ML15099A041

the University of Texas at Austin, Nuclear Engineering Teaching Laboratory Submits, 2014 Annual Report.

ML15099A041
Person / Time
Site:	University of Texas at Austin
Issue date:	03/31/2015
From:	Biegalski S University of Texas at Austin
To:	Office of Nuclear Reactor Regulation
References
DOE Contract No. DE-AC07-ER03919
Download: ML15099A041 (51)

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The University of Texas at AustinNuclear Engineering TeachingLaboratory2014 Annual ReportNRC Docket 50-602DOE Contract No. DE-AC07-ER0391903/2015A cz~~

2014 NETL Annual ReportDepartment of Mt-chi nical EnginceringT1 IF UNIVERSITY OF TEXAS AT AUS'iINNuclear hngun'ering Laboratory" Austin, fl'xas 78758512-_'2-537"0 -FAX 512-,'71-, 589 *ttp//wwunie, utcxas.edu/- ned/nc't.hjmn/FORWARDThe mission of the Nuclear Engineering Tcaching Laboratory at The University of Texas atAustin is to:" Educate the next generation of leaders in nuclear science and engineering." Conduct leading research at the forefront of the international nuclear community." Apply nuclear technology for solving multidisciplinary problems.* Provide service to the citizens of Texas, the U.S., and the international community.This objective is achieved by carrying out a well-balanced program of education, research,and service. The NETL research reactor supports hands-on education in reactor physics andnuclear science. In addition, students in non-nuclear fields such as physics, chemistry. andbiology use the reactor in laboratory course work. Thc NEITL is also used in educationprograms lor nuclear power plant personnel, secondary schools students and teachers. andthe general public.The NETL research reactor benefits a wide range of on-campus and off-campus users,including academic, medical. industrial, and goveniment organizations. The principalservices offered by our reactor involve material irradiation, trace element detection, materialanalysis. and radiographic analysis of objects and processes. Such services establishbeneficial links to off-campus users, expose faculty and students to multidisciplinaryresearch and commercial applications of nuclear science, and generate resources to helpsupport Nuclear IF ngincering activitics.Steven Biegalski. Ph.D., P.E.Director. Nuclear Engineering Teaching Laboratoryii3/2015 2014 NETL Annual ReportTable of ContentsTable of Contents iiiExecutive Summary v1.0 NUCLEAR ENGINEERING TEACHING LABORATORY ANNUAL REPORT 11.1 General 11.2 Purpose of the report 22.0 ORGANIZATION AND ADMINSTRATION 42.1 Level 1 52.2 Level 2 62.3 Level 3 102.4 Level 4 132.5 Other Facility Staff 132.6 Faculty and Facility users 132.7 NETL Support 153.0 FACILITY DESCRIPTION 163.1 NETL History 163.2 NETL SITE, J.J. Pickle Research Campus 163.3 NETL Building Description 174.0 UT-TRIGA MARK II RESEARCH REACTOR 184.1 Reactor Core 194.2 Reactor Reflector 194.3 Reactor Control 205.0 EXPERIMENT AND RESEARCH FACILITIES 215.1 Upper Grid Plate 7L and 3L Experiment Facilities 215.2 Central Thimble 215.3 Rotary Specimen Rack 225.4 Pneumatic Tubes 225.5 Beam Port Facilities 225.6 Other Experiment and Research Facilities 285.7 Experiment Facility Utilization 295.8 Nuclear Program Faculty Activities 316.0 OPERATING SUMMARY 346.1 Operating Experience 346.2 Unscheduled Shutdowns 346.3 Utilization 356.4 Routine Scheduled Maintenance 386.5 Corrective Maintenance 386.6 Facility Changes 406.7 Oversight & Inspections 41°°°3/2015 2014 NETL Annual Report7.0 RADIOLOGICAL SUMMARY 427.1 Summary of Radiological Exposures 437.2 Summary of Radioactive Effluents 447.3 Radiological Exposure Received by Facility Personnel and Visitors 447.4 Environmental Surveys Performed Outside the Facility 45iv3/2015 2014 NETL Annual ReportEXECUTIVE SUMMARYThe Nuclear Engineering Teaching Laboratory (NETL) facility supports the academicand research missions of The University of Texas, and has begun to provide these supportfunctions to other institutions. The environmental research and analysis services performed bythe NETL during the past year have been used to support the Sandia National Laboratories, LosAlamos National Laboratory, Oak Ridge National Laboratory, the Canadian government, theNational Oceanic and Atmospheric Administration, the University of Illinois, Texas A&MUniversity and the State of Texas.V3/2015 2014 NETL Annual Report1.0 NUCLEAR ENGINEERING TEACHING LABORATORY ANNUAL REPORTThe Nuclear Engineering Laboratory Annual Report covers the period from January throughDecember 2014. The report includes descriptions of the organization, NETL facilities, thereactor, experiment and research facilities and summaries of operations and radiological impact.1.1 GeneralThe NETL facility serves a multipurpose role, with the primary function as a "user facility" forfaculty, staff, and students of the Cockrell School of Engineering. The NETL supportsdevelopment and application of nuclear methods for researchers from other universities,government organizations and industry. The NETL provides nuclear analytic services toresearchers, industry, and other laboratories for characterization, testing and evaluation ofmaterials. The NETL provides public education through tours and demonstrations.Figure 1-1, NETL -Nuclear Engineering Teaching LaboratoryActivities at NETL are regulated by Federal and State agencies. The nuclear reactor is subject tothe terms and specifications of Nuclear Regulatory Commission (NRC) License R-129, a class104 research reactor license. A second NRC license for special nuclear materials, SNM-180,authorizes possession of a subcritical assembly, neutron sources, and various equipment. TheNETL is responsible for administration and management of both licenses. Activities at theI3/2015 2014 NETL Annual ReportUniversity using radioisotopes are conducted under a State of Texas license, L00485. Functionsof the broad license are the responsibility of the University Office of Environmental Health andSafety.1.2 Purpose of this ReportThis report meets requirements of the reactor Technical Specifications and the Department ofEnergy Fuels Assistance program, and provides an overview of the education, research, andservice programs of the NETL for the calendar year 2014.1.2.1 TRIGA II Reactor Technical SpecificationsThe NETL TRIGA II reactor Technical Specifications (section 6.6.1) requires submission of anannual report to the Nuclear Regulatory Commission. Table 1.1 correlates specifiedrequirements to the report.Table 1.1, TRIGA Mark II Technical Specification and the Annual ReportSpecification SectionA narrative summary of reactor operating experience including the energy 5.0, 6.1, 6.3produced by the reactor or the hours the reactor was critical, or both.The unscheduled shutdowns & corrective action taken to preclude recurrence 6.2Major preventive & corrective maintenance operations with safety significance 6.4Major changes in the reactor facility and procedures, tabulation of new tests orexperiments, or both, significantly different from those performed previously, 6.6including conclusions that no unreviewed safety questions were involvedA summary of radioactive effluents (nature & amount) released or discharged tothe environs beyond effective control of the university as determined at or beforethe point of such release or discharge, including to the extent practicable an 7.2estimate of individual radionuclides present in the effluent or a statement that theestimated average release after dilution or diffusion is less than 25% of theconcentration allowed or recommendedA summary of exposures received by facility personnel and visitors where suchexposures are greater than 25% of that allowed or recommended.A summarized result of environmental surveys performed outside the facility 7.423/2015 2014 NETL Annual Report1.2.2 The Department of Energy Fuels Assistance ProgramThe DOE University Fuels Assistance program (DE-AC07-05ID14517, subcontract 00078206,08/01/2008-08/31/2013) supports the facility for utilization of the reactor in a program ofeducation and training of students in nuclear science and engineering, and for faculty and studentresearch. The contract requires an annual progress report in conjunction with submittal of aMaterial Balance Report and Physical Inventory Listing report. Specific technical details of thereport (listed in Table 1.2) are sent under separate cover to the DOE with this Annual Report.Table 1.2, DOE Reactor Fuel Assistance Report RequirementsFuel usage (grams Uranium 235 & number of fuel elements)Inventory of unirradiated fuel elements in storageInventory of fuel elements in coreInventory of useable irradiated fuel elements outside of coreProjected 5-year fuel needsCurrent inventory of other nuclear material items with DOE-ID project identifier (i.e., "J")Point of contact for nuclear material accountability33/2015 2014 NETL Annual Report2.0 ORGANIZATION AND ADMINSTRATIONThe University of Texas System (UTS) was established by the Texas Constitution in 1876, andcurrently consists of nine academic universities and six health institutions. The UTS mission isto provide high-quality educational opportunities for the enhancement of the human resources ofTexas, the nation, and the world through intellectual and personal growth.The Board of Regents is the governing body for the UTS. It is composed of members appointedby the Governor and confirmed by the Senate. Terms are of six years each and staggered, withthe terms of three members expiring on February 1 of odd-numbered years. Current members ofthe current Board of Regents are listed in Table 2.1.Table 2.1The University of Texas Board for 2014Paul L. Foster, ChairmanR. Steven Hicks, Vice ChairmanMembers with term set to expire May 2015Student Regent Max RichardsMembers with term set to expire February 2017Regent Alex M. CranbergRegent Wallace L. Hall, Jr.Regent Brenda PejovichMembers with term set to expire February 2019Chairman Paul L. FosterRegent Ernest AlisedaRegent Jeffery D. HildebrandMembers with term set to expire February 2021Vice Chairman R. Steven HicksRegent David J. BeckRegent Sara Martinez Tuckerhttp://www.utsystem.edu/board-of-regents/current-regents, 03/30/2015The chief executive officer of the UTS is the Chancellor. The Chancellor has direct lineresponsibility for all aspects of UTS operations, and reports to and is responsible to the Board ofRegents. The