ML20307A413

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Oregon State University Triga Reactor (OSTR)
ML20307A413
Person / Time
Site: Oregon State University
Issue date: 10/22/2020
From: Reese R
Oregon State University
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML20307A413 (82)


Text

Radiation Center Oregon State University 100 Radiation Center Corvallis, Oregon 97331 P 541-737-2341 F 541-737-0480 rad.Jationcenter.oregonstate.edu October 22, 2020 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Reference:

Oregon State University TRI.GA Reactor (OSTR)

Docket No. 50-243, License No. R-106 In accordance with section 6.7.1 of the OSTR Technical Specifications, we ~re hereby submitting the Oregon State University Radiation Center and OSTR Annual Report for the period July 1, 2019 through June 30, 2020.

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 accqm_plishments over the past year.

I declare under penalty of perjury that the foregoing is true and correct.

Executed on: /z /uJ

/0 I z J Sincerely, Steven R. Reese Director Cc: Michael Balazik, USNRC Dr. lrem Turner, OSU Kevin Loche, USNRC Dan Harlan, OSU Maxwell Woods, ODOE

    • Submitte*d 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 requirem~nts of:

A. V.S. Nuclear Regulatory Commission, License No. R-106

B. Battelle Energy Alliance, LLC;

. Subcontract Award No. 00074510 .

C. Oregon Department of Energy, OOE Rule No. 345..:030-010 .

Con.ten.ts

  • Part I-Overview Executive Summary .....................................................................................................................................4 **

lntroduction ..........................................................................................................................~******** ................. 4 Overview of the Radiation Center ............................_ ........-:.......... ._ ........................................;........... 5 Part II-People Radiation Center Staff .................................................................................................................................6 **

Reactor Operations Committee ..............................................................................................................6 Professional & Research Faculty .............................................................................................................. 7 Part 111-Faci_lities Research Reactor ..........................................................................................................................................8 **

Analyt,ical Equipment ..................................................................................................................................9 Radioisotope Irradiation Sources ............................................................................................................ 9 Laboratories & Classrooms ......................................................................................................................1O Instrument Repair & Calibration ............................................................................................................1O Library .............................................................................................................................................................10 Part IV-Reactor Operating Statlstlcs ....................................................................................................................................14 Experiments Performed ...........................................................................................................................14 Unplanned Shutdowns .............................................................................................................................15 Changes Pursuant to 10 CFR 50.59 ......................................................................................................15 **

Surveillance & Maintenance ...................................................................................................................15 Part V-Radiation Protection Introd uction ..................................................................................................................................................28 Environmental Releases ...........................................................................................................................28 Personnel Doses ..........................................................................................................................................29 Facility Survey Data ....................................................................................................................................29 Environmental Survey Pata ....................................................................................................................30 **

Radioactive Material Shipments ...........................................................................................................31 References .....................................................................................................................................................31 Part VI-Work Summary ..*.....................................................................................................................................................48 Teaching .........................................................................................................................................................48 Research & Service ............................................................................................................_.........................48 Part VII-Words Documents Published or Accepted .....................................................................................................70 Presentations................................................................................................................................................76 **

Students ................................................................................................................................................._....... 78

    • Tables
    • Table Ill. 1 Title Page Gammacell 220 60(0 Irradiator Use . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 1 111.2 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 TI me . . . . . . . . . . . . . . *. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18 IV.4 Use of OSTR Reactor Experiments . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .* . . . . . . . . . 19 IV.5 Unplanned Reactor Shutdowns and Scrams . . . . . . . . . . . . . . . . . . . . . . . . . *. . . . . . . . . . . . . 19
    • V. 1 V.2 Radiation Protection Program Requirements and Frequencies . . . . . . . . .. . . . . . . . . . . . . . . . . . 32 Monthly Summary of Liquid Effluent Releases to the Sanitary Sewer . . . . . . . . . . . . . . . . . . . . . . 33
    • V.3 V.4 V.5 Annual Summary of Liquid Waste Generated and Transferred. . . . . . . . . . . . . . . . . . . . . . . . . . . 34 Monthly Summary of Gaseous Effluent Releases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . '. . 35 Annual Summary of Solld Waste Generated and Transferred. . . . . . . . . . . . . . . . . . . . . . . . . . . . 35
    • V.6 V.7 Annual Summary of Personnel Radiation Doses Received . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 36 Total Dose Equivalent Recorded Within the TRIGA Reactor Facility . . . . . . . . . . . . . . . . . . . . . . . 37 V.8 Total Dose Equivalent Recorded on Area Within the Radiation Center. . . . . . . . . . . . . . . . . . . . . . 38 V.9 Annual Summary of Radiation and Contamination Levels Within the Reactor . . . . . . . . . . . . . . . . : *40 V.10 Total Dose Equivalent at the TRIGA Reactor Faclllty Fence . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 41
    • V. 1 1 V. 12 Total Dose Equivalent at the Off~Slte Gamma Radiation. Monitoring Stations . . . . . . . . . . . . . . . . . 42 Annual Average Concentration of the Total Net Beta Radioactivity. . . . . . . . . . . . . . . * . . . . . . . . 43 V. 13 Radioactive Materi_al Shipments under NRC General License R-106 . . . . . . . . . . . . . . . . . . . . . . . 44 V. 14 Radioactive Material Shipments: under Oregon License ORE 90005 . . . . . . . . . . . . . . . . . . . . . . . 45 V. 15 Radioactive Material.Shipments' Under NRC General License 10 CFR 110.23 . . . . . . . . . . . . .* .* ... 46.
    • Vl.1 .

Vl.2 Vl3 Institutions and Agencies Which Utilized the Radiation Center . . . . . . . . . . . . . . . . . . . . . . . . . . 50 Listing of Major Research & Service Projects Performed and Their Funding . . . . . . . . . . . . . . . . -.. 54 Summary of Radiological Instrumentation Calibrated to Support OSU Departments . . . . . . . . . . . . 69

    • Vl.4 Summary of Radiological Instrumentation Calibrated to Support Other Agencies . . . . . . . . . . . . . 69
  • Figures
    • Table IV.1

. Title Monthly Surveillance and Maintenance (Sample Form)---****---**-******--**-**---**-****-*----****--*-**-**-**-***--**-**20 Page IV.2 Quarterly Survelllance and Maintenance (Sample Form)----*-**----**----*-***-**-**-*-*-*---:--*-*--*-**-**-*-***-*-*-**21 IV.3

  • Semi-Annual Survelllance and Maintenance (Sample Form) .---*--*---*----*---*-**-**-*--*-***--*-**-*****--*-*-**23 IV.4 Annual Surveillance and Maintenance (Sample Form) -:*-*--*-**-*---*-**-**-*--*-*---*-**---*--*-*--**---*-**----*-****.25
    • V,1 Vl.1 Monitoring Stations for the OSU TRIGA Reactor *-**-**-*-*--*-**-*--*--****-*-******-***-**--*---*-*****-**-**-:*-**--*-***..47 Summary of the Types of Radiological Instrumentation Calibrated **--***-*---*-*---*-**-**-*---*-*--****-**-**-**--*-*-**69

Overview **

Executive Summary Introduction **

The data from this reporting year shows that the use of the The current annual report of the Oregon State University Radiation Center and the Oregon State TRI GA reactor (OSTR) Radiation Center and TRI GA Reactor follows the usual format has continued to grow in many areas. by including information relating to the entire Radiation The Radiation Center supported 40 different courses this year, mostly in the School of Nuclear Science and Engineering.

Center rather than just the reactor. However, the information is sti ll presented in such a manner that data on the reactor may be examined separately, if desired. It should be noted that all About 40% of these courses involved the OSTR. The number ofOSTR hours used for academic courses and training was 9, while 3,621 hours0.00719 days <br />0.173 hours <br />0.00103 weeks <br />2.362905e-4 months <br /> were used for research projects. Eighty-four annual data given in this report covers the period from July I, 2019 through June 30, 2020 . Cumulative reactor operating data **

in this report relates only to the LEU fueled core. This covers percent (84%) of the OSTR research hours were in support of the period beginning July I, 2008 to the present date. For a off-campus research projects, reflecting the use of the OSTR summary of data on the reactor's two other cores, the reader is nationally and internationally. Radiation Center users pub-1ished or submitted 95 articles this year, and made 36 presen-tations on work that involved the OSTR or Radiation Center.

referred to previous annual reports.

In addition to providing general information about the activi- **

The number of samples irradiated in the reactor during this re- ties of the Radiation Center, this report is designed to meet porting period was 2,861. Funded OSTR use hours comprised the reporting requirements of the U. S. Nuclear Regulatory 84% of the research use. Commission, the U. S. Department of Energy, and the Oregon Personnel at the Radiation Center conducted 114 tours of the facility, accommodating I, I 09 visitors. The visitors included 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.

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 107. Reactor related projects comprised 73% of all projects.

The total research dollars in some way supported by the Radia-tion Center, as reported by our researchers, was $8.8 million.

The actual total is likely higher. This year the Radiation Center provided service to 62 different organizations/institu-tions, 42% of which were from other states and 39% 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.

0 Annual Report

  • a
    • OVERVIEW
    • Overview of the Radiation Center tional collaborative standard problem exploring the operation and safety of advanced natural circulations reactor concepts.

The Radiation Center is a unique facility which serves the Over 7 intern.¢onal organizations are involved in this stan-entire OSU campus, all otherinstitutions within the Oregon dard problem at OSU.

University System, and many other universities and orga-

    • nizations throughout the nation and the world. The Center also regularly provides special services to state and federal agencies, particularly agencies dealing with law enforce-The Advanced Nuclear Systems Engineering Laboratory (ANSEL) is the home to two major thermal-hydraulic test facilities-the High Temperature Test Facility (HTIF) and ment, energy, health, and environmental quality, and renders the Hydro-mechanical Fuel Test Facility (HMFTF). The assistance to Oregon industry. In addition, the Radiation HTTF is a 1/4 scale model of the Modular High Temperature Center provides permanent office and laboratory space for Gas Reactor. The vessel has a ceramic lined upper head and the OSU Schoof of Nuclear Science and Engineering, the shroud capable of operation at 850oC (well mixed helium).

OSU Institute of Nuclear Science and Engineering, and for The design will allow for a maximum operating pressure of the OSU nuclear chemistry, radiation chemistry, geochemis- l.0MPa- and a maximum core ceramic temperature of 1600°C .

try and radiochemistry programs. There is no other university The nominal working fluid will be helium with a core power facility with the combined capabilities of the OSU Radiation of approximately 600 kW (note that electrical heaters are used

    • Center in the western half of the United States. ,

Located in the Radiation Center are many items of special-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 HTIF can be used ized equipment and unique teaching and research facilities .

to simulate a wide range of accident scenarios in gas reac-They include a TRI GA Mark II research nuclear reactor; a tors to include the depressurized conduction cooldown and

    • 60Co gamma irradiator; a large number of state-of-the art computer-based gamma radiation spectrometers and associat-ed germanium detectors; and a variety of instruments for ra-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-
    • diation measurements and monitoring. Specialized facilities for radiation work include teaching and research laboratories 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 with instrumentation and related equipment for performing neutron activation analysis and radiotracer studies; laborato- enriched fuel. This data in turn will be used to verify current ries for plant experiments involving radioactivity; a facility theoretical hydro- and thermo-mechanical codes being used for repair and calibration of radiation protection instrumenta- during safety analyses. The maximum operational pressure of tion; and facilities for packaging radioactive materials for the HMFfF is 600 psig with a maximum operational tem-shipment to national,and international destinations . perature of 450°F.
    • Also housed in the Radiation Center is the Advanced Ther-mal Hydraulics Research Laboratory (ATHRL), which is The Radiation Center staff regularly provides direct sup-port and assistance to OSU teaching and research programs.
    • used for state-of-the-art two-phase flow experiments .

The Multi-Application Light Water Reactor (MASLWR) is Areas of expertise commonly involved in such efforts include nuclear engineering, nuclear and radiation chemistry, neutron activation analysis, radiation effects on biological systems, ra-

    • a nuclear power plant test facility that is instrumental in the development of next generation commercial nuclear reactors currently seeking NRC certification. The Test Facility is con-diation dosimetry, environmental radioactivity, production of short-lived radioisotopes, radiation shielding, nuclear instru-mentation, emergency response, transportation of radioactive
    • structed of all stainless steel components and is capable of operation at full system pressure (1500 psia), and full system materials, instrument calibration, radiation health physics, radioactive waste disposal, and other related areas .

temperature (600F).

In addition tq formal academic and research support, the All components are 1/3 scale height and 1/254.7 volume Center's staff provides a wide variety of other services includ-scale. The current testing program is examining methods ing public tours and instructional programs, and professional for natural circulation startup, helical steam g~erator heat consultation associated with the feasibility,* design, safety, transfer performance, and a wide range of design basis, and and execution of experiments using radiation and radioactive

    • beyond design basis, accident conditions. In addition, the MASLWR Test Facility is currently the focus of an interna-materials .

2019-2020 ©

People **

This section contains a listing of all peop le who were residents of the Radiation Center or who worked a significant amount of time at the Center during this reporting period. **

It should be noted that not all of the faculty and students who used the Radiation Center for their teaching and research are listed.

Summary information on the number of people involved is given in Table VI.I , while individual names and projects are listed in **

Table VI.2 .

Radiation Center Staff Reactor Operations Committee **

Steve Reese, Director Dan Harlan, Chair **

Dina Pope, Matthew Berry, Office Manager Business Manager OSU Radiation Safety Leo Bobek **

UMass Lowell Erica Emerson, Receptionist Abi Tavakoli Farsoni S. Todd Keller, Reactor Engineer, Senior Reactor Operator OSU School of Nuclear Science and Engineering Celia Oney, Reactor Supervisor, Senior Reactor Operator Robert Schickler, Reactor Administrator/ Assistant Direc-Scott Menn OSU Radiation Center **

tor, Senior Reactor Operator Celia Oney (not voting)

Scott Menn, Senior Health Physicist OSU Radiation Center Steve Reese (not voting)

Kyle Combs, Health Physicist OSU Radiation Center Leah Mine, Neutron Activation Analysis Manager Robert Schickler Steve Smith, Development Engineer, OSU Radiation Center Senior Reactor Operator Chris Ku/ah , Senior Reactor Operator Julie Tucker OSU Mechanical, Industrial and Manufacturing Engineering Dan Sturdevant, Custodian Haori Yang Emory Colvin , Reactor Operator (Student) OSU School of Nuclear Science and Engineering Maggie Goodwin , Reactor Operator (Student)

William Hull, Reactor Operator (Student)

Jackson Keppen, Reactor Operator (Student)

Griffen Latimer, Reactor Operator (Student)

Tracey Spoerer, Reactor Operator (Student)

Scott Veldman , Reactor Operator (Student)

Nathan Wiltbank , Reactor Operator (Student)

Stephanie Juarez, Health Physics Monitor (Student)

Destry Jensen, Health Physics Monitor (Student)

Brandon Farjardo, Health Physics Monitor (Student)

Taighlor Story, Health Physics Monitor (Student)

Nicolaas VanDerZwan , Health Physics Monitor (Student)

© Annual Report

    • PEOPLE
    • Professional and Research Faculty
    • Tony Alberti *Todd Palmer Postdoctoral Scholar, Nuclear Science and Engineering Professor, Nuclear Science and Engineering Samuel Briggs *Alena Paulenova
    • Assitant Professor, Nuclear Science and Engineering Tianyi Chen Associate Professor, Nuclear Science and Engineering Dina Pope Office Manager, Radiation Center Assistant Professor, Nuclear Science and Engineering
  • Abi Farsoni Leila Ranjbar Instructor, Nuclear Science and Engineering Associate Professor, Nuclear Science and Engineering
    • /zabela Gutowska Assistant Professor, Senior Research , Nuclear Science and
  • Steven Reese Director, Radiation Center
    • Engineering Robert Schickler
  • David Hamby Reactor Administrator/Assistant Director, Radiation Center Professor, Nuclear Science and Engineering Aaron Weiss
    • Lucas Hart Faculty Research Associate, Chemistry Sr. Faculty Research Assi stant, Nuclear Science and Engineering Brian Woods
    • *Kathryn Higley Schoo l Head, Professor, Nuclear Science and Engineering
  • Todd S. Keller Professor, Nuclear Science and Engineering Qiao Wu
    • Reactor Engineer, Radiation Center
  • Walter Loveland Professor, Nuclear Science and Engineering Haori Yang Assistant Professor, Nuclear Science and Engineering
    • Professor, Chemistry Wade Marcum Associate Professor , Nuclear Sc ience and Engineering *OS TR users fo r research and/or teaching
    • Mitch Meyer Professor of Practice, Nuclear Science and Engineering
    • *Scott Menn Senior Health Physicist, Radiation Center
  • Leah Mine
    • Associate Professor, Anthropology Guillaume Mignot Assistant Professor, Senior Research, Nuclear Science and Engineering
  • Celia Oney
    • Reactor Supervisor, Radiation Center Camille Palmer Research Faculty and Instructor, Nuclear Science and Engineering
    • 2019-2020 0

Faciliti es **

Research Reactor The Oregon State University TRJGA Reactor (OSTR) is a Rotation of the rack ensures that each sample will receive an water-cooled, swimming pool type research reactor which uses identical irradiation.

uranium/zirconium hydride fuel elements in a circular grid The reactor's thermal column consists of a large stack of array. The reactor core is surrounded by a ring of graphite which serves to reflect neutrons back into the core. The core graphite blocks which slows down neutrons from the reactor is situated near the bottom of a 22-foot deep water-filled tank, core in order to increase thermal neutron activation of samples.

and the tank is surrounded by a concrete bioshield which acts Over 99% of the neutrons in the thermal column are thermal as a radiation shield and structural support. The reactor is li- neutrons. Graphite blocks are removed from the thermal col-censed by the U.S. Nuclear Regulatory Commission to operate umn to enable samples to be positioned inside for irradiation.

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 beam ports are tubular penetrations in the reactor's main concrete shield which enable neutron and gamma radiation **

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 to stream from the core when a beam port's shield plugs are removed . The neutron radiography facility utilized the tangen-tial beam port (beam port #3) to produce ASTM E545 category elements for special in-core irradiations, an in-core irradiation tube, and a cadmium-lined in-core irradiation tube for experi-I radiography capability. The other beam ports are available for a variety of experiments. **

ments requiring a high energy neutron flux.

If samples to be irradiated require a large neutron fluence, The pneumatic transfer facility enables samples to be especially from higher energy neutrons, they may be inserted inserted and removed from the core in four to five seconds. into a dummy fuel element. This device will then be placed Consequently this facility is normally used for neutron activa- into one of the core's inner grid positions which would nor-tion analysis involving short-lived radionuclides. On the other mally be occupied by a fuel element. Similarly samples can be hand, the rotating rack is used for much longer irradiation of placed in the in-core irradiation tube (ICIT) which can be samples (e.g. , hours). The rack consists ofa circular array of inserted in the same core location.

40 tubular positions, each of which can hold two sample tubes.

0 Annual Report

    • FACILITIES The cadmlum-llned In-core lrradlatlou tube (CLICIT) enables samples to be irradiated in a high flux region near the center of the' core. The cadmium lining in the facility elimt-ficient to meet the needs of most researchers. This is true not only for INAA, but also for other experimental purposes such as the 39ArflOAr ratio and fission track methods of age dat-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-ing samples.

Analytical Equipment cupied by a fuel element. It is the same as the ICIT except for the presence.of the cadmium lining. The Radiatio!1 Center has a large variety of radiation detec-tion instrumentation. 1bis equipment 'is upgraded as neces-The two main uses of the OSTR are instruction and research. sary, especially the gamma ray spectrometers with their associated computers and germanium detectors. Additional Instruction equipment for classroom use and an extensive inventory of Instructional use of the reactor is twofold. First, it is used sig-portable radiation detection instrumentation are also avail-nificantly for classes in Nuclear Engineering, Radiation Health able.

Physics, and Chemistry at both the graduate and undergradu-

    • ate levels to demonstrate num*erous 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 Radiation Center nuclear instrumentation receives intensive -

e in both teaching and research applications. In addition, service projects also use these systems arid the combined use

    • many demonstrations and instructional experiments can be performed using the OSTR which cannot be carried out with a often results in 24-hour per day schedules for many of the analytical instruments. Use of Radiation Center equipment commercial power reactor. Shorter-term: demonstration experi- extends beyond that located at the Center and instrumentation ments are also performed for many undergraduate students fu may be made.available on a loan basis to OSU researchers in Physics, Chemistry, and Biology classes, as well, as for visitors other departments .

from other universities and colleges, froµi high schools, and from public groups .

Radioisotope Irradiation Sources The _second instructional application of the OSTR involves educating ~ctor operators, operations managers, and health The Radiation Center is equipped with a _10,200 curie (as of physicists. The OSTR is in a unique position-to provide such June, 2015) Gammacell 220 tiOCo irradiator which is capable

    • education since curricula must include hands-on experience at an operating reactor and in associated laboratories. The many types of educational programs that the Radiatipn Center pro-of delivering high doses of gamma radiation over a range of dose rates to a variety of materials .
    • vides are more fully described in Part VI of this report.

During this reporting period the OSTR accommodated a 1ypically, 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-

    • number of different OSU academic classes and other academic programs. In addition, portions of classes from other Oregon ization of food materials, soils, sediments, biological speci-men, and other media; gamma radiation damage studies; and universities were also supported by the OSTR. other such applications. In addition to the 60Co irradiator, the Center is also equipped with a variety of smaller 60Co, 137Cs, Research 226 Ra, plutonium-beryllium, and other isotopic sealed sources The OSTR is a unique and valuable tool for a wide variety of various radioactivity levels which are available for use as of research applications and serves as an excellent source of irradiation sources.

neutrons and/or gamma radiation. The.most commonly used experimental technique requiring reactor use is instrumental During this reporting period there was a diverse group of neutron activation analysis (INAA). This is a particularly projects using the 60Co irradiator. These projects included the sensitive method of elemental analysis which is descnbed in irradiation of a variety of biological materials including dif-

    • 'more detail in Part VI. :

The OSTR's irradiation facilities provide a wide range of ferent types of seeds .

