro. PhD thesis, expected 2016. "Constraining Deformation History of the Talas-Fergana Strike-Slip Fault and Kinematically-linked Thrust Faults, Kyrgyz Republic." (Advisor Prof. E. Sobel).
Barrett, JS. PhD, September 2015. "The 136Xe + 208Pb Reaction: a Test of Models of Multi-nucleon Transfer Reactions."
Brombin, Valentina. PhD in progress. "Geochemical Characterization ofLithotypes ofVeneto Volcanic Province." University of Ferrara, Italy. (Advisor M.
Coltorti).
Brown, Emory. MS student, expected 2017. "Numerical Benchmark of a prototypic TREAT Water Flow Loop using TRACE." Nuclear Engineering, OSU.
Danielson, Jordan. MS student, expected summer 2016.
"On the Design of a Particle Image Velocimetry System to support NuScale Design Certification Testing." Nuclear Engineering, OSU. (Co-chair W.R.
Marcum).
Deeken, Anke. PhD thesis, expected 2017. "Long-term Erosion and Exhumation Rates across Different Climatic Zones in the Indian NW Himalaya."
Universitaet Potsdam. (Advisor Pro£ M. Strecker).
15-16 Annual Report
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Eugster, Patricia. PhD thesis, expected 2016. "Competing Ipfluence ofFluvial and Glacial Erosion in the Western Himalaya." (Advisor M. Strecker).
Georgieva, Viktoria. PhD thesis, expected 2016. "The Late Cenozoic Evolution ofTopography in the Patagonian Andes." (Advisor M. Strecker).
Goodrich, Samuel. PhD candidate, expected winter 2016. "The Transition to Turbulence in Natural Convection Flow Adjacent to Vertical Heated Cylinders." Nuclear Engineering, OSU.
Holschuh, Thomas, PhD candidate, expected summer 2016.
"O!iantifying Reactor Kinetics Parameters for Nonproliferation Using Cherenkov Light." Nuclear Engineering, OSU.
Howard, Trevor. PhD candidate, expected winter 2017. "On the Influence ofVortical Structures and Trailing Plates in axial flow." Nuclear Engineering, OSU.
Jia, Y. PhD, January 2016. "Cenozoic Tectonic and Geomorphological Evolution of the SW Chinese Tian Shan." Institute of Geology and Geophysics, Chinese Academy of Sciences, Beijing. (Advisors B.
Fu and M.Jolivet).
King,]. PhD in progress. Study of the 2321h(n.f) reaction.
Lagor, Samuel. MS, 2016. "The Relationship between Magmatism, Deformation, and Metamorphism during the Acadian Orogeny: A Case Study from the Knox Mountain Pluton, Green Mountains, Vermont, USA." University of Vermont. (Advisor L. Webb).
Latimer, Griffen. MS student, expected spring 2016.
"Comprehensive Characterization of Motion ofln-Pile Advanced Test Reactor Fuel Experiments based on Accelerometer Measurements and Fluid Structure Interactions." Nuclear Engineering, OSU.
McCaleb, K. PhD in progress. Study of Multi-nucleon transfer reactions.
Nation, Humberto. PhD in progress.
Nieblas, Andrew. MS, 2016. "Pressure-Temperature-Time-Deformation History of the Lahul Valley, NW Indian Himalaya." San Francisco State University. (Advisor M.Leech).
Nighbert, Christopher. MS student, expected spring 2017.
"Thermal and Hydrodynamic Mixing in the Suppression Pool of the NuScale Integral Scaled Test Facility using PIV and LIF." Nuclear Engineering, OSU. (Co-chair W.R. Marcum).
Words Nixon, Chad. PhD student, expected spring 2017. "A New Measurement Technique for Qyantifying Flow Induced Vibration of a Cylindrical Rod under Axial Flow." Nuclear Engineering, OSU.
Pink, Jeremias. PhD in progress.
Ranjbar, Leila. PhD, March 2016. "A Two-channel CZT-based Radioxenon Detection System for Nuclear Weapons Test Monitoring."
Robertson, B.R. MS, December 2015.
Ruksznis, Abigail. MS, 2015. "Geology and Geochronology of Cenozoic Sedimentary Basins, East-Central Nevada."
Stanford University. (Advisor E. Miller).
Torres, Veronica Acosta. PhD, 2016. "Morphotectonic Evolution of the Kenya rift and Erosion Processes on Different Time Scales Using Cosmogenic Nuclides and (U-Th)/He Dating." (Advisor M. Strecker).
Walker, Sarah T. MA thesis, 2016. "Pottery, Politics, and Trade Routes: Evaluating Independence in Late Classic J alieza, Oaxaca." Applied Anthropology, osu.
Wei, Youran. MS student, expected fall 2015. "Experimental Measurement and Characterization of Oxide Growth on Preconditioned Aluminum." Material Science, OSU. (Co-chair W.R. Marcum).
Yao, L. PhD in progress. Study of PCN in hot fusion reactions.
Zabriskie, Adam. PhD candidate, expected spring 2016. "Fuel Particle Effects on TREAT Fuel Transients using MAMMOTH." Nuclear Engineering, OSU.
15-16 Annual Report
Oregon State University Radiation Center, 100 Radiation Center, Corvallis, OR 96331 www.radiationcenter.oregonstate.edu
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