current Chancellor is Bill McRaven.UT Austin is the flagship campus of the UTS. The facility operating license for the TRIGAMark II at the NETL is issued to the University of Texas at Austin. Figure 2-1 reflects theorganizational structure for 4 levels of line management of the NETL reactor, as identified in the43/2015 2014 NETL Annual ReportTechnical Specifications, as well as oversight functions. Other NETL resources (in addition toline management positions) include staff with specialized functions, and faculty and facilityusers. NETL support is through a combination of State allocation, research programs, andremuneration for service.School of Engineering Dean ---- --.............Reactor OversightDepartment of Mechanical CommitteeEngineering ChairRadiation Safety Nuclear Engineering Teaching -'74-----------Officer Laboratory DirectorAssociate Director[ Health Phsiist Reactor Supervisorrwi Operations S~taffReactor & Senior OperatorsFigure 2-1, Organizational Structure for the University of Texas at Ausitn TRIGA Reactor2.1 Level I PersonnelLevel 1 represents the central administrative functions of the University and the Cockrell Schoolof Engineering. The University of Texas at Austin is composed of 16 separate colleges andschools; the Cockrell School of Engineering manages eight departments with individual degreeprograms. The Nuclear Engineering Teaching Laboratory (NETL) is one of several educationand research functions within the School. Current Level 1 personnel are reported in Table 2.2.53/2015 2014 NETL Annual Report2.1.1 President, University of Texas at AustinThe President is the individual vested by the University of Texas system with responsibility forthe University of Texas at Austin.2.1.2 Executive Vice president and Provost (Provost)Research and educational programs are administered through the Office of the Executive VicePresident and Provost. Separate officers assist with the administration of research activities andacademic affairs with specific management functions delegated to the Dean of the CockrellSchool of Engineering and the Chairman of the Mechanical Engineering Department.2.1.3 Dean of the Cockrell School of EngineeringThe Dean of the Cockrell School of Engineering reports to the Provost. The School consists of 8departments and undergraduate degree programs and 12 graduate degree programs.2.1.4 Department of Mechanical Engineering ChairmanThe Chairman reports to the Dean of the Cockrell School of Engineering. The Departmentmanages 8 areas of study, including Nuclear and Radiation Engineering.Table 2.2The University of Texas at Austin Administration (Level 1)William Powers Jr., JD, PresidentGreg Fenves, PhD, Executive Vice President and ProvostGregory L. Fenves, PhD, Executive Vice President and ProvostWood, Sharon, PhD, (interim) Dean, Cockrell School of EngineeringJayathi Murthy, Chair of Department of Mechanical Engineering2.2 Level 2 PersonnelThe Nuclear Engineering Teaching Laboratory operates as a unit of the Department ofMechanical Engineering at The University of Texas. Level 2 personnel are those with direct63/2015 2014 NETL Annual Reportresponsibilities for administration and management of resources for the facility, including theChair of the Mechanical Engineering Department, the NETL Director and Associate Director.Oversight roles are provided at Level 2 by the Radiation Safety Committee, the Radiation SafetyOfficer and the Nuclear Reactor Committee. The current complement of Level 2 personnel isreported along with the NETL facility staff and the Nuclear and Radiation Engineering programfaculty in Table 2.3.Table 2.3Facility Staff& NRE FacultyNETL Facility Staff NRE FacultyDirector S. Biegalski S. BiegalskiAssociate Director P. M. Whaley S. LandsbergerReactor Supervisor M. Krause E. SchneiderHealth Physicist & Lab manager T. Tipping M. DeinhertAdministrative Associate D. JudsonElectronics Technician/ Reactor Operator L. WelchN. MohammedA. DavisJ. NavarU. ChatterjeeHealth Physics Technician J. Sims2.2.1 Director, Nuclear Engineering Teaching Laboratory (NETL Director)Nuclear Engineering Teaching Laboratory programs are directed by an engineering facultymember with academic responsibilities in nuclear engineering and research related to nuclearapplications. The Director is a member of the Cockrell School of Engineering, and theDepartment of Mechanical Engineering.2.2.2 Associate DirectorThe Associate Director is responsible for safe and effective conduct of operations andmaintenance of the TRIGA nuclear reactor. Other activities performed by the Associate Directorand staff include neutron and gamma irradiation service, operator/engineering training courses,and teaching reactor short courses. In addition to Level 3 staff, an Administrative Assistant andan Electronics Technician report to the Associate Director. Many staff functions overlap, withsignificant cooperation required.73/2015 2014 NETL Annual Report2.2.4 Safety OversightSafety oversight is provided for radiation protection and facility safety functions. A Universityof Texas Radiation Safety Committee is responsible programmatically for coordination, trainingand oversight of the University radiation protection program, with management of the programthrough a Radiation Safety Officer. Current personnel on the Radiation Safety Committee arelisted on Table 2.4.Nuclear reactor facility safety oversight is the responsibility of a Nuclear Reactor Committee; arequest has been made to the Nuclear Regulatory Commission to change the name "NuclearReactor Committee" to "Reactor Oversight Committee" to better describe the committeefunction for the University and avoid confusion with other NRC organizations. "ReactorOversight Committee" will be used in this report pending approval. Current personnel on theReactor Oversight Committee are listed on Table 2.5.Radiation Safety Committee. The Radiation Safety Committee reports to the President and hasthe broad responsibility for policies and practices regarding the license, purchase, shipment, use,monitoring, disposal and transfer of radioisotopes or sources of ionizing radiation at TheUniversity of Texas at Austin. The Committee meets at least three times each calendar year. TheCommittee is consulted by the Office of Environmental Health and Safety concerning anyunusual or exceptional action that affects the administration of the Radiation Safety Program.Table 2.4Radiation Safety CommitteeGerald W. Hoffmiann. Ph.D.. Chair, Department of PhysicsJuan M. Sanchez, Ph.D.. Vice Chair, Vice President for ResearchKevin Dalby, Ph.D., Professor, College of PharmacyW. Scott Pennington, ex-officio. Environmental Health and SafetyRick Russell, Ph.D., Associate Professor, Department of Molecular BiosciencesJohn Salsman, Director, Environmental Health and SafetyBob G. Sanders, Ph.D., Professor, Department of Molecular BiosciencesTracy Tipping, Health Physicist Laboratory Manager, Nuclear Engineering Teaching Laboratoryhttp://www.utexas.edu/research/resources/committees#rsc, 03/30/2015Radiation Safety Officer. A Radiation Safety Officer holds delegated authority of the RadiationSafety Committee in the daily implementation of policies and practices regarding the safe use ofradioisotopes and sources of radiation as determined by the Radiation Safety Committee. The83/2015 2014 NETL Annual ReportRadiation Safety Officer's responsibilities are outlined in The University of Texas at AustinRadiation Safety Manual. The Radiation Safety Officer has an ancillary function reporting to theNETL Director as required on matters of radiological protection. The Radiation Safety Programis administered through the University Office of Environmental Health and Safety.A NETL Health Physicist (Level 3) manages daily radiological protection functions at theNETL, and reports to the Radiation Safety Officer as well as the Associate Director. Thisarrangement assures independence of the Health Physicist through the Radiation Safety Officerwhile maintaining close interaction with NETL line management.Reactor Oversight Committee (ROC). The Reactor Oversight Committee (formerly known as theNuclear Reactor Committee) evaluates, reviews, and approves facility standards for safeoperation of the nuclear reactor and associated facilities. The ROC meets at least semiannually.The ROC provides reports to the Dean on matters as necessary throughout the year and submits afinal report of activities no later than the end of the spring semester. The ROC makesrecommendations to the NETL Director for enhancing the safety of nuclear reactor operations.Specific requirements in the Technical Specifications are incorporated in the committee charter,including an audit of present and planned operations. The ROC is chaired by a professor in theCockrell School of Engineering. ROC Membership varies, consisting of ex-officio andappointed positions. The Dean appoints at least three members to the Committee that represent abroad spectrum of expertise appropriate to reactor technology, including personnel external tothe School.Table 2.5Reactor Oversight Committee 2013-2014Erich Schneider (ME), ChairOzzie Bayrak (CAEE)Charlie Werth (CAEE)Steven Biegalski (ME)Lawrence R. Jacobi (External Representative)Jodi Jenkins (External Representative)Michael Krause, ex-officio (NETL)Tracy Tipping, ex-officio (NETL)Mike Whaley, ex-officio (NETL)John G. Ekerdt, ex-officioJayathi Murthy, ex-officio (ME)Scott Pennington, other (Radiation Safety Officer)http://www.engr.utexas.edu/faculty/committees/225-roc, 03/30/201593/20 15 2014 NETL Annual Report2.3 Level 3 PersonnelLevel 3 personnel are responsible for managing daily activities at the NETL. The ReactorSupervisor and Health Physicist are Level 3. The current Reactor Supervisor and HealthPhysicist are listed on Table 2.3.2.3.1 Reactor SupervisorThe Reactor Supervisor function is incorporated in a Reactor Manager position, responsible fordaily operations, maintenance, scheduling, and training. The Reactor Manager is responsible forthe maintenance and daily operations of the reactor, including coordination and performance ofactivities to meet the Technical Specifications of the reactor license. The Reactor Manager plansand coordinates emergency exercises with first responders and other local support (Austin FireDepartment, Austin/Travis County EMS, area hospitals, etc.).The Reactor