    • neutron flux levels and neutron flux qualities which are suf-2019-2020 ©

FAC.1 LITI ES **

In addition, the irradiator was used for sterilization of several media and the evaluation of the radiation effects on different intense radiation fields and low range instruments used to measure environmental levels of radioactivity.

materials. Table ID. I provides use data for the Gammacell 220 irradiator. The Center's instrument repair and cahbration facility is used regularly throughout the year and is absolutely essential to the Laboratories and Classrooms 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 The Radiation Center is equipped with a number of different radioactive material laboratories designed to accommodate calibration program for the Center, including cahbration of es-sentially all radiation detection instruments used by state and **

federal agencies in the state of Oregon. This includes instru-research projects and classes offered by various OSU aca-ments used on the OSU campus and all other institutions in the demic departments or off-campus groups.

Oregon University System, plus instruments from the Oregon Instructional facilities available at the Center include a labo-ratory especially equipped for teaching radiochemistry and a nuclear instrumentation teaching laboratory equipped with Health Division's Radiation Protection Services, the Oregon Department of Energy, the Oregon Public Utilities Commis-sion, the Oregon Health and Sciences University, the Army modular sets of counting equipment which can be configured to accommodate a variety of experiments involving the mea-Corps of Engineers, and the U.S. Environmental Protection Agency. **

surement of many types of radiation. The Center also has two student computer rooms.

Library In addition to these dedicated instructional facilities, many other research laboratories and pieces of specialized equip- The Radiation Center has a library containing a significant col-ment are regularly used for teaching. In particular, classes lections of texts, research reports, and videotapes relating to are routinely given access to gamma spectrometry equipment located in Center laboratories. A number of classes also regu-larly use the OS1R and the Reactor Bay as an integral part of nuclear science, nuclear engineering, and radiation protection.

The Radiation Center is also a regular recipient of a great vari- **

their instructional coursework.

There are two classrooms in the Radiation Center which are ety of publications from commercial publishers in the nuclear field, from many of the professional nuclear societies, from the U.S. Department of Energy, the U.S. Nuclear Regula-capable ofholding about 35 and 18 $tudents. In addition, there are two smaller conference rooms and a library suitable for graduate classes and thesis examinations. As a service to tory Commission, and other federal agencies. Therefore, the Center library maintains a current collection of leading nuclear **

research and regulatory documentation. In addition, the Center the student body, the Radiation Center also provides an office has a collection of a number of nuclear power reactor Safety area for the student chapters of the American Nuclear Society Analysis Reports and Environmental Reports specifically and the Health Physics Society. prepared by utilities for their facilities.

All of the laboratories and classrooms are used extensively 'The'Center maintains an up-to-date set of reports from such during the academic year. A listing of courses accommodated organiz.ations as the International Commission on Radiological at the Radiation Center during this reporting period along Protection, the National Council on Radiation Protection and with their enrollm~ts is given in Table ID.2. Measurements, and the International Commission on Radio-Instrument Repair & Calibration Facility logical Units. Sets of the current U.S. Code of Federal Regula-tions for the U.S. Nuclear Regulatory Commission, the U.S.

Department of Transportation, and other appropriate federal The Radiation Center has a facility for the repair and calibra-tion of essentially all types of radiation monitoring instru-agencies, plus regulations of various state regulatory agencies are also available at the Center. **

mentation. This includes instruments for the detection and measurement of alpha, beta, gamma, and neutron radiation. The Radiation Center videotape library has over one hundred It encompasses both high range instruments for measuring tapes on nuclear engineering, radiation protection, and radio-logical emergency response topics. In addition, the Radiation

~ Annual Report

    • FACILITI ES
    • Center uses videotapes for most of the technical orientations which are required for personnel working with radiation and
    • radioactive materials. These tapes are reproduced, recorded, and edited by Radiation Center staff, using the Center's video-tape equipment and the facilities of the OSU Communication
    • Media Center.

The Radiation Center library is used mainly to provide refer-

    • ence material on an as-needed basis. It receives extensive use during the academic year. In addition, the orientation video-tapes are used intensively during the beginning of each term and periodically thereafter.
    • Table 111.1 Gammacell 220 6°Co lrradiator Use
    • Purpose of Irradiation Samples Dose Range Number of Use Time
    • mouse diet, nanofibers, (rads) Irradiations (hours)

Sterilization soil, water, cow serum , l.5xl0 6 to 5.0xl06 46 429.95 chitosan

    • Material Evaluation chemicals 5.0xl0 7 to 5.x l0 7 2 251.20 Botanical Studies potatoes 5.0xl02 to 6.0xl0 3 7 .05
    • Dosimeter Analysis alanine dosimeter 2.0xl0 5 to 2.0xl0 5 1 .6
    • Totals 56 681.80
    • 2019-2020 @

FACILITIES **

'Table 111~2 Stud~nt Enr~llment in <:ci.urses.Which ar_~{iaug~t or

' *J: ,r

.* Partially Taught at t'he.Radiation Ce-nter . . * , -

I*_

[ Course# CREPIT COURSE TITLE .Suµmier Fall .Wmtei: Spring 1 Q0.19 ,2019 202(>' * '20_2Q 'i

,, ):ntroouction to Nucieai- ~gD?.eering and Radiation _

2 :42

  • ,, Health ~hys'ics ..
  • L *
  • _

-* .. "' 'Introduction.to Nuclear-Engineering and)l~di11,tfon **

1NSE Ir5:

Health Physics'. ; *. ,: *, * * ' * ,* ~ 481 I '

  • 4  ! Nu~lear and Radiation Physics I' "

lNSE235 4 Nuclear and Radi;µion Physfos II*.:

Nuclear Radiation Detection,& lnstruJ\lentatic,m '._

Intro µ> ~ermal Fluids ** , **

\ttsE 312

,.. 4* Thermo,dynamics , ' "

Societal Asp~ts _of Nuclear technoldgy:' .* 84:,. i

)~SE*33i 4 In~ to Fluid.Mechanics: .. ..

INSE233 :, _

,, 4 .HeaJ: Transfer ,.

Mathematical.mt'ltho¢;. for Np.lR_H];> ;_

8 2 31*

,, 3,6 :_ 1 **

INSFJMP 40li501/601 tNSFJMP 405/505/605 .

'i-16 : Research " 6,

" 3 4 **

INSBRHP/MP 1 Proj~ts I * ..

, Nuclear Engineering Seminar:.*

' 47 5

52,. '

1407/507/607

  • Interns~p  :

.. 1 **

iNSE 451/551

4 2 NJ.Jcfear Rules and Regu]µti0ns Neutronic Am).lysis,

'Neutr:onic Analy~is I

32 34* .I f

3 Reactor ~ o r Training I:
  • 9
3. . R~actor Operatof *Training II 5 INSE 457/557***

[NsE* 467 /567 fNsE 667.,

.:: 3 4

. *Nuclear Reactor Lab'.

Nuclear Reactor ThermalHydrai,illcs 34 34 **,'

, .4 . Nuclear Reactor Therm.al Hydraulics '

!NSE 435;535 3

'Extenw Do_sketiy & Radia#on Shielding :

...  : 37 3 Appij.ed Jbermal Hydraulics * ..

I

' *29 C

tMm473/57i 3 Ni.icleai R,eacyQr Syst~ Analysis  :

@ Annual ~eport

    • FACILITIES
    • . Table ,.1.2 (cohtlr_i.ued) *
      • I '\

. Student Eriro.llinent in Co~rs~s Whic*h are Tau*ght or

. II_ly t aug htatt e a 1ation enter

    • I 1*

i Part1a Nuinber of Students: **

I - **

I

  • '* Swnmer Fall. :wmter Spring:

Course# CREDIT COURSE TITLE 1*

l

!NSE 4°74/574 4 *.

Nuclear System* Design I

  • . 2019 '*

.~019' 2020 - ~020 I

. ,/

'" 37

.. .. I Nvd~- System Design II lNSE 475/575 4 36 I

l-4 ..

\

NSE479* ..

1 tndividual De;ign*Pr~ject  : .. , '  ;

I .' .. '

[NSE 481* 4 Radiation Protection  : ' 38 *. I JNSE:582*: 4- Applied Radiatio? Saft:ty .. "

INsE.483/583 4*

- ~iation Biology  : .. \ *,*  ; ., 2,

\

I' INSE 488/5_88~

I

.3 Radioecoiogy .. .,  ; 3, ,,

iNS_E 499/599.

  • Nuclear.Fuels 7'
    • I lt:rSE 599*

INsE~59P.

j 4'

Nonproliferation Internal Dosimetry *

\NSFJMP 503/603~ .:,  : 1 . Th~is ,'31 53; 4i., 41 '

[NSE 516* .4 Radiochemistry 4 iNSE;519 .. .. - - ~iochemical AJ).lllysis . .. 9' l~s.E 526 3 Nwµ¢qil Methcx;ls for Erigiheeritjg Analysis

. 7 j

I I

    • INSE/MI>531 1

' INSE/MP

. .'536*

jNSEIRHP.537 *-

J 3*

3 Nuclear Physics for Engineers and"Scientists Advanced Radiatiqn Detection & M~ent Digital Spectrometer Tu?sign:- .

25 I

i 13

~

j *Diagnostic :Imaging Physics  :

1~541.'.

jNSE.550* ' ~ C Naclear Medici!le. .. ) " " .

    • ~ '  :

IN:SE 553 3 Advanced-Nuclear Reactor Physics  ;

15
MP563 ' 4 Applie'dMedical Physics*  :

.. ~

/NSE 468/568; *3 Nuclear R~tor*Safety " ~ '

jNSFJMP599

  • Special Topi9>  : ,.  : ,. 6  :

I ,. ,*.

ICcrnrse*From :Other osu _i;>ep,~rtm~nts

      • jCH 233* 5 General_ Chemistry *'*  : ..  : .-'51 J

630 *:

    • !CH233H*

jCH462~

5 3

Honors General, Chemistry Experimental Chemistry II Laboratory

'*. 18 "

28 I

fE~GR 111* 3 Engineering Orientation 167. .. I

~ f '

f 1

I ENGR212H* ' '. 3 Honors Engineering .. '

I*

.. 1 I

)ST Spiczal Topics :l

    • I* OSI'R used occasionally Jo,: demonstration qndlor experiments , , I L* *..

I ,

OSTR used avily ~ '. .

he. ' ** ' '.

,I I

2019-2020 @

Reacto r **

Operating Statistics B-1 Activation Analysis of Stone Meteorites, Other Mete-orites, and Terrestrial Rocks.

During the operating period between July 1; 2019 and June 30, 2020, the reactor produced 1,187 MWH of thermal power during its 1,243 critical hours.

B-2 Measurements of Cd Ratios of Mn, In, and Au in Thermal Column. **

B-4 B-5 Flux Mapping.

In-core Irradiation of Foils for Neutron Spectral Mea- **

Experiments Performed During the current reporting period there were 5 approved surements.

B Measurements of Neutron Spectra in*External Irradia- **

reactor experiments available for use in reactor-related pro- tion Facilities.

grams. They are: :S:.7 Measurements of Gamma Doses in External Irradia-tion Facilities.

  • A-1 Normal 1RIGA Operation (No Sample Irradiation).

B-8 Isotope Production.

B-3 Irradiation of Materials in the Standard OSTR Ir-B-9 Neutron Radiography.

radiation Facilities.

B-29 Reactivity Worth ofFuel.

B-10 B-11 Neutron Diffraction.

Irradiation of Materials Involving Specific Quantities **

B-31 B-36 1RIGA Flux Mapping Irradiation of fissionable materials in the OSTR.

of Uranium and Thorium in Standard OSTR Irradia-tion Facilities. (Discontinued Feb. 28th, 2018)

B-12 Exploratory Experiments. (Discontinued Feb. 28th, Of these available experiments, four were used during the 2018) reporting period Table IV.4 provides information related to the B-13 This experiment number was changed to A-7.

frequency of use and the general purpose of their use.

Inactive Experiments Presently 39 experiments are in the inactive file. This con-B-14 B-15 B-16 Detection of Chemically Bound Neutrons.

This experiment number was changed to C-1.

Production and Preparation of 18F.

sists of experiments which have been performed in the past and may be reactivated. Many of these experiments are now performed under the more general experiments listed in the B-17 B-18 Fission Fragment Gamma Ray* Angular Correlations.

A Study of Delayed Status (n, y) Produced Nudei.

previous section. The following list identifies these inactive experiments.

B-19 B"-20 Instrument Timing via Light Triggering.

Sinusoidal Pile Oscillator. **

A-2 Measurement of Reactor Power Level via Mn Activa-tion.

B-21 B-22 Beam Port #3 Neutron Radiography Facility.

Water Flow Measurements Through TRlGA Core. **

A-3 Measurement of Cd Ratios for Mn, In, and Au in B-23 Studies Using TRlGA Thermal Column. (Discontin-Rotating Rack.

  • ued Feb. 28th, 2018)

A-4 Neutron Flux Measurements in 1RIGA.

B-24 General Neutron Radiography.

A-5 Copper Wrre Irradiation.

B-25 Neutron Flux Monitors.

A-6 In-core Irradiation ofLiF Crystals.

B-26 Fast Neutron Spectrum Generator.

A-7 Investigation oflRIGA's Reactor Bath Water Tem-B-27 Neutron Flux Determination Adjacent to the OSTR perature Coefficient and High Power Level Power Core.

Fluctuation.

B-28 Gamma Scan of Sodium (TED) Capsule.

~ Annual Report

    • REACTOR
    • B-30 NAA of Jet, Diesel, and Furnace Fuels . 19-11 Revisions to OSTROPs in Support of Wide Range Channel B-32 Argon Production Facility.

Updated sections ofOSTROPs 1, 2, 4, 5, 9, and 15 that are affected by B-33 Irradiation ofCombustlble Liquids in LS. (Discon- the replacement of the log-linear wide range channel.

tinued Feb. 28th, 2018).

    • B-34 Irradiation of Enriched Uranium in the Neutron Ra-diogTaP.hy Facility. (Discontinued Feb. 28th, 2018) .

19-12 Further Revisions to OSTROPs in Support of Wide Range Channel Additional updates to OSTROPs 2, 4, 5, 15, and* 31, including sections

    • B-35 Irradiation of Fissile Materials in the Prompt Gamma Neutron Activation Analysis (PGNAA)
  • Facility. (Discontinued Feb. 28th, 2018).

affected by replacement of the log-linear wide range channel 19-13 Adjustments to Power Channels and Secondary Con-

    • C-1 Pu0 2 Transient Experiment trol System Documentation of adjustments made to new power channel electronics during installation and calibration. Added Safety and Percent Power
    • Unplanned Shutdowns Channel readouts to the console recorder. Added "Attendant" feature to the secondary control panel, which automatically turns off the cooling fwi if temperature drops*below the low alarm set point
    • There were 12 unplanned reactor shutdowns during the cur-rent reporting period. Table IV.5 details these events. 19-14 Revisions to OSTROP 1 Removed references to Period/Log test switch, which has been re-
    • Activities Pursuant to10 CFR 50~59 moved.

2~1 Changes .to Reactor Water Cooling System Documentation of adjustments made during the cooling system There was one safety evaluations performed in support of the upgrades in Fall 2018. Decreased primary flow, increased secondary reactor this ~ear. They were: flow, added 10 additional heat exchanger plates, rerouted cooling tower piping on roof.

19-01 Replacement ofIFE with Standard Fuel The Instrumented Fuel Element (# 11630) was removed from core - 2~2 Rabbit System Modification for LLNL Project location B-4 and moved to storage, and standard fuel element Added a pa.th to a new experiment analysis location on the reactor bay

    • (#11586) was moved from G-11 to B-4.

There were 13 new screens performed in support of the reac-floor.

03 Revisions to OSTROP 31

    • tor this year. They were:

Revisions to document scanning and storage procedure. Updated lists of records to be archived. Replaced annual retrievability check with an

-annual inventory.

    • 19-07 Console Changes in Support oflFE Removal Removed fuel element temperature display and SCRAM Removed detector c ~ t selector switch and pico-ammeter. Removed reactor 20-04 Revision to RCHPP 34 Updated name lists following staffing changes. Removed references to

"blue badges" for infrequent access.

20-05 Revisions to OSTROPs 23, 25, and 26 Minor updates and revisions to procedures for crane operation, reporting 19-08 Revisions to OSTROPs in Support of IFE Removal requirements, and background.investigations.

Updated sections ofOSTROPs 1, 2, 4, 5, 15, and 16 that are af-

    • fected by the removal of the IFE and other related console changes.

19-09 Revisions to OSTROPs 10 and 18 Appendix A Minor corrections and updates to the procedures for operation of Surveillance and Maintenance Non:..Routine Maintenance

    • experimental procedures and for irradiati,on request approval 19-10 New Wide Range Log-Linear Channel July 2019
    • Allowed installation of a new wide range channel that provides fis-
  • Removed the Instrumented Fuel Element from the core.

sion chamber readouts for the log, linear, and period channels.

  • Removed the fuel temperature channel, detector current selector switch, and picoammeter from the console .
    • 2019-2020 @

REACTOR **

September 2019 February 2020 Replaced pre-demineralizer water filter. Repaired secondary pump after an electrical short.

Installed new wide-range power channel in the console. Cleaned and adjusted Neutron Radiography Facility door limit switch.

Replaced a fai led diaphragm in ventilation supply fan control damper March 2020 October 2019 Adjusted wiring on the fission chamber to minimize noi se Cleaned several rotating rack positions with Simple Green in order to remove pieces of a stuck sample.

when shut down and at low powers.

June 2020 **

Replaced demineralizer resin , pre-resin filter, and makeup water filter.

Repaired an electrical short on the stack pump.

Replaced nitrogen purge line. **

December 2019 Added Safety and Percent Power Channel readings to the console recorder.

@ Annual Report

    • REACTOR
    • Table IV.1 Present OSTR Operating Statistics -
    • i Operational Data -For LEU Core Annual Values-Cumulative Values I

(2019/2020) .j

', I I  :

! I I

MWH of energy produced 1,187 15,449 i " ' ' *)

I MWD of energy IJ!Oduced 49.4 643.7 I I Grams ~SU used- 69 883 i

I I

!~umber offµe,l eleme~ts added to(+) or removed(-) fr~m I -1 91

! the core - __ _

I

-1 I

!~um~ ofpµlses

    • 0 325 t' ,, I 1 Hours reactor critical 1,243 16,549 I
    • I'
Hours at full power (1 MW) 1,162 15,340 I
    • i Ni.i:mber of startup and shutdown checks 225 2,650 I

I

'1 I

I I I

i Number of irradiation requests processed 276 2,9~3 I I

! I I - . '

    • I Number of:amplesfrrlu!iated 2,860 24,879 I

I 2019-2020 ©

REACTOR **

I I -

Table IV.2 OSTR Use Time 'in Terms of Specific Use Categories j

I Annual Values Cumulative Values  :

OSTR Use Category (ho_urs) (hours) 1 -,

I. Teaching (departmental *and others) 9 13,758  :

I I

OSU research I
  • r** - -

1,190

' ,~4,279 I -

Off campus research " c 2,431 57,554 I " -- - '

\ _; \

, Facility time I.  ;

191

-7,748 -

Total Reactor Use Tune 3,821 103,339 Table IV.3

.OSTR Multiple.Use Time -

. Number of Users Annual Values (ho~)

~ulative Values (hours) 1 Two  : 302*

11,449 I

',Three 305 6,35~

i '

?

I I

Four 148 3,460 I  ;

!Five -

144 1,475 I

Six I

I, 72 51~  ;

i Seven "

47 174  :

I IEight o; ~o~ "

4 29' Total Multiple. U~ Tune 1,022 23,453 I '"

Annual Report

  • I REACTOR
    • Table IV.4 useofOSTR React or Ex:per1ment s I

I Experiment Research Teaching Facility Use Total

    • Number I

I

' 3 I

I A-1 0 5 8 B-3 249 4 6 259

    • I B-31 1 *o .j 4 I

B-36 5 0 0 5 I

Totai 255 7 14 276

    • Table IV.5 Unplanned Reactor Shutdowns and Scrams Type of Event Number of Occurrences Cause of Event Period SCRAM 1 Electrical interference from building construction pi:oj-ect.

1High Voltage SCRAM 1

HV SCRAM on-fission chamber during calibration of new detector.

    • ' Percent Power Channel SCRAM 1 Exceeded power during reactor startup.
    • 1
Safety Channel SCRAM
Safety Channel SCRAM 1

1 Reading spiked during operations at 1 MW.

Exceeded power during reactor startup.

    • ! Safety Channel SCRAM 1 Power fluction due to Lazy Susan loading.

1 1

Manual SCRAM 2 Scram due to Stack/CAM particulate alamis.

    • i i Manual SCRAM ' 1 Secondary pump failed to start due to electrical short.

Limit switch slow to engage when closing door and

    • : External SCRAM 3 opening shutter.
    • 2019-2020 @

)> Figure IV.1

l
l C: Monthly Surveillance and Maintenance (Sample Form)

D.l

tJ ro OS1ROP 13, Rev. LEU-8 Surveillance & Maintenance for the Month of -in the year of 20_ _

"C 0 DATE DATE REMARKS

i SURVEILLANCE & MAINTENANCE TARGET LIMITS ASFOUND NOTTO BE &

[SHADE INI)ICATES LICENSE REQUIREMENT] DATE COMPLETED EXCEEDED* INITIALS

. IDOH INCHES - .

. MAXIMUM REACTOR TANK IUGH AND LOW WATER - -

1 MOVEMENT WW IN~_

-LEVELALARMS

- . +/-3 INCHES: ANN.  :

2 .: -*BULK WATER . TEMPERATUREALARMCHECK:

. . FUNCTIONAL ' Tested*@-----L * . '

8.5xl04+/-

3A CHANNEL TEST OF STACK CAM GAS CHANNEL 8500 cpm Ann.? _cpm ~Ann.

C~L-TEST OF STACK CAM PARTICULATE 8 5xi'04+/-

_cpm Ann.

'3B Ann.?

CHANNEL, ..

.CHANNEL TEST OF REACTOR TOP CAM

- 8500 cpm 8 5xlq-4+/- _cpm' ..

3C 8500 cpm Ann.? - Ann.

- PARTICULATE CHANNEL MEASUREMENT OF.REACTOR PRIMARY -. -

4 <5 -µmho\cm ,

  • WATER CONDUCTIVITY MIN:5 NIA 5 PRIMARY WATER pH MEASUREMENT MAX:9 BULK SHIELD TANK WATER pH MIN:5 6 NIA MEASUREMENT MAX:9 FILTER 7 CHANGE LAZY SUSAN 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

>50%, Oil ok? NIA 10 EMERGENCY DIESEL GENERATOR CHECKS NIA Visual Hours Total hours/Hours 11 RABBIT SYSTEM RUN TIME NIA on current brushes -- .