Manager, assisted by Level 4 personnel and other NETL staff, implementsmodifications to reactor systems and furnishes design assistance for new experiment systems.The Reactor Manager assists initial experiment design, fabrication, and setup. The ReactorManager provides maintenance, repair support, and inventory control of computer, electronic,and mechanical equipment. The Administrative Assistant and Reactor Manager schedule andcoordinate facility tours, and support coordination of building maintenance.2.2.1 Health PhysicistThe Health Physicist function is incorporated into a Laboratory Manager position, responsiblefor radiological protection (Health Physics), safe and effective utilization of the facility (LabManagement), and research support. Each of these three functions is described below. TheLaboratory Manager is functionally responsible to the NETL Associate Director, but maintains astrong reporting relationship to the University Radiation Safety Officer and is a member of theRadiation Safety Committee. This arrangement allows the Health Physicist to operateindependent of NETL operational constraints in consideration of radiation safety.103/2015 2014 NETL Annual ReportHealth Physics. NETL is a radiological facility operating in the State of Texas under a facilityoperating license issued by the Nuclear Regulatory Commission (NRC). Radioactive materialand activities associated with operation of the reactor are regulated by the NRC, and the uses ofradioactive materials at the NETL not associated with the reactor are regulated by the TexasDepartment of State Health Services (TDSHS) Radiation Control Program. The NETL HealthPhysicist ensures operations comply with these requirements, and that personnel exposures aremaintained ALARA ("as low as is reasonably achievable"). One or more part-timeUndergraduate Research Assistant (URA) may assist as Health Physics Technicians.Lab Management. The lab management function is responsible for implementation ofoccupational safety and health programs at the NETL. The Laboratory Manager supportsUniversity educational activities through assistance to student experimenters in their projects bydemonstration of the proper radiation work techniques and controls. The Laboratory Managerparticipates in emergency planning for NETL and the City of Austin to provide basic responserequirements and conducts off-site radiation safety training to emergency response personnelsuch as the Hazardous Materials Division of the Fire Department, and Emergency MedicalServices crews.Research Support. The mission of The University of Texas at Austin is to achieve excellence inthe interrelated areas of undergraduate education, graduate education, research and publicservice. The Laboratory Manager and research staff supports the research and educationalmissions of the university at large, as well as development or support of other initiatives.The Laboratory Manager is responsible for coordinating all phases of a project, includingproposal and design, fabrication and testing, operation, evaluation, and removal/dismantlement.Researchers are generally focused on accomplishing very specific goals, and the researchsupport function ensures the NETL facilities are utilized in a safe efficient manner to producequality data. The Laboratory Manager obtains new, funded research programs to promote thecapabilities of the neutron beam projects division for academic, government and industrialorganizations and/or groups.I1I3/2015 2014 NETL Annual ReportThe NETL provides unique facilities for nuclear analytic techniques, including but notlimited to elemental analysis (instrumental neutron activation analysis, prompt gamma analysis),measurements of physical characteristics (neutron depth profiling, neutron radiography) andexperimental techniques investigating fundamental issues related to nuclear physics andcondensed matter. Nuclear analytical techniques support individual projects ranging from classassignments to measurements for faculty research.The Laboratory Manager manages the use of the five beam ports with the Texas ColdNeutron Source, Neutron Depth Profiling, Neutron Guide and Focusing System, Prompt GammaActivation Analysis Neutron Radiography and Texas Intense Positron Source. Projects aresupported in engineering, chemistry, physics, geology, biology, zoology, and other areas.Research project support includes elemental measurements for routine environmental andinnovative research projects. The neutron activation analysis technique is made available todifferent state agencies to assist with quality control of sample measurements.2.4 Level 4 PersonnelReactor Operators and Senior Reactor Operators (RO/SRO) operate and maintain the reactor andassociated facilities. An RO/SRO may operate standard reactor experiment facilities as directedby the Reactor Supervisor.2.5 Other Facility StaffIn addition to the line management positions defined in Figure 2-1, NETL staff includes anAdministrative Assistant, and Electronics Technician, and variously one or more UndergraduateResearch Assistants assigned either non-licensed maintenance support (generally but notnecessarily in training for Reactor Operator licensure) or to support the Laboratory Manager asHealth Physics Technicians and/or research support.123/2015 2014 NETL Annual Report2.6 Faculty and Facility UsersThe complement of faculty and facility users at the NETL is extremely variable. Functionallyfaculty and facility users are associated with the NETL in the capacity of academic utilization,other educational efforts, or research & service. A description of these activities follows.2.6.1 Academic UtilizationThe NETL is integrated in the Nuclear and Radiation Engineering program (NRE) of MechanicalEngineering (ME). The ME faculty complement directly supporting the nuclear educationprogram is listed in Table 2.6. Successful participation in the undergraduate program results in aBachelor of Science in Mechanical Engineering, Nuclear Engineering certification; the degree isessentially a major in Mechanical Engineering with a minor in Nuclear Engineering. AllMechanical Engineering degree requirements must be met with an additional set of specificnuclear engineering courses successfully completed.Of the five undergraduate Nuclear Engineering courses and the dozen graduate NuclearEngineering courses, five courses make extensive use of the reactor facility. Table 2.7 lists thecourses currently in the UT course catalog, many of which use the reactor and its experimentfacilities.Table 2.6University of Texas Nuclear and Radiation Engineering Program FacultyDr. Steven Biegalski, Nuclear and Radiation Engineering Associate ProfessorDr.Mark Deinert, Nuclear and Radiation Engineering, Thermal Fluid Systems, AssistantProfessorDr. Kendra M. Foltz-Biegalski, Nuclear and Radiation Engineering Research EngineerDr. Dale Klein, Associate Vice Chancellor for ResearchDr. Sheldon Landsberger, Nuclear and Radiation Engineering ProfessorDr.Mitch Pryor, Robotics Research Group Research AssociateDr. Erich Schneider, Nuclear and Radiation Engineering Assistant Professorhttps://nuclear.engr.utexas.edu/index.php/faculty-and-staff, 03/23/2014133/2015 2014 NETL Annual ReportTable 2.7, Nuclear Engineering CoursesUndergraduateME 136N, 236N: Concepts in Nuclear and Radiological EngineeringME 337C: Introduction to Nuclear Power SystemsME337F: Nuclear Environmental ProtectionME 337G: Nuclear Safety and SecurityllME 361E: Nuclear Operations and Reactor EngineeringME 361 F: Radiation and Radiation protection LaboratoryGraduateME 388C: Nuclear Power EngineeringME 388D: Nuclear Reactor Theory I"'ME 388F: Computational Methods in Radiation Transporti IME 388G: Nuclear Radiation Shieldingjl'ME 388H: Nuclear Safety and Securityl[PME 388J: Neutron Interactions and their Applications in Nuclear Science and Engineering~'1ME 388M: Mathematical Methods for Nuclear and Radiation Engineers~llME 388N: Design of Nuclear Systems I'1ME 388P: Applied Nuclear Physics~11ME 388S: Modern Trends in Nuclear and Radiation Engineering~'ME 389C: Nuclear Environmental ProtectionNE 389F: The Nuclear Fuel Cycle'llME 390F: Nuclear Analysis TechniquesME 390G: Nuclear Engineering LaboratoryME390T: Nuclear- and Radio-ChemistryNOTE[]], Academic courses with minimal or no use of the reactor facilitiesThe NRE program's graduate degrees are completely autonomous; they are Master of Science inEngineering (Concentration in Nuclear Engineering) and Doctor of Philosophy (Concentration inNuclear Engineering). Course requirements for these degrees and the qualifying examination forthe Ph.D. are separate and distinct from other areas of Mechanical Engineering. A DissertationProposal and Defense of Dissertation are required for the Ph.D. degree and acted on by a NREdissertation committee.2.6.2 Other Education EffortsThe NETL has participated in the IAEA Fellowship programs for the past decade. SeveralFellows and Visiting Scientists spend 3-6 months at the NETL per year.The Nuclear Engineering Teaching Lab also extends its facilities to two Historically BlackColleges or Universities (HBCUs). Both Hutson-Tillotson University in Austin and Florida143/2015 2014 NETL Annual ReportMemorial University in Miami Gardens, Florida have participated in this these educationalefforts.In addition to formal classes, the NETL routinely provides short courses or tours for Texasagencies, high schools and pre-college groups such as the Boy Scouts of America. Tours andspecial projects are available to promote public awareness of nuclear energy issues. A typicaltour is a general presentation for high school and civic organizations. Other tours given specialconsideration are demonstrations for interest groups such as physics, chemistry and sciencegroups.2.6.3 Research & ServiceA more comprehensive description of the nuclear analytic techniques and facilities available atthe NETL is provided in section 5. Personnel support for these activities includes faculty,graduate and undergraduate research assistants, and NETL staff.2.7 NETL SupportNETL funding is provided by state appropriations, research grants, and fees accrued fromservice activities. Research funding supplements the base budget provided by the State and isgenerally obtained through competitive research and program awards. Funds from serviceactivities supplement base funding