12 OIL TRANSIENT ROD BRONZE BEARING WD40 NIA Hoist 13 CRANE INSPECTION Hooks NIA Rope 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 .

Figure IV.2 ..

Quarterly Surveillance and Maintenance (Sample Form) . . .

OSTROP 14, Rev. LEU-6 Surveillance & Maintenance for the 1st / 2nd / 3n1 / 4th Quarter of 20_ _

SURVEILLANCE & MAINTENANCE TARGET DATE NOTTO DATE REMARKS&

LIMITS AS FOUND (SHADE INDICATES LICENSE REQUIREMENT] DATE BE EXCEEDED* COMPLETED INITIALS 1 REACTOR OPERATION COMMITTEE (ROC) 'AUDIT QUARTERLY 2- INTERNAL AUDIT OF OSTROPS QUARTERLY 3 QUARTERLY ROC MEETING . QUARTEIµ,Y 4 ERP INSPECTIONS - QUARTERLY 5 ROTATING RACK CHECK FOR UNKNOWN SAMPLES EMPTY 6 WATER MONITOR ALARM CHECK FUNCTIONAL 7A CHECK FILTER TAPE SPEED ON STACK MONITOR l"IHR+/-0.2 7B CHECK FILTER TAPE SPEED ON CAM MONITOR l"/HR+/- 0.2 8 INCORPORATE 50.59 & ROCAS INTO DOCUMENTATION QUARTERLY 9 EMERGENCY CALL LIST QUARTERLY ARM SYSTEM ALARM CHECKS ARM 1 2 3S 3E 4 5 7 8 9 10 11 12 AUD IO FUNCTIONAL LIGHT PANEL ANN N

0 I.O

  • Date not to* be exceeded is only applicable to shaded items. It is equal to the time completed last quarter plus four months .

. I f:5N 0

)>

J Figure IV.2 (continued)
J C

QJ Quarterly Surveillance and Maintenance (Sample Form)

0 ct)

"tJ 0

OSTROP 14, Rev. LEU-6 Surveillance & Maintenance for the 1st / 2nd / 3rd / 4th Quarter of 20

l.

SURVEILLANCE & MAINTENANCE DATE REMARKS&

LIMITS ASFOUND

[SHADE INDICATES LICENSE REQUIREMENT] COMPLETED INITIALS OPERATOR NAME a) TOTAL OPERATION TIME b) DATE OF OPERATING EXERCISE REMARKS & INITIALS a) 2:4 hours: at console (RO), at console or as Rx.

Sup. (SRO) 11 b) Date Completed Operating Exercise

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

OSTROP 15, Rev. LEU-8 Surveillance & Maintenance for the 1st / 2nd Half of 20- - -

DATENOT DATE REMARKS SURVEILLANCE & MAINTENANCE TARGET COMPLETED ~

LIMITS AS FOUND TOBE

[SHADE INDICATES LICENSE REQUIREMENT] DATE EXCEEDED*

.. ' .~ .

NEUTRON SOURCE'COUNT RATE INTERLOCK 2:5 cps TRANSIENT ROD AIR INTERLOCK NOPULSE CHANNEL TESTS PULSE MODE ROD MOVEMENT INTERLOCK**

NOMO~

1 OFREACI'OR INTERLOCKS: MAXIMUM PULSE REACTMTY INSERTION LIMIT :s $225 1WO ROD WITHDRAWAL PRHOHIBIT

  • I-ONLY puum P~OHIBIT AB,OVE, i k:W 2:1 kW PREVIOUS PULSE DATA FOR COMPARION PULSE# _ _

PULSE# _ __ $._ _ __

$._ _ _ _ __ _ _ _ MW 2 TEST PULSP* _ _ _ _ _ MW CHANGE _ _ _ _"C

_ _ _ _ _ "C 3 CL~G & I,lJBRICATION OF TRANSIENT RODCARR.IER INTERNAL BARREL ...

  • .i LUBRICATION OF BALL-NlJ19RIVE ON TRANSIENT ROD. CAR,!UER:

5 LUBRICATION OF THE ROTATING RACK BEARINGS WD-40 6 CONSOLE CHECK LIST OSTROP 15.Vll 7 INVERTER MAINTENANCE See User Manwtl N 8 STANDARD CONTROL ROD MOTOR CHECKS L0-17 Bodine 011 0

\0

  • Date not to be exceeded is only applicable to shaded items. It is equal to the date last time plus 7 1/2 months.

N 0

N 0

i::

Figure IV.3~ (continued>

DJ

0 Semi-Annual Surveillance and Maintenance (Sample Form) l'D "C

nd 0

~

OSTROP 15, Rev. LEU-8 Survbillance & Maintenance for the 1 st

/ 2 Half of 20 I

DATE NOT SURVEILLANCE & MAINTENANCE TARGET DATE REMARKS&

LIMITS AS FOUND TOBE COMPLETED INITIALS

[SHADE INDICATES LICENSE REQUIREMENT] DATE EXCEEDED*

I HIGH 9 FUNCTIONAL CHECK OF HOLDUP TANK WATER LEVEL ALARMS OSTROP 15 IX FULL BRUSH INSPECTION INSPECTION OF THE PNEUMATIC TRANSFER 10 Observed SYSTEM SAMPLE INSERTION AND WITHDRAWAL msertion/wrthdrawal TIME CHECK tnne

  • Date not to be exceeded is only applicable to shaded items. It is equal to the date last time plus 7 1/2 ~onths.
    • These tests may be postponed whil~ pulsing is precluded. If it has been more than 7. 5 months since I e previous test, the test shall be performed before, resuming pulsing.

Figure IV~4 ..

Annual Surveillance and Maintenance (Sample Form)

OSTROP 16, Rev. LEU-7 Annual Surveillance and Maintenance. for 20 DATE NOT REMARKS SURVEILLANCE AND MAINTENANCE

  • AS TARGET DATE ,I LIMITS TOBE &

[SHADE INDICATES LICENSE REQUIREMENJ1 FOUND DATE COMPLETED EXCEEDED* INITIALS

1. BIENNIAL INSPECTION OF FFCRS

. OS1ROP*12.0 CONTROL RODS: 1RANS

  • 2 STANDARD CONTROL-ROD DRIVE INSPECTON OS1ROP162

TRANS SAFE SHIM" REG CONTROL ROD " $2sec SCRAM 4* WITIIDRAWAL  :

INSERTION & WID <50 sec ..

SCRAM TIMES INSERT

' ~50 sec '.

~ :LU",lo 1:ih s mspecrea. ..

FUEL ELEMENT INSPECTION FOR SELECTED 5 - ' No damage .,

ELEMENTS -1~-~- * .. nr wPll -

6 REACTOR POWER CALIBRATION OS1ROP-8 RUEL ELEMENT TEMPERATURE CHANNEL ,_

7 Per Checklist CALIBRATION CALIBRATION OF REACTOR TANK WATER TEMP

8 OSTROP 16.8 TEMPERATURE METERS
-

CONTINUOUS Particulate Monitor ..

9 AIRMONITOR - RCHPP18 CALIBRATION Gas Monitor .

1ff CAM OIIJGREASE MAINTENANCE STACK MONITOR Particulate Monitor RCHPP

.'11 CALIBRATION . , Gas Monitor . 18&26 C

12 STACK MONITOR OIIJGREASE MAINTENANCE N 13 AREA RADIATION MONITOR CALIBRATION ' RCHPP 18 0

I-"

  • Date.not be exceeded is only applicable to shaded items. It is equal to the date completed last year plus 15 months.

I.O For biennial license reanirements. it is eaual to the date comoleted last time olus 2 1/2 vears.

N 0

N 0

)>

Figure IV.4 (continued>

C: Annual Surveillance and Maintenance (Sample Form)

CJ

0 (D OSTROP 16, Rev. LEU-7 Annual Surveillance and Maintenance for 20 "C

0 DATE NOT

i SURVEILLANCE AND MAINTENANCE AS TARGET DATE REMARKS LIMITS TOBE

[SHADE INDICATES LICENSE REQUIREMENT] FOUND DATE COMPLETED &INITIALS EXCEEDED*

14 CORE EXCESS <$7.55 $

DAMPERS l 8TFLOOR -

15 REACTOR BAY VENTILATION SYSTEM SHUTDOWN TEST CLOSE IN~

4111 FLOOR SECONDS 16 CRANE INSPECTION - - - - - -

17 SNM PHYSICAL INVENTORY NIA NIA OCTOBER 18 !MATERIAL BALANCE REPORTS NIA NIA NOVEMBER CFD TRAINING  :

GOOD SAM TRAINING ERPREVIEW ERP DRILL CPR CERT FOR:

CPR CERT FOR:

EMERGENCY FIRST AID CERT FOR:

19 RESPONSE PLAN FIRST AID CERT FOR:

EVACUATION DRILL .

AUTO EVAC ANNOUNCEMENT TEST ERP EQUIPMENT INVENTORY BIENNIAL SUPPORT AGREEMENTS PSPREVIEW PSPDRILL PHYSICAL 20 SECURITY OSP/DPS 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 1/2 years .

                                                                                          • Figure IV.4 (conttnuect)

Annual Surveillance and Maintenance (Sample Form)

OSTROP 16, Rev. LElf-5 Annual Surveillance and Maintenance for 20 lJAlb NUT SURVEILLANCE AND MAINTENANCE AS TAROET DATE REMARKS LIMITS TOBE

[SHADE INDICATES LICENSE REQUIREMENT] FOUND DATE COMPLETED &INITIALS 1-<:Xl I-ii-ii Jl-<:I >* . '

21 ANNUAL REPORT .. Nov*1. - . '

  • OCTI NOVI 22 ANNUAL TEST OF.RECORD RETRIEVABILITY ANNUAL

.23 KEY INVENTORY  ; ANNlJAL ' ! . . -..

REACTOR TANK.AND CORE COMPONENT 24 NO WHITE SPOTS INSPECTION 25 EMERGENCY LIGHT LOAD TEST 26 NEUTRON RADIOGRAPHY FACILTIY INTERLOCKS 27 PGNAA FACILI1Y INTERLOCKS ANNUAL REQUALIFICATION BIENNIAL MEDICAL EVERY 6 YEARS LICENSE REACTOR OPERATOR LICENSE CONDITIONS ... WRITTEN EXPIRATION OPERATINOTEST APPLlCATION DATE EXAM DATE DATEDUE COMPLETED DATE DATE DATE DUE DATE OPERATOR NAME DUE PASSED DATEDUE PASSED DATE MAILED 28 N

0 I-"

c..o I

N 0

N 0

  • 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 Environmental Releases The annual reporting requirements in the OSTR Technical the safe use of radiation and radioactive material in the Cen-ter's teaching, research, and service activities, and in a similar Specifications state that the licensee (OSU) shall include "a summary of the nature and amount of radioactive effluents **

manner to the fulfillment of all regulatory requirements of the released or discharged to the environs beyond the effective State of Oregon, the U.S. Nuclear Regulatory Commission, control of the licensee, as measured at, or prior to, the point of and other regulatory agencies. The comprehensive nature of such release or discharge." The liquid and gaseous effluents the program is shown in Table V. I, which lists the program 's major radiation protection requirements and the performance frequency for each item.

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 .

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 Liquid Effluents Released Liquid Ejfluents Oregon State University has implemented a policy to reduce Technician, and the Radiation Center Director.

The data contained in the following sections hav nb je been the volume of radioactive liquid effluents to an absolute mini-mum. For example, water used during the ion exchanger resin **

change is now recycled as reactor makeup water. Waste water prepared to comply with the current requirements of Nuclear from Radiation Center laboratories and the OSTR is collected Regulatory Commission (NRC) Facility License No. R-106 at a holdup tank prior to release to the sanitary sewer. Liquid (Docket No. 50-243) and the Technical Specifications con-effluent are analyzed for radioactivity content at the time it tained in that license. The material has also been prepared is released to the collection point. For this reporting period, in compliance with Oregon Department of Energy Rule No.

the Radiation Center and reactor made seven liquid effluent 345-30-0 I 0, which requires an annual report of environmental effects due to research reactor operations.

releases to the sanitary sewer. All Radiation Center and reactor facility liquid effluent data pertaining to this release are con- **

Within the scope of Oregon State University 's radiation pro- tained in Table V.2.

tection program, it is standard operating policy to maintain all Liquid Waste Generated and Transferred releases of radioactivity to the unrestricted environment and Liquid waste generated from glassware and laboratory experi-all exposures to radiation and radioactive materials at levels ments is transferred by the campus Radiation Safety Office to which are consistently "as low as reasonably achievable" its waste processing facility. The annual summary of liquid (ALARA).

waste generated and transferred is contained in Table V.3.

Airborne Effluents Released Airborne effluents are discussed in terms of the gaseous com- **

ponent and the particulate component.

Gaseous Ejfluents **

Gaseous effluents from the reactor facility are mon itored by the reactor stack effluent monitor. Monitoring is continuous, i.e. , prior to, during, and after reactor operations. It is normal for the reactor facility stack effluent monitor to begin opera-tion as one of the first systems in the morning and to cease operation as one of the last systems at the end of the day. All Annual Report gaseous effluent data for this reporting period are summarized in Table V.4 . **

    • RADIATION PROTECTION
    • Particulate effluents from the reactor facility are also moni-tored by the reactor facility stack effluent monitor.

using the reactor, reactor~activated materials, or using other re~h facilities present at the Center. The individual dosim-

    • Particulate Effluents.

Evaluation of the detectable particulate radioactivity in the etry requirements for these personnel will vary with the type of research being conducted, but will generally include a quar-terly 1LD film badge and 1LD (finger) extremity dosimeters.

    • stack effluent confirmed its origin as naturally-occurring radon daughter products, within a range of approximately 3xl 0- 11

µCi/ml to 1 x lo-9 µCi/ml. This particulate radioactivity is If the possibility ofneutron exposure exists, researchers are also monitored with a track-etch/ albedo neutron dosimeter.

    • predominantly 214Pb and 21 413~ which is not associated with Facilities Services maintenance personnel are normally issued reactor operations. a gamma sensitive electronic dosimeter as their basic monitor-ing device .

There was no release of particulate effluents with a half life *

    • greater than eight days and therefore the reporting of the aver-age concentration of radioactive particulates with half lives greater than eight days is not applicable .

Students attending laboratory classes are issued quarterly XB(y) 1LD badges, 1LD (finger) extremity dosimeters, and track-etch/albedo or other.neutron dosimeters, as appropriate.

    • Solid Waste Released Data: for the radioactive material in the solid waste generated Students or small groups of students who attend a one-time lab demonstration and do n9t handle radioactive materials are
    • and transferred during this reporting period are summarized in usually issued a gamma sensitive electronic dosimeter. These
    • Table V.5 for both the reactor facility and the Radiation Center.

Solid radioactive waste is routinely transferred to OSU Radia-results are not included with the laboratory class students.

OSU police and security personnel are issued a quarterly tion Safety. Until this waste is disposed of.by the Radiation XB(y) 1LD badge to be used during their patrols of the Radia-Safety Office, it is held along with other campus radioactive tion Center and reactor facility.

waste on the University's State of Oregon radioactive materi-

    • als license . Visitors, depending on the locations visited, may be issued gamma sensitive electronic dosimeters. 6SU Radiation Center Solid radioactive waste is disposed ofby OSU Radiation policy does not normally allow people in the visitor category
    • Safety by transfer to the University's radioactive waste dis-posal vendor.

to become actively involved in the use or handling of radioac-tive materials .

    • Personnel Dose An annual summary of the radiation doses received by each of the above six groups is shown_in Table V.6. There were no personnel radiation exposures in excess of the limits in 10
    • The OSTR annual reporting requirements specify that the licensee.shall present a summary of the radiation exposure received by facility personnel and visitors. The summary in-CFR 20 or State of Oregon regulations during the reporting period. '
    • cludes all Radiation Center personnel who may* have received exposure to radiation. These personnel have been categorized Facility Survey Data into six groups: facility operating personnel, key facility research personnel, facilities services main~nance personnel, _The OSTR Technical Specifications require an annual sum*-

students in laboratqry classes, police and security personnel,- mary of the radiation levels and levels of contamination

    • and visitors .

Facility operating personnel include the reactor operations and observed during routine surveys performed at the facility. The Center's comprehensive area radiation morlitoring program encompasses the Radiation Center as well as the OS1R, and

    • health physics staff. The dosimeters used to monitor these in-dividuals include quarterly TLD badges, quarterly track-etch/

albedo neutron dosimeters, monthly 1LD (finger) extremity therefore monitoring results for both facilities are reported.

Area Radiation Dosimeters

    • dosimeters, pocket ion chambers, electronic dosimetry.

Key facility research personnel consist of Radiation Center Area monitoring dosimeters capable of integrating the radia-tion dose are located at strategic positions throughout the reactor facility and Radiati~n Center. All of these dosimeters

    • staff, faculty, and graduate* students who perform research contain at least a standard personnel-type beta-gamma film or 2019-2020

RADIATION PROTECTION **

TLD pack. In addition, for key locations in the reactor facility and for certain Radiation Center laboratories a CR-39 plas-Gamma Radiation Monitoring On-site Monitoring tic track-etch neutron detector has also been included in the monitoring package.

Monitors used in the on-site gamma environmental radiation monitoring program at the Radiation Center consist of the re-actor facility stack effluent monitor descnbed in Section V and The total dose equivalent recorded on the various reactor facil-nine environmental monitoring stations.

ity dosimeters is listed in Table V.7 and the total dose equiva-lent recorded on the Radiation Center area dosimeters is listed During this reporting peri~ each fence environmental station in Table V.8. Generally, the characters following the Monitor utilized an LiF TLD monitoring packet supplied and proc~ed Radiation Center (MRC) designator show the room number or by Mirion Technologies, Inc., Irvine, California Each packet location. contained three LiF TLDs and was exchanged quarterly for a total of 108 samples during the reporting period (9 stations Routine Radiation and Contamination Surveys x 3 TLDs per station x 4 quarters). The total number ofTLD The Centers program for routine radiation and contamination surveys consists of daily, weekly, and monthly measurements throughout the 1RIGA reactor facility and Radiation Center.

samples for the reporting period was 108. A summary of the TLD data is also shown in Table V.10. **

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 From Table V.10 it is concluded that the doses recorded by the dosimeters on the 1RIGA facility fence can be attnbuted to natural back-ground radiation, which is about 110 mrem per area at a defined frequency is desirable.

The primary purpose of the routine radiation and contamina-year for Oregon (Refs. 1, 2).

Off-site Monitoring tion survey program is to assure regularly scheduled surveil-lance over selected work areas in the reactor facility and in the The off-site gamma environmental radiation monitoring program consists of twenty monitoring stations surrounding **

Radiation Center, in order to provide current and characteristic the Radiation Center (see Figure V.1) and six stations located data on the status of radiological conditions. A second objec- within a 5 mile radius of the Radiation Center.

tive of the program is to assure frequent on-the-spot personal observations (along with recorded data), which will provide Each monitoring station is located about four feet above the advance warning of needed corrections and thereby help to ground (MRCTE 21 and MRCTE 22 are mounted on the roof ensure the safe use and handling of radiation sources and of the EPA Laboratory and National Forage Seed Laboratory, 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 respectively). These monitors are exchanged and processed quarterly, and the total number ofTLD samples during the cur-rent one-year reporting period was 240 (20 stations x 3 chips that all phases of the operational and radiation protection programs are meeting the goal of keeping radiation doses to per station per quarter x 4 quarters per year). The total number ofTLD samples for the reporting period was 240. A summary **

personnel and releases of radioactivity to the environment "as ofTLD data for the off-site monitoring stations is given in low as reasonably achievable" (ALARA). Table V.Jl.

After a review of the data in Table V.11, it is concluded that,*

The annual summary of radiation and contamination levels measured during routine facility surveys for the applicable like the dosimeters on the 1RIGA facility fence, all of the reporting period is given in Table V.9. doses recorded by the off-site dosimeters can be attnbuted to Environmental Survey Data natural background radiation, which is about 110 mrem per year for Oregon (Refs. 1, 2).

The annual reporting requirements of the OSTR Technical Specifications include "an annual summary of environmental 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 surveys performed outside the facility." each category on a annual basis. The program monitors highly unlikely radioactive material releases from either the 1RIGA **

@; Annuat Report I

    • RADIATION PROTECTION
    • reactor facility or the OSU Radiation Center, and also helps indicate the general trend of the radioactivity concentration Identification of specific radionuclides is not routinely carried out as part of this monitoring program, but would be conduct-
    • in each of the various substances sampled. See Figure V l for the locations of the sampling stations for grass (G), soil ed if unusual radioactivity levels above natural background were detected. However, from Table V 12 it can be seen (S), water (W) and rainwater (RW) samples. Most locations that the levels ofradioactivity detected were consistent with are within a 1000 foot radius of the reactor facility and the naturally occurring radioactivity and comparable to values Radiation Center. In general , samples are collected over a reported in previous years .
    • local area having a radius of about ten feet at the positions indicated in Figure V 1.

Radioactive Materials Shipments There are a total of 22 sampling locations : four soil loca-A summary of the radioactive material shipments originating tions, four water locations (when water is available), and from the TRIG A reactor facility, NRC license R-106, is shown fourteen vegetation locations.

in Table V 14. A similar summary for shipments originating

    • The annual concentration of total net beta radioactivity (mi-nus tritium) for samples collected at each environmental soil, from the Radiation Center 's State of Oregon radioactive ma-terials license ORE 90005 is shown in Table Vl5. A summary
    • water, and vegetation sampling location (sampling station) is of radioactive material shipments exported under Nuclear listed in Table V 12. Calculation of the total net beta disinte- Regulatory Commission general license 10 CFR 110.23 is gration rate incorporates subtraction of only the counting sys- shown in Table V 16.
    • tem back-ground from the gross beta counting rate, followed by application of an appropriate counting system efficiency.

References

    • 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 I. U. S. Environmental Protection Agency, "Estimates of Ionizing Radiation Doses in the United States,

    • the LLD were averaged in at the corresponding LLD con-centration. Table V 13 gives the concentration and the range 1960-2000," ORP/CSD 72- 1, Office of Radiation Programs, Rockville, Maryland (1972).

of values for each sample category for the current reporting

2. U. S. Environmental Protection Agency, " Radiologi -

period.

cal Quality of the Environment in the United States, As used in this report, the LLD has been defined as the 1977," EPA 520/ 1-77-009, Office of Radiation Pro-amount or concentration of radioactive material (in terms of grams; Washington , D.C. 20460 ( 1977).