to allow the facility to provide quality data acquisition andanalysis capabilities. Both sources of supplemental funds (competitive awards and service work)are important to the education and research environment for students. The U.S. NuclearRegulatory Commission supported development of the Summer Nuclear Engineering Institute,and supports continuation of the program.153/2015 2014 NETL Annual Report3.0 FACILITY DESCRIPTION3.1 NETL HistoryDevelopment of the nuclear engineering program was an effort of both physics and engineeringfaculty during the late 1950's and early 1960's. The program became part of the MechanicalEngineering Department where it currently resides. The program installed and operated the firstUT TRIGA nuclear reactor in Taylor Hall on the main campus. Initial criticality for the first UTreactor was August 1963. Power at startup was 10 kilowatts with a power upgrade to 250kilowatts in 1968. Total burnup during the 25 year period from 1963 to final operation in April1988 was 26.1 megawatt-days. Pulse capability of the reactor was 1.4% Ak/k with a total of 476pulses during the operating history.In October 1983, planning was initiated for the NETL to replace the original UT TRIGAinstallation. Construction was initiated December 1986 and completed in May 1989. The NETLfacility operating license was issued in January 1992, with initial criticality on March 12, 1992.Dismantling and decommissioning of the first UT TRIGA reactor facility was completed inDecember 1992.3.2 NETL SITE, J.J. Pickle Research CampusLand development in the area of the current NETL installation began as an industrial site duringthe 1940's. Following the 1950's, lease agreements between the University and the Federalgovernment led to the creation of the Balcones Research Center. The University became ownerof the site in the 190's, and in 1994 the site name was changed to the J.J. Pickle ResearchCampus (PRC) in honor of retired U.S. Congressman James "Jake" Pickle.The PRC is a multidiscipline research campus on 1.87 square kilometers. The site consists oftwo approximately equal areas, east and west. An area of about 9000 square meters on the easttract is the location of the NETL building. Sixteen separate research units and at least five otheracademic research programs conduct research at locations on the PRC. Adjacent to the NETLsite are the Center for Research in Water Resources, the Bureau of Economic Geology, and the163/2015 2014 NETL Annual ReportResearch Office Complex, illustrating the diverse research activities on the campus. ACommons Building provides cafeteria service, recreation areas, meeting rooms, and conferencefacilities.3.3 NETL Building DescriptionThe NETL building is a 1950 sq meter (21,000 sq ft), facility with laboratory and office spaces.Building areas consist of two primary laboratories of 330 sq m (3600 sq ft) and 80 sq m (900 sqft), eight support laboratories (217 sq m, 2340 sq ft), and six supplemental areas (130 sq m, 1430sq ft). Conference and office space is allocated to 12 rooms totaling 244 sq m (2570 sq ft). Oneof the primary laboratories contains the TRIGA reactor pool, biological shield structure, andneutron beam experiment area. A second primary laboratory consists of 1.3 meter (4.25 ft) thickwalls for use as a general purpose radiation experiment facility. Other areas of the buildinginclude shops, instrument & measurement laboratories, and material handling facilities.The NETL Annex was installed in 2005, a 24 by 60 foot modular class room building adjacent tothe NETL building. The building provides classroom space and offices for graduate studentsworking at the NETL.173/2015 2014 NETL Annual Report4.0 UT-TRIGA MARK II RESEARCH REACTORTRIGA is an acronym for Training, Research, Isotope production, General Atomics. TheTRIGA Mark II reactor is a versatile and inherently safe research reactor conceived anddeveloped by General Atomics to meet education and research requirements. The UT-TRIGAreactor provides sufficient power and neutron flux for comprehensive and productive work inmany fields including physics, chemistry, engineering, medicine, and metallurgyCONTROL ROD DRIVEREACTO T RIOCGA Mr NcolearResearch ReatoCENTRAL ---" ALUMITNUM TANK[EXPERIMENTPNEUMATW~TRANSqFERTUBE.. .CORE CRIO ,/ FISS'ON ORROToRlnR n mdrt, a tR ACK ,R hE FLECTOR* CONTIO RD-, Mo " AN PORT *-4FLOOR LINE ., ,.* ..' * "Figure 4- 1, UT TRIGA Mark 11 Nuclear Research ReactorThe NETL UT-TRIGA reactor is an above-ground, fixed-core research reactor. The reactor coreis located at the bottom of an 8.2 meter deep water-filled tank surrounded by a concrete shieldstructure. The water serves as a coolant, neutron moderator, and transparent radiation shield.The reactor core is surrounded by a reflector, a 1 foot thick graphite cylinder. The reactor iscontrolled by manipulating cylindrical "control rods" containing boron.183/2015 2014 NETL Annual Report4.1 Reactor Core.The reactor core is an assembly of about 100 fuel elements surrounded by an annular graphiteneutron reflector. Fuel elements are positioned by an upper and lower grid plate, withpenetrations of various sizes in the upper grid plate to allow insertion of experiments. Each fuelelement consists of a fueled region with graphite sections at top and bottom, contained in a thin-walled stainless steel tube. The fuel region is a metallic alloy of low-enriched uranium in azirconium hydride (UZrH) matrix. Physical properties of the TRIGA fuel provide an inherentlysafe operation. Rapid power transients to high powers are automatically suppressed withoutusing mechanical control; the reactor quickly and automatically returns to normal power levels.Pulse operation, a normal mode, is a practical demonstration of this inherent safety feature."-' :.T :t IFigure 4-2, Core and Support Structure Details4.2 Reactor Reflector.The reflector is a graphite cylinder in a welded aluminum-canister. A 10" well in the uppersurface of the reflector accommodates an irradiation facility, the rotary specimen rack (RSR),and horizontal penetrations through the side of the reflector allow extraction of neutron beams.In 2000 the canister was flooded to limit deformation stemming from material failure in welding193/2015 2014 NETL Annual Reportjoints. In 2004, the reflector was replaced with some modification, including a modification tothe upper grid plate for more flexible experiment facilities.4.3 Reactor Control.The UT-TRIGA research reactor can operate continuously at nominal powers up to 1.1 MW, orin the pulsing mode with maximum power levels up to 1500 MW (with a trip setpoint of 1750MW) for durations of about 10 msec. The pulsing mode is particularly useful in the study ofreactor kinetics and control. The UT-TRIGA research reactor uses a compact microprocessor-driven control system. The digital control system provides a unique facility for performingreactor physics experiments as well as reactor operator training. This advanced system providesfor flexible and efficient operation with precise power level and flux control, and permanentretention of operating data.The power level of the UT-TRIGA is controlled by a regulating rod, two shim rods, and atransient rod. The control rods are fabricated with integral extensions containing fuel (regulatingand shim rods) or air (transient rod) that extend through the lower grid plate for full span of rodmotion. The regulating and shim rods are fabricated from B4C contained in stainless steel tubes;the transient rod is a solid cylinder of borated graphite clad in aluminum. Removal of the rodsfrom the core allows the rate of neutron induced fission (power) in the UZrH fuel to increase.The regulating rod can be operated by an automatic control rod that adjusts the rod position tomaintain an operator-selected reactor power level. The shim rods provide a coarse control ofreactor power. The transient rod can be operated by pneumatic pressure to permit rapid changesin control rod position. The transient rod moves within a perforated aluminum guide tube.203/2015 2014 NETL Annual Report5.0 EXPERIMENT AND RESEARCH FACILITIESNeutrons produced in the reactor core can be used in a wide variety of research applicationsincluding nuclear reaction studies, neutron scattering experiments, nuclear analytical techniques,and irradiation of samples. Facilities for positioning samples or apparatus in the core regioninclude cut-outs fabricated in the upper grid plate, a central thimble in the peak flux region of thecore, a rotary specimen rack in the reactor graphite reflector, and a pneumatically operatedtransfer system accessing the core in an in-core section. Beam ports, horizontal cylindrical voidsin the concrete shield structure, allow neutrons to stream out away from the core. Experimentsmay be performed inside the beam ports or outside the concrete shield in the neutron beams.Areas outside the core and reflector are available for large equipment or experiment facilities.Current NRE and NETL personnel and active projects are tabulated at the end of this section(Table 5.3, 5.4).In addition to reactor facilities, the NETL has a subcritical assembly, various radioisotopesources, radiation producing machines, and laboratories for spectroscopy and radiochemistry.5.1 Upper Grid Plate 7L and 3L FacilitiesThe upper grid plate of the reactor contains four removable sections configured to provide spacefor experiments otherwise occupied by fuel elements (two three-element and two seven-elementspaces), Containers can be fabricated with appropriate shielding or neutron absorbers to tailorthe gamma and neutron spectrum to meet specific needs. Special cadmium-lined facilities havebeen constructed that utilize three element spaces.5.2 Central ThimbleThe reactor is equipped with a central thimble for access to the point of maximum flux in thecore. The central thimble is an aluminum tube extending through the central penetration of thetop and bottom grid plates. Typical experiments using the central thimble include irradiation ofsmall samples and the exposure of materials to a collimated beam of neutrons or gamma rays.213/2015 2014 NETL Annual Report5.3 Rotary Specimen Rack (RSR)A rotating (motor-driven) multiple-position specimen rack located in a well in the top of thegraphite reflector provides for irradiation and activation of multiple samples and/or batchproduction of radioisotopes. Rotation of the RSR minimizes variations in exposure related tosample position in the rack. Samples are loaded from the top of the reactor through a tube intothe RSR using a specimen lifting device. A design feature provides the option of usingpneumatic pressure for inserting and removing samples.5.4 Pneumatic TubesA pneumatic transfer system supports applications using short-lived radioisotopes. The in-coreterminus of the system is normally located in the outer ring of fuel element positions, withspecific in-core sections designed to support thermal and epithermal irradiations. The samplecapsule is conveyed to a sender-receiver station via pressure differences in the tubing system.An optional transfer box permits the sample to be sent and received to three different sender-receiver stations. One station is in the reactor confinement, one is in a fume hood in a laboratoryroom, and the third operates in conjunction with an automatic sample changer and countingsystem.5.5 Beam Port FacilitiesFive neutron beam ports penetrate the concrete biological shield and reactor water tank at corelevel. Specimens may be placed inside a beam port or outside the beam port in a neutron beamfrom the beam port. The beam ports were designed with different characteristics to accommodatea wide variety of experiments. Shielding reduces radiation levels outside the concrete biologicalshield to safe values when beam ports are not in use. Beam port shielding is configured with aninner shield plug, outer shield plug, lead-filled shutter, and circular steel cover plate. A neutronbeam coming from a beam port may be modified by using collimators, moderators and/orneutron filters. Collimators are used to limit beam size and beam divergence. Moderators andfilters are used to change the energy distribution of neutrons in beams (e.g., cold moderator).223/2015 2014 NETL Annual ReportBP #4BP #5KI[ BP #1Figure 5-2, Beam PortsTable 5-2, Dimensions of Standard Beam PortsBP#1, BP#2, BP#4At Core 6 in. 15.24 cmAt Exit 8 in. 20.32 cmBP #3, BP#5At Core 6 in. 15.24 cm8 in. 20.32 cm10 in. 25.40 cmAt Exit: 16 in. 40.64 cm5.5.1 Beam Port 1 (BPI)BP1 is connected to BP5, forming a through port. The through port penetrates the graphitereflector tangential to the reactor core, as seen in Figure 5-2. This configuration allowsintroduction of specimens adjacent to the reactor core to gain access to a high neutron flux fromeither side of the concrete biological shield, and can provide beams of thermal neutrons withrelatively low fast-neutron and gamma-ray contamination.233/2015 2014 NETL Annual ReportA reactor-based slow positron beam facility is being fabricated at BP1. The facility (TexasIntense Positron Source) will be one of a few reactor-based slow positron beams in the world.The Texas Intense Positron Source consists of a copper source, a source transport system, acombined positron moderator/remoderator assembly, a positron beam line and a samplechamber.The copper source will be irradiated in the middle section of the through port (BP1-BP5).The isotope 64Cu formed by neutron capture in 63Cu (69 % in natural copper) has a half life of12.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />, with the branching ratio for P+ emission of 19 %.. A source transport system in a 4meter aluminum system will be used to move the source to the irradiation location and out of thebiological shield. The source will be moved away from the neutron beam line outside thebiological shielding to an ultra high vacuum (at around 10-10 torr) chamber, where themoderator assembly is located. High energy positrons from the source will be slowed down to afew eV by a tungsten foil moderator that also acts as a remoderator to reduce the beam size toenable beam transport to a target for experimentation. The beam will be electrostatically guidedto deliver about 108 positrons/sec in the energy range of 0 -50 keV.5.5.2 Beam Port 2 (BP2)BP2 is a tangential beam port, terminating at the outer edge of the reflector. A void in thegraphite reflector extends the effective source of neutrons into the reflector for a thermal neutronbeam with minimum fast-neutron and gamma-ray backgrounds. Tangential beams result in a"softer" (or lower average-) energy neutron beam because the beam consists of scattered reactorneutrons. BP2 is configured to support neutron depth profiling applications, with a prompt-gamma neutron activation analysis sharing the beam port.Neutron Depth Profiling (NDP) Some elements produce charged particles with characteristicenergy in neutron interactions. When these elements are distributed near a surface, the particleenergy spectrum is modulated by the distance the particle traveled through the surface. NDPuses this information to determine the distribution of the elements as a function of distance to thesurface.243/2015 2014 NETL Annual ReportPrompt-Gamma Neutron Activation Analysis (PGNAA) Characteristic gamma radiation isproduced when a neutron is absorbed in a material. PGNAA analyzes gamma radiation toidentify the material and concentration in a sample. PGNAA applications include: i)determination of B and Gd concentration in biological samples which are used for NeutronCapture Therapy studies, ii) determination of H and B impurity levels in metals, alloys, andsemiconductor, iii) multi-element analysis of geological, archeological, and environmentalsamples for determination of major components such as Al, S, K, Ca, Ti, and Fe, and minor ortrace elements such as H, B, V, Mn, Co, Cd, Nd, Sm, and Gd, and iv) multi-element analysis ofbiological samples for the major and minor elements H, C, N, Na, P, S, Cl, and K, and traceelements like B and Cd.1.E+011.E+00V0o00.0I.E-011.E-02I.E-031.E-040 1000 2000 3000 4000 5000 6000 7000 8000Energy [keV]Figure 5-3, PGAA Spectra of Carbon Composite Flywheel5.5.3 Beam Port 3 (BP3)BP3 is a radial beam port. BP3 pierces the graphite reflector and terminates at the inner edge ofthe reflector. This beam port permits access to a position adjacent to the reactor core, and canprovide a neutron beam with relatively high fast-neutron and gamma-ray fluxes. BP3 containsthe Texas Cold Neutron Source Facility, a cold source and neutron guide system.253/2015 2014 NETL Annual Report~ ~m~g~ -La CWU3 ft* 1I=Figure 5-4, Prompt Gamma Focused-Neutron Activation Analysis FacilityTexas Cold Neutron Source. The TCNS provides a low background subthermal neutron beamfor neutron reaction and scattering research. The TCNS consists of a cooled moderator, a heatpipe, a cryogenic refrigerator, a vacuum jacket, and connecting lines. The TCNS uses eightymilliliters of mesitylene moderator, maintained by the cold source system at -36 K in a chamberwithin the reactor graphite reflector. A three-meter aluminum neon heat pipe, or thermosyphon,is used to cool the moderator chamber. The heat pipe working fluid evaporates at the moderatorchamber and condenses at the cold head.Cold neutrons from the moderator chamber are transported by a 2-m-long neutron guide insidethe beam port to a 4-m-long neutron guide (two 2-m sections) outside the beam port. Bothneutron guides have a radius of curvature equal to 300 m. All reflecting surfaces are coated withNi-58. The guide cross-sectional areas are separated into three channels by 1-mm-thick verticalwalls that block line-of-sight radiation streaming.Prompt Gamma Focused-Neutron Activation Analysis Facility The UT-PGAA facility utilizesthe focused cold-neutron beam from the Texas Cold Neutron Source. The PGAA sample islocated at the focal point of the converging guide focusing system to provide an enhancedreaction rate with lower background at the sample-detector area as compared to other facilities263/2015 2014 NETL Annual Reportusing filtered thermal neutron beams. The sample handling system design permits the study of awide range of samples and quick, reproducible sample-positioning.5.5.4 Beam Port 4 (BP4)BP4 is a radial beam port that terminates at the outer edge of the reflector. A void in the graphitereflector extends the effective source of neutrons to the reactor core. This configuration is usefulfor neutron-beam experiments which require neutron energies higher than thermal energies. BP4was configured in 2005 to support student laboratories.5.5.5 Beam Port 5 (BP5)A Neutron Radiography Facility is installed at BP5 (Figure 5-5). Neutrons from BP5 illuminatea sample. The intensity of the exiting neutron field varies according to absorption and scatteringcharacteristics of the sample. A conversion material generates light proportional to the intensityof the neutron field as modified by the sample.DisksoueFigure 5-5, Neutron Radiography SystemThe conversion material is integral in one imaging system at the NETL; there are twoindependent conversion devices available at the NETL. A Micro-Channel Plate imageintensifying technology system (NOVA Scientific) is characterized by high resolution (up to 30jim) over a small (approximately 1/2 in.) field of view. A larger image can be obtained using amore conventional 7X7 in.26LiF/ZnS scintillation screen.273/2015 2014 NETL Annual ReportA conversion screen mounted on a video tube provides a direct single in one neutronradiography camera at the NETL. The image produced by the independent conversionapparatuses can be recorded in one of three available digital cameras. Cameras include a chargeinjection device (CID) camera, a cryogenically cooled charge coupled device (CCD) camera, andan electronically cooled CCD camera. The digital image is captured in a computer, where imageanalysis software produces the final product.5.6 Other Experiment and Research FacilitiesThe NETL facility makes available several types of radiation facilities and an array of radiationdetection equipment. In addition to the reactor, facilities include a subcritical assembly, variousradioisotope sources, machine produced radiation fields, and a series of laboratories forspectroscopy and radiochemistry.5.6.1 Subcritical AssemblyA subcritical assembly of 20% enriched uranium in a polyethylene moderated cylinder providesan experimental device for laboratory demonstrations of neutron multiplication and neutron fluxmeasurements. A full critical loading of fuel previously at the Manhattan College Zero PowerReactor is currently at the facility.5.6.2 RadioisotopesRadioisotopes are