µCi per unit volume or unit mass) in a representative sample,

  • which has a 95% probability of being detected .
  • 2019 - 2020 @

RADIATION PROTECTION **

TableV.1 **

Radiation Protection Program Requirements and Frequencies Frequency Radiation Protection Requirement Daily/Weekly/Monthly [Perform Routing area radiation/contamination monitoring

  • Collect and analyze TRI GA primary, secondary, and make-up water.

Exchange personnel dosimeters, and review exposure reports.

Monthly Inspect laboratories.

Calculate previous month's gaseous effluent discharg-e.

Process and reyord solid waste and liquid effluent discharges.

Prepare and record radioactive material shipments.

Survey and record incoming radioactive materials receipts.

AsRequired Perform and record special radiation surveys.

Perform tb:Yroid 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. **

Quarterly Collect and analyze samples from .r:eactor 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 ~ e n t s and personnel pocket ion chambers.

Calibrate reactor stackeffluent monitor, continuous air monitors, remote area radiation monitors, and air samplers.

Measure face air velocity in laboratory hoods and exchange dust-stop filters and HEPA filters as necessary. *

  • Annual Inventory and inspect Radiation Center emergency equipment.

Conduct facility radiation survey of the roco irradiators.

Conduct personnel dosimeter training.

Update decommissioning logbook.

Collect and process environmental soil, water, and vegetation samples.

@ Annual Report

TableV.2

~ a a t

. Moa:,thly Summary of Liquid J;ffluent Rel.ease to the :sanitary Sewer1~1

! "- - ..- . - I

. Specrfic Activity for -Average

- - I

. Total Quantity of Percent of Applicable

Total _Each Detectable Radio- Total Volume, _ 1 bate of Each.Detectable- .- Concentration Monthly Average I

.. *Discharge*

  • Quan;tity of Detectable _- nuclide in of Liquid E~u~nt; Radionuclide OfReleaseg Concentration for I

~ioacti:vi~ Radionuclide-in

  • the Waste, Where the Released Includm~

I i

(Month and Year)

~e1easec1** - the waste Release Concentration

- Released in the Radioactive Material* Released Radioactive Waste at the Point of Release Material

  • Diluent I' I

I (<;:uries) Was>l x 10-7 1 (gal). I I - - (Curies) - (µCimI- ) (o/;)<2> ,i

'. , ( µCi m1- 1

)

I I H-<3,,' 4.2lxl0*5 _ H-3, 2.70xJ0*7 _* 11;-3, 0.0027 I Sept 2019* 4.28xl0- 5 H-3,,Co-6~ H-_3,. 2'. 70xl 0- 7

,- 41,739 I Co-60, _6.96xl0* 7 Co,-60, 4.46x10*~- Co-60, 0.00009 I

1. Annual Total  : -* -

5

.II H-3, 4.21xl0* - .'H-3, 2.70xl0- 7 H-3, 0.0027 I for Radiation 4;28xl0 *H-3 co:.-60 f

H-3, 2.70xl0- 7

  • Co-60, 6.96:xl0* 7 -c_o-60, 4.46xlo-9 Co-60, 0.00009.

4l,739 I I

! Center - .  :

j .-  :

,,,, ,_, ** .. , '"' .. 4 b) t2)

The OSU operational policy' is to subtraci: only detector backgro~d from the water analysis data and not'background radioactivity in the Corvallis city -

  • Based on val~es listed in 10 CFR 20,:Appendix B*to.20'.1001-1024-01, Tabie 3,:which are applicable to *~er disposal., . -. . ,

I , ' -  : - , ' - - * , -

=tJ

-C

~

0 z

N "'tJ 0  :=tJ

~

I.O I

_N 0 m N. C')

0 I

z

RADIATION PROTECTION **

Table,V~3, I

' ,. Annua ummaryof L"1qu1*ct'Wast e Genera t e cl an d Tran sfer~e

- I' 'd

'0 Dates,ofWaste Pickup, I . Volume,ofLiqµid' Detectable ,Total Quantity* of

  • fot Transfer to the II Origin of Liquid Wasw Packagel )

1

,Radionuclides Radioactivity in the I Waste (gallons)* - in the Waste q Waste (Curies)

Waste ~ssing I I

,,,  : ~acility:

II '

I H-3, c;r-51, Mn-54, Co-60, I

'fRIGA 22,5 '7.9lx10*5 ,,

6/1/2020:

l INa-24, Sb-124, Fe-59; Co~58

.. Co-60~ .C.s-134, Cf-249, ,,  :

" Pu-~39;C-J37, U.:238, ., 8/8/2019,

  • Radiation Center

-9.63 U-235, Np-'237, H-3, .C-14, 3.Six*10~s:

µiliorat~ries 6/1/2020

- Sr-9.0, Ba-133;Cm-248, .

Bk-249, Pu-242 TOTAL 32.13 See above* ,,-

'1.15:dO-C (1) OSTR and Radiation Center liquid waste is picked up by the Radiation Safety Office for transfer tb its waste pro'cessirig facility for filial packaging., . - , *, . . ,- . . - ,_ . '. ..

Annual Report

    • RADIATION PROTECTION
    • Table.V.4
    • I I

I:

Mont hiIY TRIGA Reactor Gaseous Waste Disc

. hatges an d Analysis Estimated I

  • Fraction of the Technical I

I

    • I I

f Month Total Estimated - Estimated Quantity of A.ctivity Total Argon-41 Atmospheric Diluted Concentration of AJ:gon-41 *af Point of Specification Annual Average I

I

    • I: Argon-41
  • Released (Curies) Released< 1> (Curies) Release .

Concentration Liniit (%) I I (µCi/cc) i

.. 2'.35x10-' "

    • I July 3.01 3.01 5.87-2.UxlU-'

I August . 2.85 2.85 ,5.56

  • . l.77xl0- 7 I September 2.20 2.20 4.44 I October* 3.26 3.26 2.55x10- 1 6.37 -,

' - 2.05xl0-7 :5.l2.

l. November .. *2.54 2.54  !

I December. 4.11- 4.ll. .3.2lxllf' 8.04 '

I I January 2'.84 2.84: *2.22x*l u-' 5.55

)

    • , 2.81 2.81 2.45xl0-7 6.12 i .. :Febl"l4UY ,.

March 2.44 2.44 . - l.9lxl0*' 4.77 i

! *: April 0.79

  • 0.79' 6.35xl0-11 1.59*
    • I I

May June

. 0.68 1.58.

  • 0.68 1.58 5.33xl0-s
  • l.27x.10- 7 1:33 3.19 I*

TOTAL

('J.9-',20) 29.11 29,.11 l .93xl 0-7(2) 4.83(l) i

    • (1) Routine ~ a spectroscopy analysis of the gaseous radioactivity in the OSTR stack discharge indicateq the only detectable radionuclide

!: was argon-41. '

(2)

  • Annual Average. * *
    • Table V.5
    • I Annua*IS ummaryof S01 l"dWast e Genera t e d an dTrans ferr ed

.I

    • I I
  • Orjgin of
  • Volume of SolidW~e .. Detectable Radionuclides Total Quantity qf Radioactivity Dates of Waste Pickup II for Tnwsfer'to the OSU
  • Waste Processing
  • I I

'  : . 'in Solid Waste .

Solid Waste PackagedoJ

.  ; in the Waste

!i (Cubic Feet) (Curies) F_~cility a I

! . ' 8/8/2019 TRIGA Co-60, Se-75, Zn-65, Sc-46, Cr-51,

  • I Reactor* 42 Mn-54, Fe-59, Co,.58, Sb-124, - l.84xl0 4 . 11/5/2019:

I I I

I I,

Facility ~-239, Eu-154, H-3, Na-24 .6/1/2020 I I

Cs-134, Np-237, Pu-239, U-238 1

  • 8/8/2019 Rad1;uion

i4*

,' U-235, Cf-249, Sr-90, Eu-152,

  • i Center 3.34xlo-4 '11/5/2019

. Eu-154,.Bk-249, Pu-242, Am-241, I Laboratories 6/1/2020  !

  • Am-243, Th-232, Natural U I; I I

TOTAL.* 66* See Above 5.18xlo-4 ,,

I I ,,

(1) OSTR and Radiation Center lab waste is picked up by OSU Radiation Safety for transfer to its waste processing facility for final.packaging.'.

2019- 2020

RADIATION PROTECTION **

Table V.6 **

Annual Summary of Personnel Radiation Doses Received Average Annual Greatest Individual Total Person-mrem Dose<1> Dose<1i for the Group0>

Personnel Group*

Whole Body Extremities Whole Body (mrem) (mrem) (mrem)

Extremities (mrem)

Whole Body (mrem)

Extremities (mrem)

Facility Operating 111 227 305 1185 891 1,812 **

Personnel

' - Key Facility Research Personnel 17 10 259 80 259 80

Facilities Services Maintenance Personnel 0 NIA 0 NIA 0 NIA **

Laboratory Class Students 4 31 280 992 589 1,181 **

Campus Police and 0 NIA 0 NIA 0 NIA Security Personnel Visitors <1 NIA 11 NIA 208 NIA (l) "NIA" indicates that there was no extremity monitoring conducted or required for the group,

~ Annual Report

    • RADIATION PROTECTION
    • TableV.7
    • I

. Total Dose Equivalent Recorded on Area Dosimeters Located Within the TRIGA *Reactor Faci Iity  :

    • Monitor TRIGA Reactor Facility Location Total Recorded Dose Equivalent<1X2l I

I.D. XB(y), Neutron

(See Figure V.1)

I (mrem) (mrem)

I MRC1NE D104: North Badge East Wall 165 ND

    • MRCTSE D104: South Badge East Wall

-South Badge West Wall 95 343 ND ND MRCTSW D104:

MRCTNW D104: North Badge West Wall 343 ND I
MRCTWN D104: West Badge North Wall 569 ND

,MRCTEN D104: &st B_adge North Wall 228 ND

    • 'MRCTES MRCTWS D104:

D104:

East Badge South Wall West Badge South Wall 1,201 648 ND ND MRCTIOP D104: Reactor Top Badge 1,077 ND MRCTHXS D104A: South Badge HX Room 603 ND

  • .MRCTHXW D104A: West Badge HX Room 301 ND
    • . MRCD-302

! MRCD-302A D302: Reactor Control Room D302A: Reactor Supervisor's Office, 462 77 ND ND

    • MRCBPl iMRCBP2 D104: Beam Port Number 1 D104: Beam Port Number 2 528 175 ND ND
    • I MRCBP3 D104: Beam Port Number 3 .

1,122 ND

    • :MRCBP4 D104: Beam Port Number 4 1,120 ND_
(l) The total recorded dose equivalent values do not include natural background contribution and reflect the summation of the results of
    • fo!lf 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. "NIA" indicates that there was no neutron monitor at that location.

' (2 ) These dose equivalent values do not represent radiation exposure through an exterior wall directly into an unrestricted area.

    • 2019-2020 @

RADIATION PROTECTION **

TableV.8 Total Dose Equivalent Recorded on Area Dosimeters Located Within the Radiation Center **

Monitor I.D.

Radiation Center Facility Location Total Recorded Dose Equivalent<!)

Xfi(y) Neutron (See Figure V.l) .

(mrem) (mrem).

MRCAlO0 AlO0: Receptionist's Office 0 ND

. MRCBRF

  • .MRCA120 Al02H: Front Personnel Dosimetry Storage Rack Al20: Stock Room 23 0

ND ND **

MRCA120A

. MRCA126 Al20A: NAA Temporary Storage Al26: Radioisotope Research Laboratory 91 154 ND ND **

  • MRCCO-60

. MRCAB0 Al28:

ABO:

60 Co Irradiator Room Shielded-Exposure Room 769 0

ND ND **

, MRCAB2 MR.CABS Al32:

ABS:

TLD Equipme~t Room Health Physics Laboratory 0

0 ND ND **

. MRCA146

, MRCBlO0 Al46:

Bl00:

Gamma Analyzer Room (Storage Cave)

Gamma Analyzer Room (Storage Cave) 0 167 ND ND **

MRCB114

  • Bll4: Lab (226Ra Storage Facility) 14 ND

'MRCB119~1 B119: Source Storage Room 76 20 MRCB119-2 MRCB119A Bll9: Source Storage Room Bll9A: Sealed Source Storage Room 609 2,688 57 440 MRCB120 MRCB122-2 Bl20:

Bl22:

Instrument Calibration Facility Radioisotope Hood 12 33 ND ND MRCB122-3 MRCB124-l Bl22:

Bl24:

Radioisotope Research Laboratory Radioisotope Research Laboratory (Hood) 37 277 ND ND MRCB124.2 Bl24: Radioisotope Research Laboratory 0 ND

, MRCB124-6 Bl24: Radioisotope Research Laboratory 0 ND [

MRCB128 Bl28: Instrument Repair Shop 0 ND

  • MRCBB6 MRCClO0 BB6 ClO0:

Gamma Analyzer Room Radiation Center Director's Office 0

0 ND 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 dos!Illeters or four quarterly fast neutron dosimeters for each location. A total dose equiva-

  • lent ofND" 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. "NIA" indicates that there was no neutron monitor at that location.

@ Annual Report

    • RADIATION PROTECTION
    • Table V.8 ccont1nued)
    • Total Dose Equivalent Recorded on Area Dosimeters Located Within the Radiation Center
    • Monitor

' ' Radiation Center Facility Location Total Recorded Dose Equivalent< 1l I.D .

(See Figure V.l) XB(y)

(mrem)

Neutron (mrem)

    • . MRCC106A

, MRCC106B Cl06A: Office Cl06B: Custodian Supply Storage 0

0 ND ND  :

    • MRCC106-H

.MRCC118 C 106H: East Loading Dock Cll8: Radiochemistry Laboratory ' 0 0 ND ND

    • MRCC120
  • MRCFlO0 Cl20:

Fl00:

Student Counting Laboratory APEX Facility 0

0 ND ND

    • MRCF102 MRCB125N Fl02:

Bl2s':

APEX Control Room Gamma Analyzer Room (Storage Cave) 0 0

ND ND

    • MRCN125S Bl25: Gamma Analyzer Room 0 ND
    • ND MRCC124 Cl24: Classroom 0 MRCC130 Cl30: Radioisotope Laboratory (Hood) 0 ND
    • I MRCDlO0
MRCD102 DI00

Dl02:

React.or Support Laboratory Pneumatic Transfer Terminal Laboratory 0

231 ND ND I

1 MRCD102-H DI 02H: 1st Floor Corridor at D 102 25 ND

! MRCD106-H Dl06H: 1st Floor Corridor at D106 346 NP

    • 'MRCD200 I

MRCD202 D200:

D202:

Reactor Administrator's Office Senior Health Physicist's Office 134 252 ND ND

    • I
MRCBRR
  • , D200H: Rear Personnel Dosimetry Storage Rack 0 ND
MRCP204 D204: Health Physicist Office 334 ND  :
MRCATHRL Fl04
* ATHRL 0 ND.

I I

MRCD300

! MRCA!.44 D300:

Al44:

3rd Floor Conference Room Radioisotope Research Laboratory  !

149 0

ND ND

    • : (1) The total recorded dose equivalent values do not include natural background contribution and, reflect the summation of the I

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 mrern or that each of the fast neutron dosimeters was less than the vendor's threshold of 10 mrern. NIA" indicates that there was no neutron monitor at that location .

    • 2019-2020 @

RADIATION PROTECTION **

TableV.9 **

Annual Summary of Radiation and Contamination Levels Observed Within the Reactor Facility and Radiation Center **

During Routine Radiation Surveys Whole Body Radiation Levels Contamination Levels(!)

Accessible Location (See Figure V.1)

Average (mrem/hr)

\ Maximum Average (dpm/cm2)

\ Maximum TRIGA Reactor Facility:

Reactor Top (D104) 3.07 120 <500' 1,290 Reactor 2nd Deck Area (D 104) 10.58 67 <500 <500 Reactor Bay SW (D104) <1 12 <500 <500 Reactor Bay NW (D104) <1 21 <500 <500

Reactor Bay NE (D104) <1 15 <500 <500 Reactor Bay SE (D104) <1 22 <500 1,667 Class Experiments (D104, D302) <1 <1 <500 <500 Demineralizer Tank & Make Up Water System

<1 9 <500 <500 (D104A)

Particulate Filter--Outside Shielding (Di 04A) <1 1.3 <500 <500 Radiation Center.

NAA Counting Rooms (A146, Bl00) <1 2.4 <500 <500 **

Health Physics Laboratory (Al38) 60

  • Co lrradiator Room and Calibration Rooms

<1

<1 l.l 16

<500

<500

<500

<500

'(A128, B120,A130)

,Radiati9n Research Labs (A126, A136) 2*

<1 <500 <500

,(BIOS, Bl14, B122, B124, Cl26, C130, A144)

I Radioactive Source Storage (Bl19, B119A, A120A, A132A)

<1 8 <500 <500 **

I

_Student Chemistry Laboratory (Cl 18)

Student Counting Laboratory (C120)

<1

<1

<l

<1

<500

<500

<500

<500 **

Operations Counting Room (B136, B125)

Pneumatic Transfer Laboratory (D102)

<1

<1

<1 9

<500

<500

<500

<500 **

RX support Room (Dl00) -

<l . 2.9

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

<500 <500 Annual Report

    • RADIATION PROTECTION
    • Table V.10
    • Total Dose Equivalent at the TRIGA Reactor Facility Fence 'I Total Recorded Dose Equivalent

!I Fence (Including Background)

Environmental Monitoring Station  :

II Based on Mirion TLDs< 1* 2> '

(See Figure V.1)

I I

I (mrem)

I MRCFE-1 92+/-4 I , .

I. MRCFE-2 83 +/- 3 i  :

MRCFE-3 80+/-4 I

I I ., MRCFE-4 84+/-4 I

,. I I

I MRCFE-5

  • 88 +/- 3 '

I MRCFE-6 87+/-3

    • I.

i I

MRCFE-7 .. 84+/-4

    • I 1*'

MRCFE-8 MRCFE-9 85 +/-2 84+/-3

(1) Average Corvallis area natural background using Mirian TLDs totals 79 +/- 21 mrem for the same period .

~ (2) +/- values represent the_ standard deviation of the total value at the 95% confidence level.

    • <l
    • 2019-2020

RADIATION PROTECTION **

Table V.11 **

Total Dose Equivalent at the Off-Site Gamma Radiation M om*tormg . Stat"ions **

Off-Site Radiation Monitoring Station Total Recorded Dose Equivalent (Including Background) **

(See Figure V.1)

Based on Mirion TLDso, 2>

(mrem)

.MRCTE-2 MRCTE-3 89+/-3 60+/- 5 **

MRCTE-4 MRCTE-5 80+/- 3

. 86+/- 3 MRCTE-6 87+/-3, MRCTE-7 65 +/-4 MRCTE-8 73+/-4 MRCTE-9 MRCTE-10 91 +/-4 78+/-3 **

MRCTE-12 MRCTE-13 96+/-3 85 +/- 3 **

I MRCTE-14 MRCTE-15 83 +/-4 78 +/- 5 **

MRCTE-16 MRCTE-17 85 +/-4 81 +/- 3 MRCTE-18 79+/-4 MRCTE-19 63 +/-2 MRCTE-20 83 +/- 2 MRCTE-21 MRCTE-22 78+/-3 71 +/- 18 **

( 1) Average Corvallis area natural background using Mirion TLDs totals 79 +/- 21 mrem for the same period.

(2) +/- values represent the standard deviation of the total value at the 95% confidence level

@ Annual Report

    • RADIATION PROTECTION
    • Table V.12
    • Annual Average Concentration of the Total Net Beta Radioactivity-(minus 3 H) for Environmental Soil, Water,
    • : Sample Sample and Vegetation Samples
  • Annual Average Concentration
    • Location
(See Fig. V.1)

Type Of the Total Net Beta (Minus 3:EI)

Radioactivity< 1>

LLD Reporting Units 1-W Water 4.86xro- 8(2) 4.86xl0* 8 µCim1-l 4-W *water no sample no sample µCi m1-l

' 8 11-W Water 4.86x10-SC2l 4.86xl0- µCi m1-l I

7

! 19-RW Water l.05x10- ?<2l l.05xl0* µCi m1- 1 I

5 -5 3-S Soil 7.17xl0- +/- l.52xl0 8.49xl0-5 µCi g- 1 of dry soil 5-S Soil 6.55x10- 6(2) 6.55x10-6 µCi g-1 of dry soil 20-S 21-S Soil Soil

  • l.63xl0-5(2) 5 3 .42x 10- (ll l.63x10 3.42xl0

-5

-5

µCi g- l of dry soil

µCi g-l of dry soil

    • 2-G 6-G
  • Grass Grass 4

3.13xl0- +/- 4.64xl0*

4 5.76xl0- +/- l.47x10-4 5

8.49xl0*

3.02xlo-4 5

µCi g- 1 of dry ash

µCi g- 1 of dry ash

    • 7-G Grass l.87xl0-4 +/- 3.88x10-5 5

7.69xl0-5 7.69xl0-5

µCi g- 1 of dry ash

µCi g- 1 of dry ash.

! 8-G Grass 2.72xl0-4 +/- 4.16x10-9-G Grass 3.30xl0-4 +/- 4.46xl0*

5 7.94xl0-5 . µCi g- 1 of dry ash

    • 10-G Grass l.74xl0-4 +/- 3.55xl0*

5 7.03xl0-5* µCi g- 1 of dry ash I

12-G Grass* 2.68xl0-4 +/- 3.87x10*

5 7.03xl0-5 µCi g- 1 of dry ash I

13-G 14-G Grass Grass 2.97xl0-4 +/- 3.65xl0*

5 8.77xl0* +/- 3.5lxl0-5 5

6.3 lx10* 5

'7.69xl0" 5

µCi g- 1 of dry ash

µCi g- 1 of dry ash  :

    • i' 15-G 16-G Grass Grass l.59xl0-4 +/- 3.99xl0" 4

l.02xl0- +/-*3.06xl0*

5 5

8.20xl0-5 6.48xl0*5

µCi g- 1 of dry ash

µCi g-1 of dry ash I

I ..

I 17-G Grass 7.69xl0*5 (2) 7.69xl0*5 µCi g- 1 of dry ash I

f 5 5 3.91xl0*5 18-G Grass 6.18xl0* +/- l.85x10- µCi g- 1 of dry ash 5

i 22-G Grass 2.79xl0-4 +/- 5.66xl0* l.12x10-4 . µCi g- l of dry ash

    • I (1) +/- values represent the standard deviation of the value at the 95% confidence level.
(2) Less than lower limit of detection value shown .
    • 2019-2020 @

RADIATION PROTECTION **

TableV.13 Annual Summary of Radioactive Material Shipments Originating From the TRIGA Reactor Facility's NRC License R-106 Number of Shioments **

I Shipped To Total Activity (TBq)

Exempt Limited Quantity Yellow II Yellow ill Total 1 Arizona State University 2.79x10-6 4 1 0 0 5 Tucson AZ USA

, Auburn University 2.09xl0-7 1 0 0 0 1

, Auburen. AL USA

, Berkeley Geochronology Center l.70xl0-7 6 0 0 0 6 Berkelev. CA USA

  • Columbia University 9.32x10*7 6 1 0 0 7 Palisades NY USA Lehigh University

, Bethlehem PA USA Materion Corporation 6.57xlo-8 1 0 0 0 1 5.77x.10-2 0 0 0 6 6 Elmore OH USA Materion Natural Resources l.l3x10*1 0 0 0 22 22 Delta UT USA NASA, Marshall Space Flight Center Huntsville AL USA

  • New Mexico Geochronology Research Lab 2.12xlQ-6 1 1 1 0 3 4.02xlQ-6 0 1 0 0 1 Socorro. NM USA New Mexico Tech 3.9lxi0-6 1 3 d 0 4 Socorro. NM USA Occidental College Los Amreles. CA USA
  • Oregon State University 5.13x10-9 4.llxI0-7 1

1 0

2 0

0 0

0 1

3 Corvallis OR USA Rowan University Glassboro. NJ USA 2.44xlo-8 1 0 0 0 1 Stanford University Stanford CA USA Syracuse University 6.74xl0-7 l.50xlo-8 1

I I

0 0

0 0

0 2

I

~ Svracuse. NY USA

, Tucson AZ USA l.36xl0-6 5 I 0 0 6 University of Nevada, Las Vegas

Las VeQ'as NV USA
University of Vermont l.37xl0-6 5.29x10.g 0

2 I

0 I

0 0

0 2

2

Burlinirton. VT USA

, University of Wisconsin-Madison Madison WI USA 8.53xlQ-6 1 1 2 0 4 USGS CA

'. Menlo P11rk CA USA USGSCO l.02xl0-7 4.09x1Q-7 4

1 0

1 0

0 0

0 4

2 Denver. CO USA

'USGSVA

, Reston VA USA 9.0lxl0-7 0 0 1 0 1 1

Totals l.71xl0- 1 38 14 5 28 85

@ Annual Report

  • a
    • RADIATION PROTECTION
    • TableV.14 Annual Summary of Radioactive Material Shipments
    • Originating From the Radiation Center's State of Oregon License ORE 90005
    • Shipped To Total Activity (TBq) Exempt Number of Shipments Limited White I Yellow II Total
    • Argonne National Lab Argonne, IL USA l.87xI0* 3 3 Quantity 2 1 0 6
    • Idaho National Laboratory Idaho Falls, ID USA 5.75xl0* 5 0 1 0 0 1
    • Los Alamos National Lab Los Alamos, NM USA l.73xl0*6 10 4 0 0 14
    • Pacific Northwest National Lab Richland, WA USA 3.26xJ0* 8 0 1 0 0 1
    • University of Nevada Las Vegas Las Vegas, NV USA 6.19x 10-1 0 1 0 0 1
    • Totals l.93x 10*3 13 9 1 0 23
  • I
    • 2019-2020 @

RADIATION PROTECTION **

Table V.15 Annual Summary of Radioactive Material Shipments Exported Under NRC General License 10 CFR 11 O 23

  • Number of Shipments Shipped To Total Activity (TBq)

Exempt Limited Quantity Yellow II Total **

  • Beijing Research Institute of Uranium Geology Beijing, CHINA . 3.08xl~ 0 I 0 I China Earthquake Administration

l.23xlo-' I 0 0 I Beijing, CHINA Curtm University of Technology 8.85xl~ 0 I I 2 Bently Western Australia AUSTRALIA Dalhousie University Halifax, Nova Scotia CANADA 3.29xlo-' 3 0 0 3 Geological Survey of Japan Ibaraki, JAPAN Glasgow University l.06xl0*7 l.79xJ0-9 I

I 0

0 0

0 I

1 Glasgow, Scotland ISTO l.18xl0-1 1 0 0 0 Orleans, *FRANCE Korean Baskic Science Institute

  • Cheongju-s~ Chungcheongbuk-do KOREA Lanzhou,Umversity 2.70xl0-S 4.20xlo-8 3

3 0

0 0

0 3

3 Lanzhou, Gansu CHINA

, Northwest University XiAn, CHINA l.26xlo-' 1 0 0 I **

Polish Academy of Sciences Krakow, POLAND QUAD-Lab, Natu~ Histoyr Museum of Denmark 3.64xlo-8 2 0 0 2 3.27xlo-9 I 0 0 1 Copenhagen, DEMARK Scottish Universities Research & Reactor Centre 6.77xl~ 4 3 0 7

, East Kilbride, SCOTLAND

  • Sofia University

, Belgrade SERBIA

'Universidade de Sao Paulo 3.IOxlo-9 1 0 0 I 1.53xl0-7 -3 0 0 3 San Paulo, BRAZIL

' University of Geneva 7.76xl0-7 3 1 0 4

, Geneva, SWITZERLAND

  • University of Manitoba 1

WIIlilipeg, CANADA 3.66xl~ 0 2 0 2 University of Melbourne 5.8lxl0-7 0 1 0 1 Parkville, Victoria AUSTRALIA 1

University of Padova 2.35xl0-' 2 0 0 2 Padova, ITALY University of Queensland

Brisbane, Queensland AUSTRALIA l.42xl~ 0 2 0 2 Victoria University of Wellington 2.3 lxlo-' 1 0 0 1 Wellington, NEW ZEALAND Vrijc Universiteit
2. l 7xlo-8 1 0 0 1 Amsterdam, THE NETHERLANDS Totals 2.57x10-5 32 11 1 44 Annual Report
    • RADIATION PROTECTION
    • . *. Figiire V.1
    • [ Monitoring Statio~s f~r the *osu TRIGA Reactor .. II I
    • .tmlil(:
  • ,,;:IJN

. ' . CNG'US UIJUTY . -

    • . "IW!:Cllffll .a;

,. ,......*= ="

lll1II\JEI ,R:f m4

    • R nG CAIO(A.tu,srADIIC *
  • GoUDU.flDST.al0ff CUSS .

s IIO!L

, 1111m 'DUISLOCADDSlmZSP:IVtB

  • llW 'WA1D.
  • MJICWAfllt . onmMIJUDOlfc:aiaur m&C0&TI.U.IUmOD' ..
      • 2019 - 2020 . ©

-W-ork **

Summary The Radiation Center offers a wide variety ofresources for VJ also highlights major Radiation Center capabilities in research teaching, research, and service related to radiation and radioac-tive materials. Some of these are discussed in detail in other and service. These unique Center functions are described in the following text. **

parts of this report. The purpose of this section is to sum-marize the teaching, research, and service efforts carried out Neutron Activation Analysis during the current reporting period. Neutron activation analysis (NAA) stands at the forefront of tech-Teaching niques for the quantitative multi-element analysis of major, minor, trace, and rare elements. The principle involved in NAA consists of first irradiating a sample with neutrons in a nuclear reactor such as **

An important responsibility of the Radiation Center and the reactor is to support OSU's academic programs. Implementa-the OSTR to produce specific radionuclides. After the irradiation, the characteristic gamma rays emitted by the decaying radionu-clides are quantitatively measured by suitable semiconductor radia-tion 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 tion detectors, and the gamma rays detected at a particular energy are usually indicative of a specific radionuclide's presence. Com - **

puterized data reduction of the gamma ray spectra then yields the programs. Table III.2 plus the "Training and lnstuction" sec- concentrations of the various elements in samples being studied.

tion (see next page) provide detailed information on the use of With sequential instrumental NAA it is possible to measure quanti-the Radiation Center and reactor for instruction and training. tatively about 35 elements in small samples (5 to 100 mg), and for activable elements the lower limit of detection is on the order of parts per million or parts per billion, depending on the element.

Research and Service Almost all Radiation Center research and service work is **

tracked by means of a project database . When a request for facility use is received, a project number is assigned and the project is added to the database. The database includes such information as the project number, data about the person and institution requesting the work, information about students in-volved, a description of the project, Radiation Center resources needed, the Radiation Center project manager, status of indi-vidual runs, billing information, and the funding source.

Table VI. I provides a summary of institutions which used the Radiation Center during this reporting period. This table also includes additional information about the number of academic personnel involved, the number of students involved, and the number of uses logged for each organization .

The major table in this section is Table VI.2. This table provides a listing of the research and service projects carried out during this reporting period and lists information relating to the personnel and institution involved, the type of project, and the funding agency. Projects which used the reactor are indicated by an asterisk. In addition to identifying specific projects carried out during the current reporting period, Part Annual Report

    • WORK 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 spectnnn of research reactor management, research reactor radiation protection, radiological emergency response, reactor behav-ior (for nuclear power plant operators), neutron activation
    • material types and involving virtually every scientific and analysis, nuclear chemistry, and nuclear safety analysis .

technical field .

Special training programs generally fall into one of several

    • While some researchers perform their own sample counting 6n their own or on Radiation Center equipment, the Radia-

. Center prov1"des a complete tion J NAA service for researchers categories: visiting faculty and research scientists; Interna-tional Atomic Energy Agency fellows; special short-term courses; or individual reactor operator o~ health physics

    • and others who may require it. This includes sample prepara-tion, sequential irradiation and counting, and data reduction and analysis.

training*programs. During this reporting period there were a

_ , large number of such people as shown in the People Section .

    • - I"adiations As has been the practice since 1985, Radiation Center personnel annually present a HAZMAT Response Team Ra-*

diological Course. This year the course was held at Oregon As descnbed throughout this report, a major capability of the State University.

Radiation Center involves the irradiation of a large variety of substances with gamma rays and neutrons. Detailed data Radiation Protection Services

    • on these irradiations and their use are included in Part ID as well as in the "Research & Service" text of this section .

The primary purpose of the radiation protection program at the Radiation Center is to support the instruction and

    • Radiological Emergency Response Services The Radiation Center has an emergency response team 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 capable of responding to all types of radiological accidents .

health physics services in support of OSU Radiation Safety This team directly supports the City of Corvallis and Benton and to assist other state and federal agencies. The Radiation County emergency response organizations and_ medical fa-Center does not compete with private industry, but supplies

    • cilities. The team can also provide assistance at the scene of any radiological incident anywhere in the state of Oregon 9n behalf of the Oregon Radiation Protection Services and the Oregon Department of Energy.

heal~ 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 maintains dedicated stocks of radio-logical emergency response equipment and instnnnentation.

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, Toes~ items are located at the Radiatj.on Center and at the sealed source leak testing, packaging and shipment of radio-Good Samaritan Hospital in Corvallis.

active materials, calibration and repair of radiation monitor-During the current reporting period, the Radiation Center ing instruments (qiscussed in detail in Part VI), radioactive emergency response ~ conducted several qaining ses- waste disposal, radioactive material hood flow surveys, and sions arid exercises, but was not required to respond to any radiation safety analysis and audits.

    • actual incidents .

Training anr} Instruction The Radiation Center also provides services and technical support as a radiation laboratory to the'State of Oregon Radi-

    • In addition to the academic laboratory classes and courses discussed in Parts ID and VI, and in ~ddition to the routine ation Protection Services (RPS) in the event of a radiological emergency within the state of Oregon. In this role, the Radia-

. tion Center will provide gamma ray spectrometric analysis of training needed to meet the requirements of the OS1R Emer-water, soil, milk, food products, vegetation, and air samples gency Response Plan, Physical Security Plan, and operator collected by RPS radiological response field teams. As part requali:fication program, the Radiation Center is also used for of the ongoing preparation for this emergency support, the special training programs. Radiation Center staff are well ex-

    • perienced in conducting these special* programs and regularly Radiation Center participates in inter-institution drills.
    • offer training in areas such as research reactor operations,
  • 2019' - 2020 @

WORK **

Radiological Instrument Repair and Calibration Instrument calibrations are performed using radiation sources certified by the National Institute of Standards and Technology **

While repair ofnuclear instrumentation is a practical neces-(NISl) or traceable to NIST.

sity, routine calibration of these instruments is a licensing and regulatory requirement which must be met. As a result, Table VI.3 is a summary of the instruments which were cali- :e the Radiation Center operates a radiation instrument repair and cah"bration facility which can accommodate a wide vari-ety of equipment brated in support of the Radiation Center's instructional and research programs and the OSTR Emergency Plan, while Table VI.4 shows instruments calibrated for other OSU departments The Center's scientific instrument repair facility performs maintenance and repair on all types of radiation detectors and non-OSU agencies.

Consultation **

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 Radiation Center staff are available to provide consultation ser-vices in any of the areas discussed in this Annual Report, but in particular on the subjects of research reactor operations and on hand and repair time is therefore minimized.

In addition to the instrument repair capability, the Radia-use, radiation protection, neutron activation analysis, radiation shielding, radiological emergency response, and radiotracer methods.

tion Center has a facility for calibrating essentially all types of radiation monitoring instruments. This includes typical Records are not normally kept of such consultations, as they often take the form of telephone conversations with research-portable monitoring instrumentation for the detection and ers encountering problems or planning the design of experi-measurement of alpha, beta, gamma, and neutron radiation, ments. Many faculty members housed in the Radiation Center as well as instruments designed for low-level environmental have ongoing professional consulting functions with various monitoring. Higher range instruments for use in radiation accident situations can also be cahbrated in most cases.

organizations, in addition to sitting on numerous committees in advisory capacities.

. TableVt1 **

I I,

i Institutions, AgendE!!s a*nd Groups Which

  • , ** Utilized the Radiation _Center - -

Nunibei;- of

!-rntu.itions, Agenci~ and Groups I

  • Arizona State Univeristy Numbei:o( , NumbernfTimes of Projects , Faculty Involvement Dses of Center:

FacilitiPc::

1Tempe, AZ USA

  • Auburn University I~uburn, AL. USA 1

1 ..

. 0.

1 5

1 i*Beijing Research Institute ofUrani~ Geology

'.Beijing CHINA '  ; .

2 0 2 **

.:*Berlceley Ge0ehronology Center l

~erkeley, CA USA*

i:Boyt Veterinary Lab.

1 0 6

I *

Stxes, QR USA

'College of Veterinary Medicine 1corvallis, *oR USA *1 1 0 i

5 2

I I **

'I

**I I
  • columbia University ,.

1 0 1

?alisades,.NY. USA .

'.*Dalhousie University '.

  • 1 2

!Halifax, Novia Scotia CANADA  :

1  :

jDepartment of Geosciences * *. ..

1 0 i rrucson, AZ USA  :

@ Annual Re_port

    • WORK
    • Table-Vl.1 (continued)
  • Institutions, Agencies and Groups Which Utilized the Radiation Center
    • I
intuitions, Agencies and Groups Number of Number of Tunes of Projects Faculty Involvement Number of I Uses of Center i FiidlitiP-,;

[)epartment of Horticulture I 1 2 7 Hermiston, OR USA

    • :Environmental and Molecular Toxicology

,Corvallis, OR USA

'Genis, Inc.

1 1 1 I 1 0 2

Reykjavik, ICELAND 1
  • Geological Survey of Japan/AIST 1 0 1
Tsukuba, Ibaraki, JAPAN

~Institute of Geology, China Earthquake Administration 1 0 1 i8e1jing, CHINA

    • ;*INSU-CNRS - Universite d'Orleans

,Orleans, FRANCE

~Korea Basic Science Institute L r 2

    • 3 1 1 Cheongwon-gun, Chungcheongbuk:-.do SOUTH KOREA
  • Lanzhou University _

2 0 3 Lanzhou City, Gansu Province CHINA

  • Lanzhou University 2 0 3 Lanzhou, CHINA
    • :*Lawrence Livermore National Laboratory Livermore, CA USA

.*Lehigh University 1 1 1

,*Materion Brush, Inc .

1 1

0 0

1 5

'Elmore, OH USA

.* Materion Corp.

1 0 1

Toledo, OH USA
    • *Materion Natural Resources
  • pelta, UT USA 1* Museo Egizio 1 0 13 j

1 2 1 1Torino, ITALY jNASA Marshall Space Flight Center 1 0 4

Socorro, NM USA 1 0 6
    • - f,t,Northwest University rx:i'An, CHINA 1 0 1 i

i*Nray Services, Inc. i 1 1 1 Dundas, Ontario CANADA I

  • Oregon State University(!)  :

125(2) 17 46 Corvallis, OR USA " I 2019-2020

WORK **

Table Vl.1 (continued)

Institutions, Agencies and Groups Which Utilized the Radiation Center **

Intuitions, Agencies and Groups Number of Number of Times of

_Projects Faculty Involvement Numberof

  • Uses of Center F<><'iliries
  • Oregon State University - Educational Tours

'Corvallis, OR USA 1 0 7

  • Oregon State University Radiation Center 1 1 13 Corvallis, OR: USA

'*Polish Academy of Sciences 1 2 0

Krakow, POLAND

  • Quaternary Dating Laboratory 1 0 1 Roskilde, DENMARK

_Radiation Protection Services

.Portland, OR USA 1 0 4

  • Rowan University Glassboro, NJ USA
  • Scottish Universities Environmental Research Centre -

1 1-0 1 0 6 East Kilbride UK -

Selmet, Inc 1 0 1

'Albany, OR USA

  • Sofia University 1 2 2
Sofia, BULGARIA
    • Solidia Technologies Piscatawsy, NJ USA 1
  • Stanford University 1 2 1 1 0 2 Stanford, CA USA
  • Syracuse University 1 1 1 Syracuse, NY USA

.* U.S. Geological Survey 1 0 1 Reston, VA USA 1

  • U.S. Geological Survey 2 0 8

<Denver, CO USA

  • u.s. Geological Survey Menlo Parle, CA USA
  • Universita' Degli Studi di Padova 2

1 0

2 8

2

,Padova ITALIA

'university of Alaska, Anchorage I ,

Anchorage, AK USA 1 1 16 **

  • University of Geneva 1 1 5 Geneva SWITZERLAND
  • University of Glasg9w 1 0 2

,Glasgow, SCOTLAND*

Annual Report

    • WORK
    • Table Vl.1 (continued)

Institutions, Agencies and Groups Which Utilized the Radiation Center

    • I IJntuitions, Agencies and Groups i

Number of Number of Times of Projects Faculty Involvement Number ot ,

Uses of Center:

Faciliti= I

    • !*University of Manchester Manchester, UK 1 0 1 '

i*University of Manitoba 1 1 2

!Winnipeg, Manitoba CANADA

  • university of Melbourne 1 1 3 I

Melbourne, Victoria AUS1RALIA

  • University of Nevada, Las Vegas '

1 1 *3

Las Vegas, NV USA i
    • ;*University of Queensland
Brisbane, Queensland AUS1RALIA 1 1 ,2 .,

I

    • '*University of Sao Paulo
sao Paulo BRAZIL 1

1 1 4 Madison, WI USA

    • :US National Parks Service
crater Lake, OR USA 1 0 3 I

Victoria Univeristy of Wellington

,Wellington, NEW ZEALAND

.*Vrije Universiteit 1 0 .. 2 '

    • 1 1 2 '

!Amsterdam TIIE NETHERLANDS

'*Wayne State University 1 2 2 I

,Detroit, Ml USA

,*Western Australian Argon Isotope Facility I 1 0 4

Perth, WesternAustralia AUS1RALIA I I

,81 333 1Totals 84

.* ProJect which mvolves the OSTR

    • '(2)

Use by Oregon State University does not include any teaching activities or classes accommodated by the Radiation Center.

  • This number does not include on going projects being performed by residents of the Radiation Center such as the; I

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 .

    • 2019-2020

©)>

Table Vl.2

E 0
c
, Listing of Major Research and Service .Projects Preformed or in Progress A C:

Ill at the Radiation Center a~d Their 'funding Ag-encies

0 ct) '. Funding "O \ Project *users Organiz.ation Name Project Title  : Description 0
i.

I Production ofAr-39 from K-39 to measure f I.444 Duncan Oregon State A'r-40/Ar-39 Dating of Oceanographic radiometric ages on. basaltic rocks from ocean OSU Oceanography ,

Unjvers!ty Sainples - - - Department I

.. " basins. - -
  • 815 Oregon _State , Sterilization of wood samples. ~o2.5 Mraqs in Co- OSU Forest Products_ - (

'Morrell Sterilization of Wood _Samples I .. Universitv , 60 irr!ldiator for fumral evaluations.

I Berkeley . Production of Ar-39 from K-39 to determine ages Berkeley 1920 .. Becker Geochronol_<;>gy Center Ar- 39/Ar-40 Age Dating , in various anthropologic and geologic materials. Geoc.hronology

' Center I -

Vrije Universiteit,

1074 Wijbrans . Vrije. Universiteit AriAr Dating of Rocks and .Minerals" - AriAr dating of rocks

) ' ~

and minerals.

Amsterdam I

, University of  : Production of Ar-39 from K-39 to *determine ages' Earth Sciences, *

! 1191 Vasconcelos Queensland Ar-39/Ar-40Age Datin~ * *

in v:anous anthropologic and geo~ogic _mate~als.

University of Queensland I

I  : Determination of history and timing of denudation I The University of - Fission Track Thermo-chronology of - of basement terranes ,in New Zealand and thermal .

u'mvers1"ty.ofTI'-"*-'- !

f 1353 Xamp . . edim nWIUUO:

Waikato New Zealand * . *

  • history ofl ate Cretaceous -Ce
  • n_o:z;o1c s entary r . '.

basins.,- . I I

University of Ar-40/Ar-39-Dating of Young Geologic Irradiation of geological materials such as volcanic- Uruversity of i-1465 *singer - -

  • Wisconsin Materials - - - , .. . , rocks from sea floor etc. for Ar-40/Ar-39 datirul:. . W1SCOnsin Oregon State Teaching and OSU Nuclear Engineering & Radiation . OSTR tour and reactor lab. NA I

!1504 University - , I Tours .Health Physics Department I I Educational Tours I I

Age determination of apatites by fission track

1514 I

Sobel Universitat Potsdam Apatite Fission Track ~alysis analysis*.