available in a variety of quantities. Gamma and beta sources generally inmicro curie to mill curie quantities are available for calibration and testing of radiation detectionequipment. Neutron sources of plutonium-beryllium and californium-252 are available.Laboratories provide locations to setup radiation experiments, test instrumentation, preparematerials for irradiation, process radioactive samples and experiment with radiochemicalreactions.283/2015 2014 NETL Annual Report5.6.3 Radiation Producing MachinesThe NETL houses a 14-MeV neutron generator. The generator is currently being developed forhigh-energy neutron activation analysis and portable neutron radiography applications.5.6.4 Support LaboratoriesThere are several laboratories adjacent to the reactor. One laboratory supports sample andstandards preparation. Labs are also used for various types of radio assay, with one dedicated toa receiving station for rabbit system operations and sample counting. A control system permitsautomated operations.The DOE is anticipating a loss of nuclear workforce with limited prospects for replacement ofradio chemists in the national laboratory system. Therefore, a graduate-level radiochemistrylaboratory was developed with support from the Department of Energy (DOE). The laboratoryconsists of state-of-the-art Alpha Spectroscopy Systems, Liquid Scintillation Counting Systemand several High Resolution Gamma Counting Systems. Students are encouraged to developskills and interests that make them viable replacements for the nuclear workforce.5.7 Experiment Facility UtilizationFigure 5-1 provides the number of hours of reactor operation allocated to experiments in theapplicable facility, with abbreviations in Figure 5-1 explained in Table 5.1 that follows. Therewere 776.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> utilized for experiments in 2013. In addition, operations supported irradiationin more than one experiment facility simultaneously for 72.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. Therefore, total time forreactor operations was 848.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br />. The number of operating hours allocated to experimentsincludes the "console key on" time.293/2015 2014 NETL Annual Report2014 Operating Hours DistributionMai nt.17% .\RSR7%Tour/Pulse1%BP50%BP4j6% -TPNT/21%BPS-ý15%BP1 pb3L Cd3L0% 2% 3%EPNT26%Figure 5-1, Utilization of Experiment HoursTable 5.1Terminology for Figure 5-1PGNAAPb3LCd3LNAAEPTNTNAA TPNTNAA RSRBP 1-5TourClassesTrainingPulseRadiographyPrompt Gamma Neutron Activation AnalysisSample material irradiated in the lead-lined (enhanced for lower gamma) 3-element position in-core facility (isotope production)Sample material irradiated in the cadmium-lined (enhanced for epithermalneutrons) 3-element position in-core facility (generally used for NAA)Neutron Activation Analysis for samples irradiated in epithermal neutronpneumatic tube (irradiation position lined with cadmium)Neutron Activation Analysis for samples irradiated in thermal neutronpneumatic tubeNeutron Activation Analysis for samples irradiated in rotary specimen rackBeam PortGeneral facility toursAcademic support (ME337, ME361, ME388, ME389N, Health Physics,Summer Nuclear Engineering Institute)Operations supporting reactor operator training or requalification programTime required to support approximately 36 pulsesNeutron radiography303/20 15 2014 NETL Annual Report5.8 Nuclear Program Faculty ActivitiesPublications and conference participation associated with the NETL during 2014 are providedbelow.Table 5.4, Publications and Conferences -2014W.H. Wilson, S.R. Biegalski, C. Johnson, D. Haas, J. Lowrey, "Cosmic-Ray Induced Productionof Radioactive Noble Gases in the Atmosphere, Ground, and Seawater," submitted to the Journalof Radioanalytical and Nuclear Chemistry, September 2014.C. Johnson, S. Biegalski, J. Lowrey, and D. Haas, " Local Transport of Radioxenon Releasedfrom the Chalk River Laboratories Medical Isotope Facility," submitted to the Journal ofRadioanalytical and Nuclear Chemistry, September 2014.K. Dayman, S. Biegalski, "Determination of Short-Lived Fission Product Yields with GammaSpectroscopy," submitted to the Journal of Radioanalytical and Nuclear Chemistry, September2014.F. J. Klingberg, S. R. Biegalski, D.A. Haas, A. Prinke, "Electron-Photon Coincidence Decay of127Xe," submitted to the Journal of Radioanalytical and Nuclear Chemistry, September 2014.R.I. Palomares, K.J. Dayman, S. Landsberger, S.R. Biegalski, C.Z. Soderquist, A.J. Casella,M.C. Brady Raap, J.M. Schwantes, "Measuring the Noble Metal and Iodine Composition ofExtracted Noble Metal Phase from Spent Nuclear Fuel Using Instrumental Neutron ActivationAnalysis," Applied Radiation and Isotopes, 98, 66-70, 2015.C. Johnson, S. Biegalski, H. Armstrong, W. Wilson, "Examination of radioargon production bycosmic neutron interactions," Environmental Radioactivity, 140, 123-129, 2015.J.D. Lowrey, A.G. Osborne, S.R. Biegalski, M.R. Deinert, "Comparison of numerically stablemethods for implementation of a double-porosity model with first order reaction terms,"Transport in Porous Media, 106 (1), 33-45, 2015.R. Gomez, S. Biegalski, V. Woods, "Aerosol Sample Inhomogeneity in Samples with Debrisfrom the Fukushima Daiichi Nuclear Accident," Environmental Radioactivity, 135, 1-5, 2014.A. Reinhart, A. Athey, S. Biegalski, "Spatially-Aware Temporal Mapping of Gamma Spectra,"IEEE Transactions on Nuclear Science, 31(3), 1284-1289, 2014.F.W. Eslinger, T.W. Bowyer, M.W. Cooper, D.A. Haas, J.C. Hayes, H.S. Miley, J.P. Rishel,V.T. Woods, S.R. Biegalski, I. Hoffman, E. Korpach, J. Yi, K. Ungar, and B. White," Sourceterm estimation of radioxenon released from the Fukushima Dai-ichi nuclear reactors usingmeasured air concentrations and atmospheric transport modeling," Journal of EnvironmentalRadioactivity, 127, 127-132, 2014.O Doron, L Wielopolski, S Mitra, S Biegalski, "MCNP Benchmarking of an Inelastic NeutronScattering System for Soil Carbon Analysis." Nuclear Instruments and Methods: A, 735, 431-436, 2014.Henriques, A., J. T. Graham, S. Landsberger, S., J. F., Ihlefeld, G. L., Brennecka, G. L., D. W.,Brown, J. S., Forrester, J. S., and J. L. Jones, "Crystallographic Changes in Lead ZirconateTitanate due to Neutron Irradiation", Am. Inst. Phys. Advances, 4, 11725-1 -11725-6 (2014).Horne, S., S. Landsberger and B. Dickson "Determination of Isotopic Ratios of UraniumSamples Using Passive Gamma Spectroscopy With Multiple Detectors", J. Radioanal. Nucl.313/2015 2014 NETL Annual ReportTable 5.4, Publications and Conferences -2014Chem., 299, 1171-1175 (2014).Peterson, C., M. Pryor and S. Landsberger, "Evaluating Automation for Material Reduction inGloveboxes Using Plutonium Surrogates", Trans. ANS, Decommission and Remote Systems,Embedded Topical Meeting, p 143-146 (2014).Landsberger, S. G., G. George, and S. Landsberger "Educational Training of Handling NaturallyOccurring Radioactive Material (NORM) in the Oil and Gas Industry", "An Evaluation ofCompton Suppression NAA in the Determination of Arsenic in Drinking Water in Surfside,Texas", Trans. ANS, 111, 174-175 (2014).Landsberger, S. G., G. George, S. Landsberger and G. Kuzmin, "An Evaluation of ComptonSuppression NAA in the Determination of Arsenic in Drinking Water in Surfside, Texas" Trans.ANS, 111, 552-554 (2014).Landsberger, S., Morton, J., S. G. Landsberger, G. George, M. Moyamezi and D. Hurst, "In SituDetermination of Radionuclides in the Oil and Gas Fields", Trans. ANS, 111, 555-557 (2014).Yoho, M. and S. Landsberger, "Quality Assurance for Gamma-Gamma Coincidence in a TwoSource Complex Spectrum", Trans. ANS, 111, 558-559 (2014).Hashem, J., M. Pryor, S. Landsberger and J. Hunter, "Implementation of Flexible Automationfor Neutron Radiography Applications", Trans. ANS, Decommission and Remote Systems,Embedded Topical Meeting, p 136-138 (2014).Landsberger, S., "Gamma-Ray Detection: A Historical Overview", Trans. ANS. 110, pp 45-452(2014).Henriques, A., J. T. Graham, S. Landsberger, S., J. F., Ihlefeld, G. L., Brennecka, G. L., D. W.,Brown, J. S., Forrester, J. S., and J. L. Jones, "Crystallographic Changes in Lead ZirconateTitanate due to Neutron Irradiation", Am. Inst. Phys. Advances, 4, 11725-1 -11725-6 (2014).Home, S., S. Landsberger and B. Dickson "Determination of Isotopic Ratios of UraniumSamples Using Passive Gamma Spectroscopy With Multiple Detectors", J. Radioanal. Nucl.Chem., 299, 1171-1175 (2014).Peterson, C., M. Pryor and S. Landsberger, "Evaluating Automation for Material Reduction inGloveboxes Using Plutonium Surrogates", Trans. ANS, Decommission and Remote Systems,Embedded Topical Meeting, p 143-146 (2014).Landsberger, S. G., G. George, and S. Landsberger "Educational Training of Handling NaturallyOccurring Radioactive Material (NORM) in the Oil and Gas Industry", "An Evaluation ofCompton Suppression NAA in the Determination of Arsenic in Drinking Water in Surfside,Texas", Trans. ANS, 111, 174-175 (2014).Landsberger, S. G., G. George, S. Landsberger and G. Kuzmin, "An Evaluation of ComptonSuppression NAA in the Determination of Arsenic in Drinking Water in Surfside, Texas" Trans.ANS, 111, 552-554 (2014).Landsberger, S., Morton, J., S. G. Landsberger, G. George, M. Moyamezi and D. Hurst, "In SituDetermination of Radionuclides in the Oil and Gas Fields", Trans. ANS, 111, 555-557 (2014).Yoho, M. and S. Landsberger, "Quality Assurance for Gamma-Gamma Coincidence in a TwoSource Complex Spectrum", Trans. ANS, 111, 558-559 (2014).Hashem, J., M. Pryor, S. Landsberger and J. Hunter, "Implementation of Flexible Automationfor Neutron Radiography Applications", Trans. ANS, Decommission and Remote Systems,Embedded Topical Meeting, p 136-138 (2014).Landsberger, S., "Gamma-Ray Detection: A Historical Overview", Trans. ANS. 110, pp 45-452(2014).Schneider, E. A. and Phathanapirom, U. B., "VEGAS: A Fuel Cycle Simulation and323/2015 2014 NETL Annual ReportTable 5.4, Publications and Conferences -2014Preconditioner Tool with Restricted Material Balances," Nuclear Technology, under review(2015).Van der Hoeven, C. and E. A. Schneider, "Generation of Improved Isotopic MolybdenumCovariances from Elemental Cross Section Data Using SAMMY," Nuclear Science andEngineering 179, 1-21 (2015).Thoreson, G. G., Schneider, E. A., Armstrong, H. A. and C. van der Hoeven, "The