  • Universitat Potsdam

'C

, r

' Fission*track dating method on apatites: use of t University of

  • Univeersity of r

'.1519 Dunkl Fission Track Analysis of ,Apatites fission tracks from decay ofU-238 and U-235 to I Goetting;en Tuebingen

  • determine the cooling aize of aoatites. '

' I Univ~rsita' Degli Stlldi Fission track analysis ofApati"tes , Fission track dating method on apatites by fission,  :

1 152~ .zattin NA di Padova *  : track analysis.

  • Irradiation to induce U-235Jission for fission track I thermal history dating, especially for hydrocarbon I
1555 Fitzgerald Syracuse University Fission track tliermochronology exploration. The main thrust is towards tectonics; Syracuse Uni~ersity t in particular the uplift and formation ofniountain

' - "ranges'. ** ,*

' I Ar-Ar geochronology and Fission Track 1617. Spikings_, University-of Geneva- dating , * ** ,

  • Argon dating of Chilean ~tes: __ University of Geneva i I *
  • I .

I Table Vl.2 (continued)

I I Listin*g*of Majnr Res~arch and Service Projects Preform~ or in Progress -

at the Radiation Center and Their F1,1nding Agencies I I 1,Project Users*

  • Organization Name Project Trtle__ . Description. .. Funding*  ;

1 Fission track Thermocbronology of geological I r623 _ Blythe Occioental College Fission Track Analysis Occidental College samples '

I Reactor O~gon 'State

  • Operations support of the . ~ r and OperaJ:ions use of the reactor in support of reactor '

'*1660 NA I C Onerations Staff* Universitv facilities testing and facilities testing. -

-Radiological emergency support ot OOE related. I

--

  • to instrument cahbrati9n; radiological and  ;

Oregon Department of_ Oregon Department '

11674 Niles *

  • Radiological Emergency Support: RAM transport consulting, and maintenance of
  • Energy ofEnergy i radiological analysis laboratory at the Radiation --

.. Center. ,

i I US National Parks US National Parks j

'1745 _ Girdner C14 Measurements LSC analysis of samples for C14 measurements.

i . Service . Service  ;

i Terra Nova Nurseries, Genera Modifications using gamma U~e of gamma and fast neutron irradiations for Nova Terra . Nurseries, I i 1767 Korlipara {

Inc. irradiation genetic studies in genera. - Inc.

. - .. I

'1168 Bringman - Brush-Wellman Antimony, Source Production:  : ,Production of Sb-124 sources. Brush~Wellman I Production of'3/4-39 from K-3_9 to determine

.. Quaternary Dating i Quaternary Datmg l

!1777 Storey Quaternary Dating  :

Laboratory radiometric rures of 11:eoloitlcal materials. Laboratory I- .. - .  : -

This project subjects chitosan polymer in 40 and '1 I

I 70% DOA formulations to 9 and 18 Kgy, boundary

! 1778

  • Gislason. .. Genis, Inc **1_" Gamma exposure of Ghitos*ao, polymer
  • doses for commerical sterilizatioµ f9r the purp~se Genis, Inc. I of determine changes in the molecular weight apd I . . product formulation oronerites. '

I Trace-element analysis of ancient Maya ceramics

1785 Mine Oregon State Univesity INAA of Maya ceramics

.from Pultrouser Swamp, Belize.

'1818 Sabey :Brush Wellman Antimony source production (Utah) Brush-Wellman I I  : ..

Fission track thehnocbronometry ofth~ l I 1-831 Thomson _ University_ of Arizona Fission Track * -- Patagonian.Andes and the Northepi Apennines, Yale University I I

C I ., Italy.

- I Swingle AriAr dating of ordinary cho:r;idritic AriAr dating of ordinary ,chondritic meterorites .. University of.Arizona !

!1~41 . University of Arizona meterorites I I "

  • Pofuh Academy .of

.. ' for illite-mechte data Polish Academy of

. AI).czkiewicz Fission Track Services -- Verification of AFT data  :

11855 Sciences Sciences I I

Uni'9'.ersity of University of ,,

N I Production of Ar-39 from K-40 to determine 0 il864 ' Gans California at Santa Ar-40/Ar-39 Sample Dating* California *at Santa '

I-' radiometric ages of geologic-samples.  ;

I.D I Barbara Barbara I

'I I , *Apatite fiss_ion track to reveal the exhumation_ . *

~

I University of . Fission Track Irradiations

  • history of rocks from.the ID-WY-UY postion
  • University of  !

N 0

I1865- Carrapa Wyoming* of the Sevier fold. and thrust belt, Nepal, and WyQming I I  : Argentina.* .. .' I I

I

-,,----- ---------- ----------

  • Table.Vl.2 (c~ntinued)

-,1 ~

c
J Listing of Major Research.and Service-Projects Preformed or in Prog*ress ,* "
J C:

Ill .. at the Radiation Center and Their"Funding Age~cies

,I

c .. i rt)
Project Users Organization Name 'Project Title Description* Funding "C '

0

i. Plattsbµrgh State Use*offission tracks to detrmine location of235U, Plattsburgh State
' 1878
  • Roden-Tice
  • Fission-track research Universitv

! Universitv 2321h in natural rocks and minerals.

,INM of Ar¢}µleological Ceramics from: Trace-:element analysis of Inca~period <;eramics for Wayne State I'

,.1882 . Bray Wayne State Univerity Universitv

South America . provenance determination. :
  • I

- Toe current project is designed to*identi:fy the -

  • LD50 rate of gamma irradiation so that large Oregon State seed lots inay be ifra4iated in order to develop* OSU Horticulture 1884 Contreras
  • Mutation breeding o,fwoody plarits University*

'. novel phenotypes that-exhibit reduced fertility or sterility. * * .. * *-

1886 Coutand Dalhousie University Fission Track.Irradiation Fission track irradiations of imru:ite samoles. Dahousie Universitv :

11-887 Oregon State .. OSUNERHP Farsoni :Xenon Gas Production Productjon ofx~1ion gas. * .: :

Universitv ./

The goal of this project is to determine the effects

' . of hydrolysis and radiolysis on the extraction -

I

.. .. . a iµiility of diamide an~ chlorinated cobalt Qregon s~~ *Hydrolysis and R:adiolysis of syn~rgistic

  • dicarbollide (CCD). <:;:CD and the.,qiamide are Orego~ ~tate

'1889 Paulenova .'  : synergistic extractants and will be together in Univeristy NSE

University extractants

- ' ..  : . solution for hydrolysis and radiolysis experiments.

~

Effects will be measured with IR spectroscopy and

' extraction distribution ratios. -

I Use of fission tracks to determine*location of Geologisches IIlstitut, J

'1905: Fellin ETH Zurich.

  • Fission T~k Analysis 235U 232Th in.natural rocks and minerals. ETH Zurich  !

C

' Use of neutron activation to determine fission Oregon State Fission Yield Determination Using yields for various fissile and fertile.materials using* N/A ,

1913 Reese University .G~a Sp~~py- - lllllllilla*soectrosceov. * *


'--___;-----1-___; ----'------l------------- -+li==;;..;.i;=;;,.;;.;; .,;;..;;,.i;.o..;..__....;...______-4-_ _ _ _ _ _ _,

Scottish Universities .. ..

., Scottish Universities * \

Ar/Ar Age Dating i 1914 : Barfod Environmentai . Ar/Ar.age dating.: *Research and Reactor Research Centre Centre .*;

Victoria University of . ~ ' . . Vitoria University of  ;

11927 *seward "

Fission Track Dating '. Fission track dating of apatite samples. Wellimrton l Wellirurton

1939 . Wansz Lanzhou University Lanzhou University-Fission Track
  • Fission Trackdatin~. Lanzhou University I

' Oregon State

1955 Higley* lJptake ofredionuclides in plants '. ~ e concentration ratios in plants. OSUNERHP ., I University L 1

' University of Ra4iometric age dating of geologic University of

  • Ar/Ar age dating..

,1957 Phillips

.. Melbourne samoles Melbourne i I . ' " " Irradiation with fast neutrons to produce Ar-39_ .

. U mversity . ofViermont I,

1965 Webb University ofVerinont Ar/Ar ~e dating . from K-39 for Ar/Ar 11:eochronofoi!v. * *
  • Table Vl.2 (c~ntinued) .

Listing of Major Researc*h and Service Projects Preformed or in Progress at tlie Radiation Center and Their Funding Agenc~es I " I I

!Project ,Users Organiz.atio~ Name Project '.fi.tJ~ Des_cription I Funding

'* I I

School of

1975

'I McDonald University of Glasgow Samuel Jaanne

' Use of fissin tracks to determine last heating event of apatites.

G- ~hical and Earth Science*

-I I I

OregonS~ Multi-element, transition ,metal salt production for '

1979, Paulenova Mixed Matrix Extraction Testing. I

, University mixed matrix extraction testing. .. I I

,' 1980*" Radiation Protection Carpenter ,San:ipl~ counting : *. Sample counting. State of Oregon RPS I Services I

11995 Camacho Unive~ity of Manitoba Ar/Ar dating.'

'Production ofAr-39 from K-39 to determine Univefliity .of I

,radiometric W!:es of ,11;eological materials. Manitoba*. I
2004 Sudo Uruversity of Postdam AriAr Geochronological Studies AriAr dating of natural rocks and minerals for geological studies.

l I Arizona State

  • _Fast neutron irradiation of mineral and ro'ck . Arizona State *;
2007 Wartho. ,Argon-Argon Geochronology ..

University

  • samples for 40 Ar/39Ar dating purposes. University I University *of Sao University of Sa<:>
2010 I

Helena Hollanda Paulo AriAr Geological Dating Ar/Ar geologic dating ofniaterials.

  • Paulo II I

I Si02 surfaces were silanized (vapor deposition) *j

'. 1 with TGVS to create double bonds on surface.

Chemical, Biological . . '

OSU Chemical - I

2016 Schilke & Environnierital . TCVS Silaniz.ati.Qn for EGAf coating , The surface is incubated in Pqlyethylene tnblocks, Engineering Engineering once gamma irradiated it wilJ bind the triblocks to.
. . . the surface . -1 12011 I

Jourdan Wester Australian Aigon Isotope Facilitv Age dating of geological material.

.

  • AriAf geochronology.

Curtin University ** iI Lawrence Livermore .. i>roduction of neutron induced 39Ar from 39K *for Lawrence Livermore i

,2023 Cassata Ar/Ar dating

. . .. National Laboratory Ar/Ar. datin,11;. ,_ National Labor:_atory *\

2028 Mine Oregon State University INAA of ceramics from the Ancient .

Near East

' Provenance determination of ceramics from the Ancient Near East via trace-element analysis.

OSU Anthropology I

- I Korea Basic Science - AriAr. ~alysis for. age ~ of geological Korea Basic Science

\2029 I

Kim

Institute.

Ar/Ar geochronology samples. Institute 1 I

Cp.ina University of

  • China University of, iI 2033. Chang.*.. Fission Track F~ion traclc -~g of rock samples.

Petroleum - Beijing* Petroleum - Beijing I I

Oregon State . Sterilization of wood to 2 ..0 Mrad for.fungal

!4034 Morrell Sterilization of Wood Products OSU Fo~ Products i University exoeriments.

i Lanzhou Center of Oil ' Lanzhou Center -,I I

N 12035 Wang and Gas Resourc*es, F~ion Track Fission track dating of rock samples. of Oil and Gas I 0

I.O

' CAS - Resources CAS

'l, N

0 12036 Loveland Oregon: State University * -

. Measure,ment of fission, product TKE Measurement of fission product kinetic energy for various fissile elements*. . .. i N

0

-.----- ----- ----- ----- ----- Table Vl.2 (continued), .*  ;

I listing of Major-Research and Service Projects Preformed or*in*Progress
I C

Q) at the Radiation Center and Their Funding Agencies .

x, - ' I m ,l>roject Users- Organization Name Project rrt,e -* Description Funding "C I I 0
i.
-  : Prevention of Infections AS{!Ociated witµ - i I

Combat-related.Injuries by Local Sustained

C~Delivery ofVrtamin D3 and Other Immune- '

Boosting Compounds Awru:d Mechanism. Weare preparing nanofiber wou.qd dressings that contain Prevention of Infections Associated I Oregon State . compounds that will be ~leased over time to I

2039 Gombart with Combat-related Injuries by Local University ipduce the ~une response in woup.ds to help Sustained c~Delivery I prevent infection and speed wound _healing. The I  : "

-- nanofibers must be irradiated so that they are .

!  : ' - sterile. These experiments will be performed in '

i cell culture and in animal models. "

i - ,, Use ofneutron radiography to view degradation in '

' - Oregon State - .. aluminum ATR -capsules fron:i endurance1esting of --

(2041 Marcum  : . Neutron Racliography of ATR*Capsules University tbese caps~es under contiimous hydraulic loading I ,_ over the course of a vear.. I I

~elemenianalyses -of Neolithic and Bronze Univ~ity of Oregon

)2042' Walsh University :0f Oregon INAA of Apcient Ceramics frqi;n Korea Age ceramics from SE Korea . . - '

I Helmhoitz~Zentrum .. _ G:POMAR Helmholtz .

2045 van den Bogaard fur. O~orschoog . GEOMAR AriAr- . AriAr dating research of geological samples- -

. Centre foi: Ocean T :-

Kiel (GEOMAR)

-- Research*

- . (

Measuring the uptake of strontium by inorganic I
(IONSIV) and organic (chitosan-based) sorb1mt I Oregon State m?teiials. Kinetics ofuptake will also be i205J Paulenova University . * - Measuring the uptake of stroqtium
  • I

- ' evaluated. Nap.rral strontium will-be used as a carrier and Sr-85 will serve as a tracer. .. I Gamma irradiation of pollen has been used°* -- I

- I r

. su~fully by plant geneticists to facilitate

discQvery of genes and chromosomal regions that r

,, l

-, -- control traits of interest in crops and trees like

poplar. Geneticists in tlie US Forest Service have I Gamma irradiation of Port-Orford Cedar  ;

identified valuable single gene~ in Port-Orford 2058 - Cronn USDA Fo~st Service pollen to generate .chromosomal segment Cedar, *an ecologically and economically important USDA Forest Seryjce

. deletions conifer native to Oregon.. We would like to test I

.. " whether pollen irradiation can be used to create ,. "i

,, deletion lines that have modified traits, with. the 1: - *- - goal -of-identifying the genes controlling these t

'" traits. - c

"

  • Ar/Ar geochronology ofv(?lcanic and igneous -

I Geological Survey of Geological Survey of

'2060 Ishizuka,, AriAr Geochronology: . rocks associated with subduction initiation of .. Japan I - "

Japan/AISt.  :

oceanic island arc..  : --

I

_ .TableVl.2 (con~inued) * .

L.:isti.,g of MaJor*Research and s*ervice Projects Preformed or in Progress at the Radiation Center and -

Their Funding Agencies I

Project Users Organiz.ation-N rune Project _'Ijtle Description Funding  :'

I 2061 Weiss Oregon State ,. Neutron Radioiaphy Imaging of Investigation into the applicablity of neutron radiography for evaluating concrete curing

  • l University Goncrete processes. ,

I., .. ..

W,e will be performing bencli scale microcosm i I I

' Abiotic D~hlorination of chlorin'ated studies to measure the abiotic dechlorination in I

2064 Schaefer COM Smith*

, solvents in soil matrices. . different soil matrices. Gamma irradiation will be CDMSmith I

I

' - used to sterilize the samples. I I .. '

. Use ofneuti:on radiography and orilography

  • I Oregon State Neutron Radiography of Long-Term . Oregon State '

12?67 Reese imaging in long-term studies' of concrete curing *1

. University Concrete Curing  ; University CCE used in civil construction.

I . Use offj.ssion-track analysis to determine U

\

i

,. l I content and fission track age constrains low- '.

!2068 XU Tongji University Apatite/zircon fission-track irradiation m

temperature 'cooling and exhumation South

I' I China I I

INSU-CNRS- AriAr analysis for age dating of geologic samples INSU-CNRS- I 12669 Scaillet Ar/Ar ~ g of geologic sampl~

Universite d'Orleans ' (solid rockcliios and minerals) * - Universite d'Orleans :

1 I I The purpose of this experiment is to determine

' ' what color a nearly colorless Tourmaline will

,, I t

I i turn with dosages of 5, 10 and 20 Mr of Gamma -,(

I ,. ..- ,. irradiation. 1\vo Pakistan Bery1 crystals are also I part of this experiment to s_ee the color change as

well as 2 piec:es of Four Peaks Am~thyst that may I

. have been faded by sunlight. For the Tourmaline, I

Gamma irradiation induced change of

';2010 Lowell Colorado Gem and color in Tourmaline from a Pegmatite in colouossibilities are brown, yellow, and pink Colorado Gema and I

Min~ralCo. to red. The commercial value _of colorless gem Mineral Co.

the Oban Massif, Nigeria .. . i I Tourmaline is very low, but other cofors of gem

)

I Tourmaline, especially pink and red results, would .. l' 1 '. I

.. stimulate mining of this material in Nigeria. 20 I


. . Mr is usually a dosage that will ~ t e the visible

' I I

color, and*lower dosag~ may be preferable if the I I

I Gamma rays ca.use a ne)V color other than pink or

'/  : *r

,, red which is the desirable result.*

f

,, I NAA *or archaeological ceramics from the Valley Oregon State - Market Exchange in Ancient Oaxaca, N '2074 Mine of Oaxaca, Mexico,' to trace the origins of niarket NSF

....0 I.D

, I University Mexico

  • exchan,11;e.  :

N 0

N 0 ~

0

0 A

,--I------------------------

)>

Table.Vl.2 (contiriu~d) . .

, Listing of Major Research and Service Projects Preformed or in Progress C:

Q) at the Radi~tion Center and Theijrfunding Agencies

xi (D ' Funding i "C
  • Project Users Organiz.ation Name Project Title Description 0
l. Trichloroethylette can diffuse int9 low p~rmeabil- I' ity materials such as clays. When there is a change  !

' . - . in chemical gradient, TCE can "back diffuse"  !

I Biogeochemi~ Processes thiµ: Control . U : *ty* *f.,., _ _,." I oufofthe clay into higher permeability*materials mvers1 o ... e,.,.,,

'.2075 Berns Uµiversity of Texas Natural Attenuation ofTCE in Low '

(such as sand) and be transported through the sub-  !

Permeability Zones .. _

smface. Thj.s project fqcµses on the biogeochen;ti- I cal interactions influencing the back diffusion of I trichloroethvlene at a sand-clav interface. **

.. Oregon'State Standard Test Method for Antimony , Round-robin to demonstrate utility of INAA for I I

12081 Mine University Content in Plastics characterizing antimony content in plastics . .'

I Use of :µssion track analysis to determin,e U 2085 He Lanzhoµ University: Apatite fissio~ track m conterit the sedimentation 'ofXinin11; Basiri.

. _Lanzhou l.Tniversity I

The goal of this project is to indueti mutations I .. -- in-seeds and dormant cuttings of commercially .

I i

i -- important landscape plants produced by the horti~

  • - __ 'cultural industry. Based on results by the principle'  : I i  : researcher and published literature, it is_ anticipated I I

Mutation Induction by Radiation in radiation. induced c4anges to the genome and Innovative Plants  !

.2086 Pounders Innoval:jve Plruits LLC Asexually Propagated Landscape Plants*. ~11 cytoplasm of treated material may 4Iclude J.,LC ~

. -- .. . improved environmental tolerance and/or morpho- '

.. .. logical changes of horticultural importance suQh as I

I .*: 'floJer color, leaf color, dwarfness, branching etc. I

' .. Identified muta,tions of commercial value will be '

I

. . ,. asexually prooa£ated.by particioating nurseries. '

. Full spectrum irradiation of CaF2 crystals to  :

I

w81 Hecht UNM Calcui-m Fluoride dosimetry studies determine changes_ in optical properties due.to

.. . neutron exposure.

  • I

'I Fission Track Dating* of Qaidam Basin Fission track dating of Qaidam Basin, China to

2092 Jianaiqng Northwest.University determine its age. I'

'20% Reese Oregon State University

. . Cross linking of polyblers Ctoss linking polymers by use of gamma irradiation,:

NSE I Project is- designed to irradiate liquid donor bovine, -

  • J serum* ~p.tained ~ vinyl bags to__a minimum level , _

Donor* Bovine Serum Irradiation I 1

'.2097 Boyt Veterinary Lab *** of 25 kGy to inactivate any adventitious agents Boyt Veterinary Lab :*

I *- that may be present in 0:2 um sterile filtered ,* -i oroduct.

Institute of Geology, -

Studying the thermal history of the northeast Tibet China Earthquake

'2098 Pang Ghina Earthquake

  • Fission-Track dating-,;

Plateau by _the fission-track dating method. Administration _.

Aclministration

. Table.Vl.2 (continued) .

Listing of Major Research and Service Projects Preformed or in Progress

.i j

I at t'1e Radi~,tion Center arid Their Funding Agencies I I

i Project Users - ' Organization Name Project Title Description . ' Funding: .

i I

I Use ofgamma spectroscopy'to verify authentisity *1 Gamma S~troscopy of Hiroshima 12099

  • Wesel Nakhla Dog Meteroites ofv,:atch claim~ to have been exposed to the I

I Watch Hiroshima bombiru!:.  !

I II This project is a collabof!ition with OSU Robotics. i

," We are investigating the performance of PDMS , I I School of Nuclear materials, which are used to fabricate soft robotics, Soft Robotic Applications for.Nuclear Idaho National 2100 Palmer - Science and

, Safeguar,ds following radiation exposure. We .would like Laboratory Engineering to' characterize any,changes in hardness, tensile*

.. - I strength, and recovery after e)\:posure to high  !

I-. radiation environments.

I I

!2101 Yang Zhejiang University Fission-track thermochronom_etry Fission-track analysis for dating geological material.

Zhejiang University l I Gut microbiota mediates the interplay To identify microbial taxa an,d their genes that I College of Veterinary OSU Veterinary I 12102. Shulzhenko Medicine,

  • between immunity and gluco~ affect glucose metabolism and immune response I I ~ Medicine metabolism using mouse model of diet-induced diabetes. I I I The.project is SERDP ER-2720, Key Fate I and Transport Processes Impacting the Mass *I I

i' Discharge, Attenuation, and Treatment of Poly- i i'

and PerfluoroalkyJ Substances and Coajngled I"

. .. Chlorinated.Solvents or Aromatic Hydrocarbons .

.. The overall goal of this ~earch is to attain I "

improved-insight into the fimdamental fate I

! and transport processes that control pe.r- and I Colorado School of polyfluoroalkyl substance (PFAS) fate and Colorado School of I

\2103* Higgins SERDP ER-2720 l I

I Mines transport as well as comingled chlorinated Mines I I

i solvents and/or fuel hydrocarbons in groundwater I" '. at aqueous film fo~g f0a!]l (AFFF)-impacted I

I .. - . .*

sites. This research will particularly focus on the -

- , . release and transformation of polyfluorinataj I

PFASs to themore problematic perfluoroalkyl . I I acids (PFAAs) in source zones as well as the I

I I .. -*

  • impact of commonly employed remediation technolo!,!;ies for co-contaminants on PFAS fate.

I I i .I The goal*ofthis project is to'explore the use of N

I' shape-memory polymer construtts to deliver i 0

U) I. - and retain bioactive agents within complex bone 1

i fractures. and .defect sites. Bioabsorbable shape-l:5 :2104 Oest Department of Shape-:-memory polymers for accelerated memory polymer constructs will be doped with .

SUNY Upstate I Orthopedic Surgery repair of complex bone defects Medical Univei:sity I N

0 I

I

' antimicrobial and osteogenic agents, then triggered II

., by a local temperature change to conform to II - '.

the bone defect site, effectively containing the - -- . ..I I

.* bioactive !Ul:ents within the'area to be repaired. '  !


,-- -----,---- ---------- Table Vf~2 (continued)' .

Listing of Major*Research*and Service Projects Preformed or*in Progress at the Radiation Center and Their Funding Agencies

,J - I , '

(D Description Funcj.ing "C

0 Project Users Organization Name Project Trtle I

' Evaluation of Moisture C:::on~nt in Wood Use 9fneutron radiography to dete~~ the

. i

~ Oregon State

2105 ,Way University Products moisture content of various. wood composites.

I -- . , . .,

INAA to-determine concentrations of PGE-and 1

2106 Renaud Vesta Minerals. In~. PGE Determination ,.

I -- REE in mineral ores*.  :

I This project is a collaboration with OSU Robotics.

We are investigating the performance of PDMS

materials, which are use:d to fabricate soft robotics, Idaho National School of"Nuclear
  • I Soft R9botic Applications ofr Nuclear
  • following radiation exposure. We would like
2101 Palmer Science and Safegau:rds * .  : ' . . Laboratory I I

Engineering i to characterize any clµmges.in hardness, tensile

,_, strength, and recovery after exposure to high ' I I,_* ' ..

" ' " radiation* ~nvironments. - i I

Johnson Crushers ,

' , Determination ofRa-228 in Zircon sand used for Johnson Crushers I

2108 Walker Cbaracterization bf Zircon sand weldmi;1; flux. .
  • International

, Internatinal Inc

' I I Objective is to determine the effects offive I

" . treatments on reduction.of bacteria and viruses *
  • I
f. School of Biological Altematiye ".J'echniques for Ensuring and on the activity of milk digestive enzymes, _

School of Bio And  ;

1 2109 Dallas an~ Population health Microbiolo~cal Safety ofQonor Bi:east particularly bile, salt-stimulated lipase. The Pop Sciences * .- I I

Sciences Milk - treatments being tested are HTSt and LTLT  :

I, pasteurization, high pressure processing, gamma I I

.. cell irradiation. and.UV-C exposure. .,

- I

- i Det:erntiruµ:ion of di.1Ierent isotopes in variable 1

2no Stewart-Smith ., *sample counting '. - I' samples.

1 2111 . Torrin Ru~ers AriAr Geochronology

  • Lunar/solar system chronoloizy. .. 'NASA i INAA to determine provenance or pottery from the i

,2112 Carpenter University o'rMichigan INAA., of Formative Zapotec_Ceramics ,., _, Valley of Oaxaca. .. - .'

Greenberry Industrial Greenberry Industrial :

2113 Mills ' Bechtel-Special Relief Devices Radfatio~ aging testing Lt.C .- '.

LLC We do a great deal of work with steriie*plant tissue  :

I

\

I cultures, mostly needing to use non-sterile plants*  ; I Department of Forest for experiments. Determine if would it be possible i2114. Strauss ~ste'm.s' .and Steriliz.ation of Plant.tissue cultures ..

to do a time/dose series where we see at what  :

Society

dos~ we gt:t aµ microbial contaminants killed but I

-*- *- the plants are still viable.

I I

AriAr analysis for age dating of Geologic i2H5

.. Scao LS~-CNRS Age dating o_f geologic materials

.. materials.

- ' µ;CE-CI':1RS i

                                                                                      • ** Table Vl.2 (continued)

Listing of Major Research and Service Projects Preformed or in Progress at the Radiation Center and Their Funding Agencies

,Project Users Organization Name Project Title Description Funding We would like to determine if the oligomerization I of uranyl peroxide can be driven by radiation,

' in solution. We will prepare solutions of lithium 1

' Determine if the oligomerization of uranyl triperoxide monomers and apply different

  • Department of Department of
  • 2116 Nyman uranyl peroxide can be driven by radiation doses (time of radiation) until change is Chemistry'. Chemistry radiation observed by visual inspection and spectroscopi9 characterization. We estimate 3 samples, irradiated for one day, and TBD for the other two samples.

I Irradiation of all will start simultaneously.

I 1bis project seeks to reduce the size, weight

I and thermal losses from high temperature solar I

receivers by the application on microchannel heat transfer technology to solar receiver Sch of Mech/Ind/Mfg High-Flux Microchannel Receiver design. Our o_bjective is to design and test on-2117 Fronk Engr Development sun a supercritical CO2 n:µcrochannel receiver

' commercial module_ operating at a fluid exit temperature of 720 "C capable absorbing an I average flux of 140 W/cm2 with a receiver  !

efficiency of 90 percent or higher.

Oregon State Use of beam quality indicators to categorize the

2118 Reese NRF Beam Purity University NRFbeam.

I University of INAA to determine trace-element composition of 2119 Blackmore Cambridge INAA of Korean Ceramics Korean archaeological ceramics. *

  • I

' . Using the in situ TEM ion irradiation facility at Argonne National Laboratory, we already I observed He ions (simulating alpha-particles) induced annealing effects on 80 MeV ion tracks i

Institute of Tibetan (simulating fission tracks) in apatite. For the next I Plateau Research, Alpha-particle induced annealing effects step, we are planning to us_e chemical etching to Chinese Academy of 2120 Li Chinese Academy of offission tracks in apatite further confirm the alpha-annealing effects on Sciences  :

Sciences real fission tracks. Neutron-induced fission tracks I are essential to the etching experiments because neutron-induced fission tracks, as compared to natuially occurring fission tracks, have no thermal N . history ( or thermal annealing effects).

0 I I-" I Beijing Research Beijing Research ID Fission track analysis to determine U 2121 Jia lnstitue of Uranium Fision track dating of areas of South China. lnstitue of Uranium N content in South China 0

Geology Geology N I I 0 Beijing Research I

Ar-Ar analysis for age dating of geologic Ar-Ar analysis for age dating of geologic materials

  • 2122 Jia lnstitue of Uranium materials. (solid rock grains and minerals).

jGeology

-:--------------,,-....,,...--------------,--...,...---,--....,.,..-------:-e----------.,.---~

. .Jable.Vl.2 (continued) _ _

5" Listing of:Major Re,earch and Service Projects_ Pr~formed or in Progr_ess E at the Radiation Center and Their-Funding Agencies

  • Q)
0 'Project Users . Organiz.ation Name . ProjectTitle Description  ; ., Ftmd'ip.g . i Cl)

"C 0

I i

.. This research will test the effect of three

'. I

i. I i '. , different soil textures and mineralogy on th'e

' bioavailability of aminomethylphosphonic acid '

to soil microorganisms. Different concentrations

' ofAMPAwill be*applied to soil, and chemical .'

I , Effect of soihype on bioavailability Sch of Environ &

Sch *ofEnvIT9:i;t & -

extractions and microbial properties will be *

2123 Dick of aminomethylphosphonic acid to Natural Res I Natural Res measured at different time intervals. Chemical .,

I p:ticroorganisms "

I

! " extractions froni sterilized and unsterilized soil I *samples will be compared at each time interval to J

. ' determine the chemical vs. biological degradation effects.

Multiple images*of.carbon steel balance-valve with 2125 IMarksthaler Jensen Hughes NRF Images ofBalance,Valve Jensen Hughes EPDM rubber o~rings.

The main objective of the project is to induce. ..

., -random mutations in elite diploid cool season /

grass varieties.'It is anticipated that some of these '

Cool Season Grasses Mutatuion . random mutatipns coaj<;i, have economic value Barenbrug USA:

212{i Runde .. Barenburg . "'

Breed,ing Project . ' I and could be commercialized. The species ~ed in the project will be AnnualRyegtass, Perennial i Rverniss. Italian RveJ;.l;raSS and Meadow Fescue. i Oregon State INAA.to deterntjne elemental: concentrations in 1

2129 Torres University_

" Efemental Analysis qf Marine s*ents marine sediments from S. America

  • OSUCEOAS "I

INAA to determine ch~mical composition of I I 1 µniversity at Albany, Geochemical1 analysis of clays' an'd.. '

'.213Q Perei'Rodriguez ~tural clays and ceramics from the Mixteca Alta, .,

s:uNY cerami~s from Oaxaca Oaxaca Mexico. -*

I

.. *. Developing radiation hardened electronics *. \

integrated with inertial .sensors (i.e. gyroscopes

  • InertialWave Inc.

I

2132 Pqpp ln{lftiiµWave Inc: Hardened Electronics Testing ' -

and accelerometers) in supporlofNASA

  • I I

interplanetarv space missions. ..

I We are studying the e~ects of northern clim~

  • on the attenuation time ofRotenone as well as ,  ;

University of Alaska, The Effects ofRotenone on Freshwater 2133 . Briggs the effects Rotenone has 6ri freshwater microbes.

  • University of Alaska Anchorage Microoof Our.project plans to determine if there is biotic -

I I ~ "

degradation occurring with Rotenone. *_ . '

j envirosure Solutions,  : Determine isotope and activity of materials from

!2134 ' 1\vaddell . - Isotopic Deuirmjnation of }4aterial received samples.

I LLC I

. ' ,. . _envirosure Soh,rtions, i LLC I

. University of University of I

'2135

  • Pomell!!: . Apatite Fis_sh:m Track * . ~patite fiss_ion track, standards for zeta calibration. Innsbruck  :

Ii:uisbruck Oregon State *Soil analysis by INAA:for.Uranium/Thorium: '

,2J36 Higley Universitv INAAof~ Site Soil~ concentration assessment. .. . l I

. Table Vl.2 (continued), .

  • Listing of Major Research and Service Projects Preformed or in Progress at the Radiation Center and Their Funding Agencies I  :

Project Users Organization Name Project Title . :Description -

Funding l 1

New Mexico Bureau Fission-track analysis of apatite from mountain I

!2137 Kelley Basin and ~ge NSF New Mexico Tech ofGeolol!V rcmges in southwestern New Mexico. . '.

I' .. This project will result in new geological age '.

determinations by the 40Ar/39Ar method for I potassium-bearing silicate minerals (including I hornblende, muscovite, biotite and orthoclase), I 40Ar/39Ar dating of mineral samples

'.2138 Hames Auburn University along with basalt whole rock samples, in Auburn University_

from orogenic belts and mineral deposits

the Auburn Noble Isotope Mass Analysis
  • I I

I Laboratory (ANIMAL). This project is for scientific investigation of Earth's history, and has I aoolications to mining industries.

Ar/Ar Thermochronology of Hawaiian lava f

I

,,2139 Grove Stanford University Ar/Ar Thermochronology (IRR 16X) Stanford Univ~ity samples.

I Neutron radiography will be used to examine .  !

coupons of stainless steal alloys that have be I Oregon State Us of neutron radiography to examine I i2140 Weiss University hydrogen content in steal alloys exposed to a hydrogen en\fironment on one surface. The content and depth profile of the I

I hydrogen will be determined. * . '

Oregon State Neutron radiography imaging ofNiCd battery to ,*

12141 Akey NRF .Imaging of Battery I

University. . - . obtain data on its construction.

Fast neutron irradiation or geological samples .

I I "

~ewMexi~ t9 primarily tr:ansmute 39K to 39Ar for the  !

Irradiation of samples for 40Ar/39Ar NM Bureau of 12142 Heizlei- Institue of Mining & purposes of rock and mineral dating .. Samples are '

geochronology for NM Tech Geology

! Technology for academic geological investigations requiring '

) knowledge of a11:e and/or thermal historv.

' Oregon State Elemental composition of ceramics from Rome QSU Crop and Soil

!2143 Noller INAA of Roman Ceramics r I University viaINAA. Science I

We analyze a variety of geological samples for '

I "

Ar Geochronology for the Earth their 40Ar/39Ar ages, inc:luding samples for

/2144 Hemming Columbia University Columbia Univeristy I Sciences (AGES) external collaborators and for internal *grant-I . sunnorted research.

I Neutron irradiation requested for 40Ar/39Ar I U.S. Geological USGSArgon

2145 Morgan 40 Ar/39Ar Geochronology* geochronology. Will use 39K,(n,p) 39Ar reaction I Survey Geochronology N to determine a!!es on rocks and minerals. I 0

1.0 I Menlo Park Geochronology uses 40Ar/39Ar ,

I techniques to date materials for geologic hazards, N

I

. U.S. Geological mapping, tectonic and IJ?-ineral resource projects . Menlo Park I 0 ;2146 Calvert 40 Ar/39Ar Geochronology Survey The method requires fast-neutron irradiation of Geochronology N

0 I

! separates from volcanic, plutonic, sedimentary and I ~

metamorphic rocks to convert 39K to 39Ar.

I I 0

0 A
E 0

Table Vl.2 (continued)  ::0 l>

J Listing of Major Research and Service Projects Preformed or in Progress A
J r::

OJ at the Radiation Center and Their Funding Agencies

c ro Project Users Organization Name Project Title Description Funding

"'O 0

i. The main aim of this project is the complex study of the Siberian Traps Large Igneous Province (LIP), the typical example ofLIPs. Investigation of such provinces is of both fundamental Shmidt Institute of scientific and applied importance, due to needs Shmidt Institute of 2147 Veselovskiy Thermal history of Siberian platform Physics of the Earth Physics of the Earth for understanding of ,reasons of the intraplate magmatic *activity, revealing the possible influence of the intense volcanism to the biotic hazards, and explanation of the origin of the unique Pt-Cu-Ni deposits related to the Siberian Traps, Oregon State Using PGNAA to determine low Z elements found 2148 Reese PGNAA of Neonatal fluid Crystal Universitv in crvstaline material from filtered neonatal fluid.

Examination of neutron activation in titanium 2149* Vanderstelt Nray Services, Inc. Titanium Trubine Blade Activation Nray Services, Inc.

turbine blades from neutron radiography.

Irradiation of potassium-bearing minerals that will U.S. Geological U.S. Geological Survey-RestonAr/Ar be dated by the Ar/Ar method at the USGS Reston U.S. Geological 2150 McAleer Geochronology Laboratory Argon Geochronology Laboratory. The samples Society Survey are from diverse localities and of diverse age.

Benzo[a]pyrene Toxicokinetics: Impact Oregon State Oregon State To identify the role of dietary and microbrial-2151 Williams of Indoles from Diet or Microbial University EMT University derived indoles in mice.

Trvptophan Metabolism" Measurement of fission product yeild of fissile Lawrence Livermore Lawrence Livennore 2152 Burke *Fission Product Yield Measurement and fertile materials through fission reactions with National Laboratory National Laboratory I gamma spectroscopy, Neutron Radiography to Image Carbor:i Using neutron radiography to look at pressurized 2153 Quinn Solidia Technologies Solidia Technologies Dioxide in Concrete CO2 in concrete that is curinll.

Insights into the Long-Term Mass Environmental and Sub-task: Assessing the biotransformation of per Oregon State 2154 Field Discharge & Transformation of AFFF in University EMT Molecular Toxicology and polyfluoroalkyl substances.

the Unsaturated Zone Identification of any and/or quantification ofany 2155 Turner Selmet, Inc. Sludge Radioisotope Identification Selmet, Inc.

radioisotopes in sludge material.

University of Neutron irradiation of geologic material for noble University of 2157 Fawcett. MN2019a Manchester gas analysis and dating. Manchester Reconstruction of the cooling histories of the surface rocks that comprise the Balkanides Thermocbronological reconstruction of mountains in Bulgaria by modeling the observed Sofia University 2158 Balkanska Sofia University the tectonic evolution of the Balk1llli.des FT and other thermochronologic data Placement constraints on mountain building and tectonic processes of the Balkanides region .

Table Vl.2 (continued)

Listing of Major Research and Service Projects Preformed or in Progress

  • at the Radiation Center and Their Funding Agencies
I Project Users Organization Name Project Title Description Funding Department of University of Arizona 40Ar/39Ar Irradiation rock & mineral samples for 40Ar/39Ar

.2160 Schaen University of Arizona Geosciences geochronology dating. (

NAA Qf clays to_ determine radioactivity level I for future neutron radiography work. This will 2161 Torina Museo Egizio NAAofClays determine/estimate how long the samples will  :

need to be held prior to free release.

Role ofmicrobiota in the effects of I Oregon State To address the role of micro biota in fatty liver Oregon State ,

2162 Jump polyunsaturated fatty acids (PUFA) on_

University disease and in beneficial effect of PUFA on liver. University I liver The main idea is to introduce gamma rays to tissue L cultures of 3 potato varieties in a bid to ipduce

  • I mutations to the plants. There are certain qualities_

I

/ characteristics we hope will be mutated and so, I upon inducement with gamma radiation, we will I Oregon State evaluate the plants (if they survive the mutation)  :

2163 Sathuvalli Dept of Horticulture Gamma irradiation- of potatoes University for those qualities. The first stage is to ascertain I Horticulture I the optimum racljation dosage for the 3 varieties I

' under evaluation. A second stage will come _

' - up where the potatoes will be evaluated basc;xl '

on information from the firsri.e. the optimum -,!

radiation dosage, Irradiation of apatite grains mounted in epoxy for 2164 Goddard Rowan University ATR Irradiation Rowan University I fission track analysis at Rowan University.  :

L A set of 5 polymers (EPDM, PTFE, PCTFE, PFA, PAI) used in common spaceflight applications are "

' NASA Marshall Space to be exposed to the mixed neutron/gamma field of

2165 Caffrey Nuclear Propulsion Polymer Tests the OSTR in order to evaluate changes in material NASA i Flight Center )

properties. The current test includes a total of 60 'microdogbone' ASTM D638 Type V tensile soecimens. L 2166 Kampfer Materion Corp. Trace-element analysis of Be powder. INAA to determine U content ofBe*powder. Materion Corp.

I

, Oregon State Use of neutron radiography to examine I

  • 2167 Reese University Neutron Radiography of Artifacts  :

archaeological artifacts.

N 0

I-"

lO N

0 N

0 :E 0

0 A

)>

  • -* Table*Vl.2 (continued).

C:

OJ Listjng* of Major Research and Service Projects Pr~formed o*r in Progress*

It)

-_ - at the Radiation Center and Their Funding*Agencies -

"C ~

i 0

i.
  • Project lJs~ -* .I ~ t i ~ n Niµne Project Title. Descripti,oii , Funding J l

- We are trying to isolate th~ effects that i

' bio:&h::ri growtl(and fouling has on sorption

  • 1

" , kin~tlcs, breakthrough, and desorption in

  • - -* wicked coltJmns of two differept proprietary The Effects ofBiofilms in elm 'adsorbents:By looking at the data for i

-- Oregon State Oregon State I 2168 *. Radniecki testing of'sorbents (o.r removal: of Cu, triplicate columns with and without biofihns Vniversity CBEE

  • University CBEE .

I Zn an~ PFAS's from Storwater - enriched from the OGSIR facility in Avery '

I'

. parJs we hope fo isolate the effects that -

naturally occµring biofilms* have on- sorption *-

I,* ,-

removal of PFASs, *zinc and copper in l

I

  • I - I stormwater. '

Environmental and PFAS Compounds_ in the INAA to determine total fluorine content in Oregoll' State I

!21,69' Field

  • Molecular Toxicology Environment -, .consumer products and the environment - Uniyersity I
" Testing electrical coaductivity changes of

- - i materials while monitoring temperatures of I Thetmoelectric Cooler Conductivity I

'2170 Howe 'Howe.Industries .. device and ambient conditions. Power will be- Howe Industries I

.. , Experiment -_ --- '

stepped *at various levels to determine these '

oarametei- chani;i;es.  :

I I

We would. like to get tpese seeds irradiated .

    • I I

I I ,_ .for inducing gamma irradiation-,induced I Department of Plant University of - I Gamma induced chromosomal chromosomal breaks in CS and MOY-wheats. I 2171 Tiwari Science and Landscape Maryland College I Architecture breaks in CS and MOV wheats It will allow us- to. map targeted. candidate Park - J

' genes 'in low recombination regions and will help' iii overall :wheat improvement. I I

  • I -WORK Figure Vl.1 S~mmary of th~ Types of Radiological lnstru.mentation Calibrated to Support the OSU
    • " TRIGA Reactor and Radiation Center
    • 45 40 35 30 25 20 15 10 5

0 Alpha GM ION Micro Personal Air Detectors Detectors Chambers Meters Dosimeters Samplers

  • , **-. * * , Table VIA  :- . *
  • 1. ;Sµmrri,~ry, ~fR~~~-~l~gi~af lnstrum~n~~tion *.
  • -: Calibrated to *support Other"Agend~s * . *
  • - - . - - - - - . . - - - - - - - , - - - - - - - L--[Ag-=e_n~.cy:..;_*_*_"_*_**___:__:--'-----'---__ * *_*_*--+-'-~~u_._m._be-r_.;._o_-f_C_al_ib_ra_ti_o_ns,
  • ! ** :*  :** * ,Tab,le Vl.3 * ** . * '. ic~I~bia Men;iorial#ospital :- - . 2
  • sJ~:mary of Radiological 11'.lstrumentati~n\ _:..:_jc_;_ol_um_b:._ia_>S-tee--,,,-1c;:;-\iSilll~ ** -.;_g_._,.:.....,,,.,.,......,,..---t---:----3-,-_-------:
  • <:alibrate'cl tq.S1,1pport osu Pep*cutments *: !Do~-Ev~, ovif  :- 2
  • . ;9syDepartment. :* -*_ -_: Num.J:>en>fCalibrations: '-:EP_'A....a:_;....:_*i-_.....:_--~------+----:-'~~------.--:~ .

1 ..