Applicationof Neutron Transport Green's Functions to Threat Scenario Simulation," IEEE Transactions onNuclear Science, in press (2015).333/2015 2014 NETL Annual Report6.0 FACILITY OPERATING SUMMARIES6.1 Operating ExperienceThe UT-TRIGA reactor operated for 461 hours0.00534 days <br />0.128 hours <br />7.622354e-4 weeks <br />1.754105e-4 months <br /> on 144 days in 2014, producing a total energyoutput of 144.4 MW-hrs. The history of operations over the past 22 years of facility operation isprovided in Figures 6-1 and 6-2. As illustrated, operating time has shown a marked increasefrom the first several years and has been relatively stable for the past decade. Varying researchrequirements over the past few years have led to a decrease in total energy generation.250200150~100E oZ 1992 1995 1998 2001 2004 2007 2010 2013Year of OperationFigure 6.1, Operating Days35.0030.0025,0020.001 10.000 5,000.001992 1995 1998 2001 2004 2007 2010 2013Year of OperationFigure 6-2, Energy Generation6.2 Unscheduled ShutdownsReactor safety system protective actions are classified as limiting safety system (LSSS) trip, alimiting condition for operation (LCO) trip or a trip of the SCRAM manual switch. The use of343/2015 2014 NETL Annual Reportthe manual scram switch in normal reactor shutdowns is not a protective action. The followingdefinitions in Table 6.1 classify the types of protective actions recorded.Protective ActionSafety System SettingLSSSCondition for OperationLCO -(analog detection)Condition for OperationLCO -(digital detection)Manual Switch(protective action)Table 6.1, Protective Action DefinitionsDescriptionAutomatic shutdown actuated by detection of limitingsafety system setting such as fuel temperature orpercent powerAutomatic shutdown actuated detection of a limitingcondition for operation within a safety channel or theinstrument control and safety system such as poolwater level, a loss of detector high voltage or anexternal circuit tripAutomatic shutdown actuated by software actiondetecting inoperable conditions within a programfunction of the instrument control and safety systemsuch as watchdog timers or program database errorsManually initiated emergency shutdownTable 6.2 lists 3 unscheduled shutdowns that occurred in 2014, all of which were initiated by thereactor safety system.Date07/03/201409/15/201410/27/2014Time Type10:02 SCRAM12:06 SCRAM14:08 SCRAMTable 6.2, SCRAM Log for 2014Comments* FTI Thermocouple, Intermittent Failure* FTI Thermocouple, Intermittent FailureFTI Thermocouple, Intermittent FailureThere were three temperature channel trips in 2014 related to thermocouple intermittent signalfailure. In all cases, time dependent data indicates fuel temperatures were normal and the tripsoccurred because of signal transients not indicative of actual fuel temperature. Attempts toisolate the trip to a specific component or recreate the failure have not been successful. Thefailure mode is conservative and acceptable until either the channel fails in a more consistentmode or the characteristics leading to the actuations can be identified.6.3 UtilizationUtilization of the NETL reactor facility is near the maximum possible under a 5-day per weekschedule. The main categories of facility utilization include education, undergraduate research,graduate research, and external research collaborations. Table 6.3 lists the external research353/2015 2014 NETL Annual Reportcollaborations at NETL since 2009. Facility usage is largely dominated by the use of nuclearanalytical techniques for sample analysis. These techniques include neutron activation analysis,neutron radiography, neutron depth profiling, and prompt gamma activation analysis.Table 6.3, NETL External Research Collaborations since 2009External Collaborator Location Facility UtilizationTrinitek Services, Inc. Sandia Park, NM Soil sample analysisEnvironment CanadaBridgeport InstrumentsCarollo EngineeringEvergreen SolarKaizen InnovationsIdaho National LaboratoryIllinois State GeologicalSurveyUT BiologyDepartment of GeologicalSciencesLos Alamos NationalLaboratoryLolodine, LLCUT Health Science CenterPacific Northwest NationalLaboratoryRMT, Inc.Signature ScienceBiomedical EngineeringDepartmentSouthwestern UniversityComprehensive Nuclear-Test-Ban TreatyOrganizationClarkson UniversityJWK CorporationCivil and EnvironmentalEngineering DepartmentNational Center for Energy,Science and NuclearTechnologiesNanospectra Biosciences,Inc.U.S. Nuclear RegulatoryCommissionNTSGatineau, Quebec,CanadaAustin, TXAustin, TXMarlboro, MAGeorgetown, TXIdaho Falls, IDChampaign, ILAustin, TXAustin, TXLos Alamos, NMJersey City, NJHouston, TXRichland, WAMadison, WIAustin, TXAustin, TXGeorgetown, TXVienna, AustriaPotsdam, NYAnnandale, VAAustin, TXRabat, MoroccoHouston, TXRockville, MDAlbuquerque, NMArctic air filter analysisRadiation detector developmentRadiation damage studiesSilicon wafer trace element analysisSoil sample analysisIsotope productionWater sample analysisSoil sample analysisGeological sample irradiationSample irradiationsNut AnalysisNanoparticle analysisIsotope ProductionWater sample analysisMaterial irradiations and shrapnelanalysisTissue sample analysisPlant sample analysis and studentlaboratoriesRadioxenon productionAir filter analysisSample irradiationsFly ash sample analysisSoil sample analysisTissue sample analysisReactor operations trainingIsotope production363/2015 2014 NETL Annual ReportTable 6.3, NETL External Research Collaborations since 2009External Collaborator Location Facility UtilizationOmaha Public Power District Blair, NE Boral coupon analysisTEKLAB Collinsville, IL Water sample analysisXIA Hayward, CA Radioxenon productionLawrence Livermore Livermore, CA Isotope productionNational LaboratoryVarious activation and analysis services were carried out in support of the overall UT missionand for public service. Analytical service work was performed for outside agencies. Over 1000samples were irradiated during 2014, continuing the decrease that began in 2013, as illustrated inFigure 6-4. There has been no utilization of BP2 or BP4 for the past few years, and a singleutilization of the central thimble. Thermal pneumatic irradiations decreased significantlycompared to the annual average since 2003 as has been the trend, while epithermal irradiationsfor the manual PNT remained consistent with the historical average. The automatic PNT wasutilized more in 2014 than in 2013. Three element thermal facility irradiations were 26% of thehistorical average, and 21% for epithermal irradiations.IwSFigure 6-4, NETL Sample Activation373/2015 2014 NETL Annual Report6.4 Routine Scheduled MaintenanceAll surveillances and scheduled maintenance activities were completed during the reporting yearat the required frequencies. All results met or exceeded the requirements of the TechnicalSpecifications.6.5 Corrective MaintenanceActivities this reporting period predominately consisted of adjustment and replacement ofradiation monitor components, pool water system components, room confinement systemcomponents and periodic maintenance due to wear. All replacements were done in accordancewith 10 CFR 50.59. Corrective maintenance activities included the replacement of individualcomponents or assemblies with like or similar replacement parts. The following list is asummary of the corrective maintenance activities accomplished by facility staff:* Adjustment of primary coolant pipe brackets on reactor tank upper level" Replacement of the purification system particulate filter" Adjustment and maintenance of Particulate CAM detector HV connector at probe end" Replacement of detector in Particulate CAM" Adjustment of high voltage power supply in Argon-CAM" Replacement of high voltage power supply in Argon-CAM* Replacement of green "normal light" bulb in mid-level area radiation monitor" Adjustment of reactor door weather-strips" Replacement of return air gaskets in HVAC system" Replacement of reactor bay fume hood fan beltOne additional interim corrective maintenance activity occurred during 2014. In late November2013 a small leak was discovered in the BP-5 experimental area. Appropriate actions were takento collect the leaking water, and operations were continued until the normal scheduledmaintenance in January 2014. The water leak rate increased late in 2013 and an automated watercollection and transfer system was set in place to accommodate the increased leak rate. The383/2015 2014 NETL Annual Reportcollected water was sampled and held until determined acceptable for sewer disposal by HealthPhysics staff. In January after allowing beam line components to decay over the 2013 Christmasholiday break and performing various routine annual maintenance functions, the beam lineexperiments installed in BP5 were removed to allow inspection and location of the exact leakpoint. After components were removed from the interior of BP5 it became obvious that the leakwas at the BP I end of the through port. The normal shielding plugs in BP 1 were found stuck iththe typical minor tar migration through a slip joint in the beam port liner wall which hadpreviously also been observed at BP4. A plug pulling system was constructed. The slowapplication of tension and cold flow of the tar allowed successful extraction of the inner plugfrom BP1. Once this was removed the source of the leak was identified as a small fracture inone of the bellows seal walls in the area designed for flexing. Since this was going to require amajor repair effort and significant funding to permanently fix, a temporary fix was devisedconsisting of a plug system which would seal the central beam line region in the area of itspenetration through the pool liner and effectively stop the leak until a permanent repair could bemade. A 50.59 review of the temporary repair was developed and approved by the ReactorOversight Committee. The temporary plug system with provisions for filling and venting theflooded space was then fabricated, installed and tested. The system was determined to beperforming as intended so normal reactor operations resumed during the second calendar quarterof 2014 and plans were initiated for a permanent fix.6.6 Facility ChangesDuring the 2014 calendar year there were a few changes in the facility staffing and severalmaintenance activities resulted in hardware changes as indicated above. There were no changesmade to procedures in 2014.6.6.1 Staff changes:There were two Reactor Operators who let their positions at the end of 2014. One full timeResearch Associate / reactor operator left his position for retirement. Another student operatorsuccessfully completed his coursework and graduated from the University of Texas at Austin.393/2015 2014 NETL Annual Report6.6.2 Facility changesFacility changes during 2014 (with the exception of the temporary repair of the beam line leak,previously described) principally included replacement of failed components with equivalentparts.During 2014 the integral noble gas stack monitor internal HV power supply exhibitedintermittent failure. The problem was very intermittent so the internal unit was replaced with acommercially available unit designed for scintillation detectors which was already on hand.This allowed time for troubleshooting and repair of the intermittently failing internal powersupply. The Particulate CAM Monitor detector as replaced with an equivalent new GM detector.During 2014 enhancements to the existing facility access control and security monitoringsystems supported by the Global Threat Reduction Initiative (DOE/NNSA) continued. Facilitymodifications included completion of the upgrading of security systems for the reactor facility.6.6.3 Procedure revision/updatesThere were no procedure revisions made in 2014.6.6.4 Facility Changes Accomplished in Accordance with Other Regulatory Requirements:There were no changes to the license, or Technical Specifications.Proposed or Pending Changes:Some Technical Specifications and license changes have been proposed and submitted tothe USRNC for final review and approval, including:i. A set of changes for clarification and correction of terminology,ii. A request for a license amendment/revision to permit byproduct and sourcematerial under the control and used by the reactor facility to support reactoroperations to be controlled under the reactor license,iii. A request to define initial startup, andiv. A request to require an operator at the controls when the reactor is not secured(currently required when the reactor is not shutdown).403/2015 2014 NETL Annual ReportA request for renewal of the facility operating license was made, with notification by theUSNRC that the UT facility meets requirements for operation under "timely renewal."Work to address requests for additional information is in progress.6.7 Oversight & InspectionsInspections of laboratory operations are conducted by university and licensing agency personnel.Two committees, a Radiation Safety Committee and a Reactor Oversight Committee reviewoperations of the NETL facility. The Reactor Oversight Committee convened on the dates listedin Table 6.4.Table 6.4, Reactor Oversight Committee ReviewsFirst Quarter NoneSecond Quarter 22 April 2014Third Quarter NoneFourth Quarter 21 October 2014Inspections by licensing agencies include federal license activities by the U. S. NuclearRegulatory Commission (NRC), Nuclear Reactor Regulation Branch (NRR), and state licenseactivities by the Texas Department of State Health Services (TDSHS) Radiation ControlProgram. NRC inspections conducted in calendar year 2014 are indicated in Table 6.5. Nofindings of significance were identified.Table 6.5, License InspectionsLicense DatesR-129 7-9 October 2014SNM-180 NoneL00485 (89) NoneRoutine inspections by the Office of Environmental Health and Safety (OEHS) for compliancewith university safety rules and procedures are conducted at varying intervals throughout theyear. In response to safety concerns at other sites on the main campus, several additional OEHSinspections have been made. Inspections cover fire, chemical, and radiological hazards. Nosignificant safety problems were found at NETL, which reflects favorably on the positive safetyculture for all hazard classes at the NETL. Safety concerns included such items as storage ofcombustibles, compressed gases, and fire extinguisher access.413/2015 2014 NETL Annual Report7.0 RADIOLOGICAL SUMMARY7.1 Summary of Radiological ExposuresThe Radiation Protection Program for the NETL facility provides monitoring for personnelradiation exposure, surveys of radiation areas and contamination areas, and measurements ofradioactive effluents as indicated in Table 7.1. Site area measurements include exterior pointsadjacent to and distant from the building.Table 7.1, Radiation Protection Program Requirements and FrequenciesFrequency Radiation Protection RequirementWeekly Gamma survey of all Restricted Areas.Swipe survey of all Restricted Areas.Swipe survey of Radioactive Materials Areas.Response check of the continuous air monitor.Response checks of the area radiation monitors.Neutron survey of the reactor bay (during reactor operation).Monthly Gamma, neutron and swipe surveys of exterior walls and roof.Exchange personnel dosimeters & interior area monitoring dosimeters.Review dosimetry reports.Response check emergency locker portable rad. measuring equipment.Review Radiation Work Permits.Response check of the argon monitor.Response check hand and foot monitor.Collect and analyze TRIGA primary water.As Required Process and record solid wastes and liquid effluent discharges.Prepare and record radioactive material shipments.Survey and record incoming radioactive materials.Perform and record special radiation surveys.Issue radiation work permits, provide HP for maintenance operations.Conduct orientations and training.Quarterly Exchange OSL environmental monitors.Gamma and swipe surveys of all non restricted areas.Swipe survey of building exterior areas.Semi-Annual Inventory emergency locker.Calibrate continuous air monitor, argon monitor, area rad. monitors.Leak test and inventory sealed sources.Annual Conduct ALARA Committee meeting.Calibrate portable radiation monitoring instruments.Calibrate personnel pocket dosimeters.Calibrate emergency locker portable radiation detection equipment423/2015 2014 NETL Annual Report7.2 Summary of Radioactive EffluentsThe radioactive effluent paths are ventilation for air-borne radionuclides, and the sanitary sewersystem for liquid radionuclides. The most significant airborne radionuclide effluent is argon-4 1.Two other airborne radionuclides, nitrogen-16 and oxygen-19, decay rapidly and do notcontribute to effluent releases. Argon-41, with a half-life of 109 minutes, is the only airborneradionuclide emitted by the facility during normal operations.7.2.1 ReleasedThere were no releases of solid radioactive materials during calendar year 2014. A smallquantity of radioactive waste is stored for decay or aggregation for a shipment.7.2.2 DischargedAirborne Releases. A differential pressure control system in the facility assures airborneradioactive releases are controlled. The reactor room is ventilated by a general area system, anda sub-system to collect and discharge argon 41 generated from routine reactor operations. Therewere 1.44x 106 iCi of argon 41 discharged during calendar year 2014, with the annual averagerelease 1% of the value permitted by Technical Specifications.Liquid Discharges. There are no routine releases from the facility associated with reactoroperation. Large liquid-volume radioactive waste is captured in holding tanks, where liquidradioactive waste may be held for decay or processed to remove the radioactive contaminants asappropriate. Water contaminated with tritium was discharged to the sanitary sewer on sixdifferent occasions in 2014. The average tritium concentration of the discharges was more thanan order of magnitude below the limits of 1OCFR20 for discharge to sewerage, with totaldischarge approximately 1.2 mCi. In addition to the tritium contaminated water, there was onedischarge to the sanitary sewer of approximately 20 liters of water contaminated with activationproducts. The total discharged activity was less than 1 gCi and the concentrations of theindividual isotopes were well below the sewer discharge limits of 1 OCFR20.433/2015 2014 NETL Annual Report7.3 Radiation Exposure Received by Facility Personnel and VisitorsFor calendar year 2014, no facility personnel received radiation exposures in excess of 25% ofthe allowed limit. Similarly, no visitors to the facility received in excess of 25% of the allowedlimit.7.4 Environmental Surveys Performed Outside the FacilityNETL monitors exterior locations indicated as positions 1 through 6 on the exterior dosimetermap. For 2014, minimal doses (< 1 mrem) were reported for al positions for all quarters.Sidewalk, NETL facility frontentranceReactor bay exterior wall. 0astROaCtor bay eXt rior wael. weStNETL pOwer tron.fororNETL ;orvice doorNETL roof stackIndicat*s location of doa=Lerywithin the buildingPARK I NFigure 7-1, NETL Environmental Monitor LocationsIn addition to the NETL monitors, the Texas Department of State Health Services monitorsexterior locations near NETL indicated as positions 1 through 5 on the TDSHS TLD map. Thereported doses for 2013 were:0 Position 1 -2 mrem443/2015 2014 NETL Annual Report* Position 2 -5 mrem" Position 3 -2 mrem* Position 4 -16 mrem* Position 5 -7 mremIssues with the dosimetry vendor were encountered in 2012, as noted in the 2012 Annual Report.TDSHS subsequently modified environmental monitoring in 2013 to use raw dosimetry datarather than background-corrected vendor dose reports. TDSHS corrected the raw data forbackground using data from a badge located approximately four miles southeast of NETL todevelop environmental monitoring data for the NETL. This process was continued in 2014.The TDSHS environmental monitoring reports since 2013 indicate an increase over historicalvalues that are not reflected in other environmental monitoring for the facility (reported above).Historical non-reactor activities conducted at the Pickle Research Campus have potential toelevate background radiation levels in the area. Therefore, the changes in dose levels as reportedby TDSHS may be related to the change in background correction. The UT Radiation SafetyOfficer opened a dialog in 2014 with TDSHS to resolve the issue.453/2015 2014 NETL Annual ReportNM iN TI $K.6. -G- X go -P Ea SO TgI,.We k m Yii&On maps tkM ShOMM MWi MM UWppnqaU~iW I My PEaI~ AIO"Id oOCoogle maps a" SSwhMapNEIL TW locadofisSafto tocalmos fow UT Nsciew Erq~..wý Tegtmga V #?+TWmdvmtyMu Samood lom aunef nmwhoI eoýe E of SEDOD463/2015