  • I Radiatjon: Safety Offi~e "., * * .*
  • 13 ... '. J:Fire Marshall/.Hazmat 78
  • I Yet Me<F 1 -* - *f...-,'- . ~ - - .__:._** - - - ' - - *~ ' - ' -:-.--.-;-.~---t:------;---;-------;--: . i
  • ! Total .1~: \-:--:J~---:-.cf_R ,, 5

__o__~-~e___H_o-=-_s_pi-:-~-:---:_-.-,-_-,.-,.--:-----tc--...,....,...,----:----:-;--;-;; ... '

jl-Iealth Dtvmop. .: ,.

  • 102

. : *- 1'

'.1-

~

~DOT_ - .- . 4
  • l
  • - ~rre__:_goo-+H-~-~-~-d-,-Sc-ie~n~c~~-.~&-~-y~-ey-_-.-f-:---;--,-,~-----,,.l 58*
  • !PSU ** - * ** -

!,_I_:_*_..:._,:_ ___:__-,-.,...__:.__ _--;--j-----;--........cL-~~~* . 7 * * * * - ~ II

~

  • !Nv~r~:end Sand& Gravei:* .~: -, *. * ,: *.. 2 -1
  • ~,S-a~_em_H __o_s-pi-utl:-*-. ...,.::--'-~----,--,-+-----:-.-.)-9--:--:-:---;j
  • Isam~ Health ,
  • 32
  • ~~.o..:. .ta.. :. l. :. .'----:,.,...-.__.:_:_ ... -,--:--------t-,-_-:--.:-: .. ~3~23--.....,--,
  • 2019*~ 2020

-W-ords **

. Pu.blications Al Shehri, A., & Gudmundsson, A. (2019). Unsupervised classification of lava flows in Harrat Lunayyir using remote sensing and GIS. Arabian Journal of Bindeman, I., Leonov, V., Colon, D., Rogozin, A.,

Shipley, N., Jicha, B., Loewen, M., Gerya, T.

(2019). Isotopic and petrologic investigation, Geosciences, 12(16), 522. doi:10.1007/s12517-019-4707-3 .

and a thermomechanical model of genesis of large-volume rhyolites in arc environments: **

Alfaro, A., Gazel, E., Jicha, B., Rasbury, T. (revised version Karymshina volcanic complex, Kamchatka, submitted). Unravelling the genesis of young Russia Frontiers in Ear:th Science, 6.

continental-arc shoshonites in the Talamanca doi:10.3389/feart.2018.00238 Cordillera, Costa Rica. Lithos.

Balestrieri, M. L., Olivetti, V., Rossetti, F., Gautheron, Bray, T. L., & Mine, L. (submitted, 2020). Imperial Inca-style Pottery from Ecuador: Insights into Provenance and Production using INAA and C., Catto', S., & Zattin, M. (in press, 2020).

Topography, structural and exhumation history of the Admiralty Mountains region, northern Victoria Ceramic Petrography. Journal of Archaeological Science Reports. **

Land, Antarctica. Geoscience Frontiers.

Balkanska, E., Georgiev, S., Kounov, A., Tagami, T., &

Buchs, D. M., Coombs, H., Irving, D., Wang, J., Koppers, A., Miranda, R., Coronado, M., Tapia, A., &

Pitchford, S. (2019). Volcanic shutdown of Sueoka, S. (submitted, under revision). Fission-track analysis using LA-ICP-MS: techniques and the Panama canal area following breakup of procedures adopted at the new low-temperature the Farallon plate. Lithos, 334-335, 190-204.

thermochronology laboratory in Bulgaria Comptes doi: 10.1016/j.lithos.2019.02.016 rendus de l'Academie bulgare des Sciences. Buchs, D. M., Irving, D., Coombs, H., Miranda, R., Wang, J., Coronado, M., Arrocha, R., Lacerda, M., Goff, Behar, N., Shaar, R., Thuxe, L., Asefaw, H., Ebert, Y.,

C., Almengor, E., Portugal, E., Franceschi, P.,

Heimann, A., Koppers, A. A. P., & Ron, H. (2019).

Paleomagnetism and Paleosecular Variations From Chichaco, E., & Redwood, S. D. (2019). Volcanic contribution to emerge~ce of Central Panama in the Plio-Pleistocene Golan Heights Volcanic Plateau, Israel. Geochemistry, Geophysics, Geosystems, 20(9), 4319-4335. doi:10.1029/2019GC008479 the Early Miocene. Scientific Reports, 9(1), 1417.

doi: 10.1038/s41598-018-37790-2 **

Bettinardi, D. J., Brown, M.A., Paulenova, A., Tsai, Y., &

Tkac, P. (submitted, in review). Separation of Re/

Burberry, C._ M., Elkins, L., Hoang, N., Le DucAnh, &

Dinh, S. Q. (preprint, 2019). Neogene-Recent Reactivation of Jurassic-age Faults in Southern Mo for the Determination of Ultratrace Re Content.

Separation Science and Technology. Vietnam, with Implications for the Extrusion of Indochina EarthArXiv. doi: 10.31223/osf.io/

Bettinardi, D. J., Paulenova, A., & Tkac, P. (accepted, *2020).

d936q Speciation ofMolybdenum(VI) in Chloride Media at Elevated Mo Concentrations. ACS Omega Cahoon, E. B., Streck, M. J., Koppers, A. P., & Miggins, D. P. (2020). Reshuffling the Columbia River Journal.

Basalt Chronology: Picture Gorge Basalt, the Bhattacharya, J.P.; Miall, A., Ferron, C., Gabriel, J., earliest- and longest-erupting formation. Geology.

Randazzo, N., Jicha, B.R., Singer, B.S. (2019).

doi: 10.1130/G47122.1 11.IDe-stratigraphy in point sourced river deltas:

application to sediment budgets,- shelf construction, Canada, A. S., Cassel, E. J., Stockli, D. F., Smith, M. E.,

Jicha; B. R., & Singer, B. S. (2020). Accelerating and paleo-storm records. Earth Science Reviews

' exhumation in the Eocene North American 199. doi: 10.1016/j.earscirev2019.102985 Cordilleran hinterland: Implications from detrital zircon (U-Th)/(He-Pb) double dating. GSA Annual. Report Bulletin, 132, 198-214. doi:10.1130/B35160.l

    • WORDS
    • Canada, A.S., Cassel, E.J., McGrew, A.J., Smith, M.E.,

Stockli, D-.F., Foland, K.A., Jicha, B.R., Singer, B.S.

Fernandez, ML; Mazzoli, S; Zattin, M; Savignano, E; Genge, M C; Tavani, S; Garrone, A; Franchini, M. (2020).

    • (2019). Eocene exhumation and extensional basin formation in the Copper Mountains, Nevada, U.S.A.

Jurassic hydrothermal mineraliz.ation and Cretaceous-Tertiary exhumation in the foreland of the southern Patagonian Andes: new constraints from La Paloma Geosphere, 15, 1-21. doi:10.1130/GES02101.1 Cavazza, W., Albino, I., Galoyan, G ., Zattin, M., & Catto', area, Deseado Massif: Argentina. Tectonophysics, S. (2019).. Continental accretion and incremental 775, 228302 .

    • deformation in *the thermochronologic evolution of the Lesser Caucasus. Geoscience Frontiers, 10, 2189-2202. doi:10.1016/j.gsf.2019.02.007 Gabet, E. J., & Miggins, D. P. (2020). Minimal net incision of the northern Sierra Nevada (California, USA) since the Eocene/early Oligocene. Geology. doi:10.1130/
    • Chako Tchamab'e, B.,-Carrasco-Nufl.ez, G., Miggins, D. P., &

N'emeth, K. (2020). Late Pleistocene to Holocene

  • G47902.1 Garnier, B., Tlkoff, B., Beltet6n, O.F., Jicha, B., DeMets; C.,
    • activity of Aichi chica maar volcano, eastern Trans-Mexican Volcanic Belt Journal of South American Earth Sciences, 97, 102404. doi:10.1016/j.

'Consenza-Muralles, B., Hernandez, D., Marroquin, G., Mixco, L., Hernandez, W. (revised version submitted). An integrated structural and GPS study

      • jsames.2019 .102404 Channell, J. T., Singer, B. S., & Jicha, B. R. (2020).

of the Jalpatagua Fault, southeastern Guatemala.

Geosphere.

    • TIIlling of Quaternary geomagnetic reversals and excursions in volcanic and sedimentary archives .

Quaternary Science Reviews, 228. doi: 10.1016/j.

Gem;:alio@u-K~u, G., Uslular, G., Danfik, M., Koppers, A., Miggins, D. P., Friedrichs, B., & Schmitt, A. K. (2020). UTh disequilibrium, (UTh)/He

    • quascirev.2019 .106114 Clague, J J; Barendregt, R W; Menounos, B; Roberts, NJ; and 40Ar/39Ar geochronology of distal Nisyros Kyra tephra deposits on Da~ peninsula (SW Anatolia). Quaternary Geochronology, 55, 101033.

Rabassa, J; Martinez, O; Ercolano, B; Corbella, H; Hemming, S R;. (2020). Pliocene and Early doi: 10.1016/j.quageo.2019.101033 Pleistocene glaciatiqn and landscape evolution Genise, J.F., Bellosi, E.S., Sarzetti, L.C., Krause, J.M., Dinghi,

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Cantil, L.F., Jicha, B.R. (2020). 100 Ma sweat bee nests: Early and rapid co-diversification of crown

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San Francisco, California: AGU fall meeting.

Cooper Boemmels, J., Crespi, J., and Webb, L.E. (2019). Early Zhang, L; Weinberg, RF; Yang, L-Q; Groves, DI; Sai, S-X; Cretaceous postrift evolution of the eastern North Matchan, E; Phillips, D; Kohn, B P; Miggins, D P; American margin: Insights from the New England-Liu, Y; Deng, J;. (2020). Mesozoic Orogenic Gold Mineralization in the Jiaodong Peninsula, China:

A Focused Event at 120 2 Ma During Cooling of Quebec igneous province. Geological Society of America Abstracts with Programs, 51(5). doi:10.1130/

abs/2019AM-336121 Pregold Granite Intrusions. Economic Geology, 115(2), 415-441. doi:10.5382/econgeo.4716 Cooper-Boemmels, J., Cresp~ J., Amidon, W., Fleming, T.,

and Webb, L.E. (2020). The western New England- **

Presentations Quebec igneous province of Vermont and New York: an example ofpostrift magmatism and normal faulting from the northern Appalachians. Geological Balkanska, E., Georgiev, S., Kounov, A., Tagam~ T., &

Sueoka, S. (n.d.). Fission-track analysis using LA-Society of America Abstracts with Programs.

doi: 10. l 130/abs/2020SE-344836 ICP-MS: laboratory procedures adopted at joint Low-temperature Thermochronology laboratory at Derycke, A., Gautheron, C., Genge, M. C., Zattin, M, Mazzol~

S., Witt, C., & Marquez, M. (24-26 September 2019).

Southern Patagonia fore land (44 - 48° S) evolution: **

Sofia University and Geological Institute, BAS.

insight from low-temperature thermochronological approach. Quito: 8th International Symposium on Andean Geodynamics.

Ann.ual Report

    • -woRDS
    • Fairchild, M. E., Rivera, T. A., & Jicha, B. R. (22-25 September 2019). Testing the basalt-rhyolite Holliday, McKenna, Rivera, Tiffany A., Jicha, B.R. (22-25 September 2019). Constraining_the ages of the
    • connection of the Beaver Ridge volcanic field, Utah .

Phoenix, Arizona: GSA annual meeting .

Markagunt and Sevier mega gravity slides, Utah.

Phoenix, Arizona: GSA annual meeting.

      • Ferron, C., Bhattcharya, J.P., Matthews, W.A., Lin, W.,

Sandeep, S., Singer,B.S., Jicha, B.R. (22-25

  • September 2019). Forebulge control on drainage Jicha, B. R., & Garcia, M. 0. (21-26 June 2020). Diffuse volcanism along the Northwest Hawaiian Ridge prior to the 25 Ma major Pacific Plate
    • divides using detrital zircons -- Late Cretaceous Gallup and Torrivio sandstones, New Mexico.

Phoenix, Arizona: GSA annual meeting.

reorganization. Honolulu, Hawaii: Goldschmidt Meeting .

Jicha,RR., Yogodzinski, G., Hoernle, K., Hauff, F.,

Genge, M. C., Franchini, M., Gautheron, C., Mazzoli, S., Portnyagin, M., Werner, R., Bezard, R. (22-25 Savignano, E., & Zattin, M. (24-26 September September 2019). New 40Ar/39Ar age constraints

    • 2019). Meso-Cenozoic exhumation of Patagonia between latitudes 40 and 45° S constrained by low-temperature thennochronology. Quito: 8th from extensive dredging of Murray Canyon, western Aleutians. Phoenix, Arizona: GSA annual meeting.

Kay, S. M, Jicha, B. R., Yogodzinski, G. M., & Tibbett, A.

International Symposium on Andean Geodynamics . K. (9-13 December 2019). M~atic Clues to the Goodwin, L.B., Feinberg, J., Hoehn, J. Longchamp, M., Distinctive Tertiary Evolution of the Attu Region of

    • Smith, DM., Jicha, B.R., Singer, B.S., Barrigan, C., Heizler, M.T., Flowers, R., Metcalf, J.R. (22-25 September 2019). Eppir si*mouve: Miocene the Western Aleutian Arc. San Francisco, California:

AGU fall meeting.

Klepeis, K.A., Schwartz, J.J., Miranda, E.A., Webb, LE.,

    • pseudotachylyte veins preserve a record of earthquakes >5.5 on low-angle normal faults.

Stowell, H.H., and Lindquist, P. (2019). Initiation and growth of steep transpressional shear zones

  • - Phoenix, Arizona: GSA annual meeting. through a 65 km thick section of continental crust in Herrero-Bervera, E., & Jicha, B. R. (9-13 December 2019). SW New Zealand'. Geological Society of America Full Vector and 40Ar/39Ar Study of an Excursion Abstracts with Programs, 51(5). doi:10.1130/

Recorded by the K.aupo flow, Honolulu Volcanic abs/20 l 9AM-338375 Series, Oahu, Hawaii, USA: A new Excursion or just Medaris, L.G. Jr., Malone, D.H., Hill, G.C., Singer, B.S.,

a Record of the Hilina Pali Episode? San Francisco, Jicha, B.R., Van Lankvelt, A., Williams, M.L.,

California: AGU fall meeting . Reiners, P.W. (22-25 September2019). The Hoernle K., Jicha, B., O'Connor J., Yogodzinski G., Mnller, deon 14 Wolf River Tectonomagmatic event:

    • R.D., Hauff, F., Werner, R., Portnyagin M., Bezard, R.* (21-26 June 2020). Pacific-wide rejuvenated volcanism related to subduction initiation and .

A midcontinental link between the Picuris and Pinwarian orogenies. Phoenix, Arizona: GSA annual meeting.

    • formation of the Hawaiian-Emperor Ben~I.

Honol~lu, Hawaii: Goldschmidt Meeting.

Mine, L., Wmter, M., & Cira Martinez-Lopez, C. (April 2020). Intra-valley Exchange before the Rise of

    • Hoernle, K., Jicha, B.R., Muller, D., Portnyagin, M, Werner, R., Hauff, F., Bezard, R., HOfig, T.W., Yogodzinski, G. (9-13 December 2019). Role of the Aleutian MonteAlban--New Data from Trace-element Analyses of Rosario Phase Ceramics. Austin, Texas: 85th Annual Meeting, Society for American
    • Arc and NW Pacific seafloor in Pacific-wide plate reorga.niz.ation in the Paleogene. San Francisco, California: AGU fall meeting.

Archaeology. (Accepted but not presented due to COVID-19).

Mixon,-E. E., Singer, B. S., Jicha, B. R., Marcott, S. A.,

HOfig, T.W., Portnyagin M., Hoernle K., Hauff, F., Jicha, Moreno, H., & Ramirez, A. (9-13 December B.R., Wartho, J.-A., Van den Bogaard, P., Garbe- 2019). 2019. 40Ar/39Ar Geochronology and

    • SchOnberg, D. (21-26 June 2020). More than 40 million years of oblique subduction recorded in the magmatism of the westernmost Aleutian arc.

Geochemical Evolution ofCalbuco Volcano (41 °S):

An lnve~tigation*ofTrans-Crustal Magma System Response to Glacial Loading from 0-200 ka San

    • Honolulu, Hawaii: Goldschmidt Meeting . Francisco, California: AGU fall meeting.

~

2019 '2020 ' 0

WORDS **

Oh, J.H., Sieh, K., Schonwalder Angel, D., Herrin, J.,

Jenkins, S., Jicha, B., Singer, B. (23-27 May Webb, L.E., Karabinos, P., and Klepeis, K.A. (2019).

Geochronologic evidence for Salinic thrusting and 2020). Reconstructing the eruption catalogue for the Bolaven Plateau (Laos) monogenetic volcanic Acadian reactivation of external basement massifs in western New England and ovei-printing of the **

field using satellite images, petrographic textural Ordovician Taconic thrust belt. Geological Society of analyses and geochronology. Heraklion, Crete: America Abstracts with Programs, 51 (5). doi: 10.1130/

Cities on Volcanoes Meeting. abs/2019AM-334274 Pank, K., Hansteen, T.H., Geldmacher, J., Garbe-ScMnberg, D., Jicha, B., Hoernle, K. (23-27 May 2020): Origin Webb, LE., Karabinos, P., and Klepeis, K.A. (2020). Evidence for Salinic andAcadian reactivation ofTaconic thrusts along the western Green Mountain front. Geological and evolution of the lowermost lava successions at Santorini volcano (Greece): insights from major Society of America Abstracts with Programs.

and trace element composition of rocks from the doi:10.1130/abs/2020SE-344590 submarine caldera wall. Heraklion, Crete: Cities on Volcanoes Meeting.

Students Rivera, T.A., White, C., Schmitz, M., Jicha, B.R. (22-25 September 2019). Chemically distinct, but temporally equivalent lavas in the Snake River Bettinardi, David. PhD Nuclear Science and Engineering (2020), Oregon State University.

Plain, Idaho. Phoenix, Arizona: GSA annual meeting. Bruck, Benjamin. PhD student, University ofWISconsin-Madison. (Advisor Brad Singer).

Schaen, A.J., Schoene, B., Singer, B.S., Dufek, J., Eddy, M.,

Jicha, B.R., Cottle, J.M. (22-25 September 2019).

Short duration ofrhyolite melt extraction from Couture, Jordan. MS (2019/2020), University ofAlaska-Anchorage. "Degradation of rotenone in eight lakes **

petrochronologic modelling within a young Andean on the Kenai Peninsula." (Advisor Pat Tomco).

pluton. Phoenix, Arizona: GSA annual meeting. Dreiker, Zach. BS Geology (2020), University of Vermont.

Schnalzer, K.M., Webb, L.E., and McCarthy, K. (2020). "Microstructural analyses and 40Ar/39Ar Evidence for polyphase deformation in the mylonitic zones bounding the Chester and geochronology of the Dry Hill Thrust in the Berkshire Massif." (Advisor Laura Webb).

Athens Domes, southeastern Vermont, from Genge, Marie Catherine. PhD student, University of Padova 40Ar/39Ar geochronology. Geological Society of "Structural evolution of the Central Patagonia: a America Abstracts with Programs. doi: 10.1130/ source-to-sink approach." (Advisor: Massimiliano abs/2020SE-344494 Zattin).

Singer, B. S., Jicha, B. R., & Channell, J. T. (9-13 December Karslyan, Yana. PhD Chemistry (2_020), Oregon State 2019). Leveraging astrochronology of Quaternary University.

geomagnetic reversals and excursions to constrain accuracy and precision of the 40Ar/39Ar Klug, Jacob. PhD student, University ofWISCOnsin-Madison.

(Advisor Brad Singer).

chronometer. San Francisco, California: AGU fall meeting. Knaus, Clinton. PhD candidate; Chemistry, Oregon State YllilIIl, C., Hoernle, K., Jicha, B., Hauff, F., Wallace, L. University.

(16-19 March 2020). Age and composition of lavas drilled at .IODP Exp. 375, site 1520 and 1526. Napier, New Zealand: IODP Exp. 372-375 L~ Xia PhD student, University of Padova. From bedrock to sediments: insights on Ross Sea ice-flow dynamics inferred from detrital data." (Advisor: Massimiliano workshop.

Waldman, R., Yogodzinski, G., Hauff, F., Bizimis, M., Jicha, Zattin).

L4 Youjuan. Post-doc, University ofWISconsin-Madison. **

B.R., Portnyagin, M., Werner, R., Hoernle, K.

(22-25 September 2019). Nature and significance of altered oceanic crust (AOC) of the northwest (Advisor Brad Singer).

Pacific. Phoenix, Arizona: GSA annual meeting.

Annual Report

  • I WORDS
    • McCarthy, Kyle. BS Geology (2020), University of Vermont. "Microstructural analyses and 40Ar/39Ar Spooner, Me lissa H. PhD Candidate, Nutrition Program ,

Oregon State University.

    • geochronology of shear zones along the NE margin of the Chester Dome, Vermont." (Advisor Laura Unnamed. Two PhD students, Natural History Museum of Denmark. (Michael Storey) .

Webb) .

Wang, Yu. PhD student, China University of Geosciences, Mixon, Emily. MS student, University of Wisconsin- Wuhan. "Cenozoic uplift and exhumation of SW Madison. (Advisor Brad Singer). Fujian linked to preservation of ore deposits, South

    • Moreno Yeager, Pablo. PhD student, University of Wisconsin-Madison. (Advisor Brad Singer) .

China Block: Implications from zircon and apatite fission-track thermochronological record ." (Co-advisor: Massimiliano Zattin).

Osterle, Juergen. PhD (2019), Victoria University, Wellington , New Zealand. "Thermo-tectonic Yang, Chaoqun. PhD student, China University of evolution of the Suckling-Dayman metamorphic Geosciences, Wuhan . " Provenances of Cenozoic

    • core complex, southeastern Papua New Guinea."

Schnalzer, Kristin . MS Geology (2020), University of sed iments in the Jianghan Basin and implications for the formation of the Three Gorges. " (Co-advisor:

    • Vermont. "Evidence for polyphase deformation in Massimiliano Zattin).

the shear zones bounding the Chester and Athens Domes, southeastern Vermont, from 40Ar/39Ar

    • geochronology." (Advisor Laura Webb) .
  • 2019-2020 @

Oregon State University Radiation Center, 100 Radi.ation Center, Corvallis, OR 96331 **

www.radiationcenter.oregonstate.edu a