ML13249A075

2012 Annual Report for the University of Texas at Austin

ML13249A075
Person / Time
Site:	University of Texas at Austin
Issue date:	08/19/2013
From:	Whaley P M University of Texas at Austin
To:	Document Control Desk, Office of Nuclear Reactor Regulation
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/ / ~COLLEGE OF ENGINEERING THE UNIVERSITY OF TEXAS AT AUSTINDepartme-ntofMechanicalEngineering" I University Station C220() Austin, Texar 78712-0292 Telephone(512) 471-1131 FAX(512)471-8727 August 19, 2013U. S. Nuclear Regulatory Commission Attn: Document Control DeskWashington D. C. 20555

Subject:

Annual Report for The University of Texas at Austin, Docket 50-602

Dear Sir:

Enclosed is the 2012 Annual Report for the Nuclear Engineering Teaching Laboratory at TheUniversity of Texas at Austin. This report is being submitted in accordance with Section 6.6 ofthe Technical Specifications.

Please contact me at 512-232-5373 if you have any questions.

Sincerely, P. M. WhaleyNETL Associate Director

Enclosure:

2012 Annual Report'ýWo The University of Texas at AustinNuclear Engineering TeachingLaboratory 2012 Annual ReportNRC Docket 50-602DOE Contract No. DE-AC07-ER03919 2012 NETL Annual ReportDepartment of Mcchanical Engineering THE UNIVERSITY OF TEXAS AT AUSTINNuclear Engineering 7kcahing

Liborato,

-Austin. "l_'as 787.58512-232-5370

-FAX 512-471-4589-bttp//u-?u

e. atexas.edid/-

neniInet.htnl FORWARDThe mission of the Nuclear Engineering Teaching 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. The NFTL is also used in education programs for 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 government organizations.

The principal services offered by our reactor involve material irradiation, trace element detection, materialanalysis, and radiographic analysis of objects and processes.

Such services establish beneficial links to off-campus users, expose faculty and students to multidisciplinary research and commercial applications of nuclear science, and generate resources to helpsupport Nuclear Engineering activities.

Steven Biegalski.

Ph.D., P.E.Director, Nuclear Engineering Teaching Laboratory ii 2012 NETL Annual ReportTable of ContentsTable of Contents iiiExecutive Summary vForward vi1.0 NUCLEAR ENGINEERING TEACHING LABORATORY ANNUAL REPORT I1.1 General I1.2 Purpose of the report 22.0 ORGANIZATION AND ADMINSTRATION 42.1 Level 1 62.2 Level 2 72.3 Level 3 112.4 Level 4 132.5 Other Facility Staff 132.6 Faculty and Facility users 132.7 NETL Support 163.0 FACILITY DESCRIPTION 173.1 NETL History 173.2 NETL SITE, J.J. Pickle Research Campus 173.3 NETL Building Description 184.0 UT-TRIGA MARK II RESEARCH REACTOR 194.1 Reactor Core 204.2 Reactor Reflector 204.3 Reactor Control 215.0 EXPERIMENT AND RESEARCH FACILITIES 225.1 Upper Grid Plate 7L and 3L Experiment Facilities 225.2 Central Thimble 225.3 Rotary Specimen Rack 235.4 Pneumatic Tubes 235.5 Beam Port Facilities 245.6 Other Experiment and Research Facilities 295.7 Experiment Facility Utilization 305.7 Nuclear Program Faculty Activities 326.0 OPERATING SUMMARY 346.1 Operating Experience 346.2 Unscheduled Shutdowns 356.3 Utilization 366.4 Routine Scheduled Maintenance 396.5 Corrective Maintenance 396.6 Facility Changes 396.7 Oversight

& Inspections 41iii 2012 NETL Annual Report7.0 RADIOLOGICAL SUMMARY 437.1 Summary of Radiological Exposures 437.2 Summary of Radioactive Effluents 447.3 Radiological Exposure Received by Facility Personnel and Visitors 457.4 Environmental Surveys Performed Outside the Facility 45iv 2012 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.v 2012 NETL Annual Report1.0 NUCLEAR ENGINEERING TEACHING LABORATORY ANNUAL REPORTThe Nuclear Engineering Laboratory Annual Report covers the period from January throughDecember 2010. 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 Laboratory Activities 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 theUniversity using radioisotopes are conducted under a State of Texas license, L00485. Functions I

2012 NETL Annual Reportof 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 2010.1.2.1 TRIGA 11 Reactor Technical Specifications The NETL TRIGA II reactor Technical Specifications (section 6.6.1) requires submission of anannual report to the Nuclear Regulatory Commission.

Table 1.1 correlates specified requirements 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 anestimate 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 recommended A 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 7.41.2.2 The Department of Energy Fuels Assistance Program2 2012 NETL Annual ReportThe DOE University Fuels Assistance program (DE-AC07-051D14517, 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 2.2) are sent under separate cover to the DOE with this Annual Report.Table 2.2, DOE Reactor Fuel Assistance Report Requirements Fuel 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 accountability 3

2012 NETL Annual Report2.0 ORGANIZATION AND ADMINSTRATION The 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 appointed by 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 2011Win. Eugene Powell, ChairmanPaul L. Foster, Vice ChairmanR. Steven Hicks, Vice ChairmanFrancie A. Frederick, General Counsel to the Board of RegentsNash M. Home, Student RegentErnest AlisedaAlexis CranbergWallace Hall, Jr.Jeffrey D. Hildebrand Brenda Pejovichhttp://www.utsystem.edu/bor/currentRegents.htm, 07/31/2013 The 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 and Staff are listed in Table 2.2.4 2012 NETL Annual ReportTable 2.2University of Texas System Chancellor's OfficeFrancisco G. Cigarroa, MD, Chancellor Pedro Reyes, PhD, Executive Vice Chancellor for Academic AffairsScott C. Kelley, PhD, Executive Vice Chancellor for Business AffairsKenneth I. Shine, MD, Executive Vice Chancellor for HealthRanda S. Safady, Vice Chancellor for External Relations Dan Sharphorn, Vice Chancellor and General Counsel ad interimStephanie A. Bond Huie, Vice Chancellor for Strategic Initiatives ad interimBarry McBee, J D, Vice Chancellor for Governmental Relations Francie A. Frederick, JD, General Counsel to the Board of Regentshttp://www.utsystem.edu/sites/utsfiles/assets/general-files/OrgChart.pdf, 07/31/2013 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 theTechnical 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.5 2012 NETL Annual ReportFigure 2-1, Organizational Structure for the University of Texas at Ausitn TRIGA Reactor2.1 Level I Personnel Level 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.and schools; the Cockrell School of Engineering manages eight departments with individual degreeprograms.

The Nuclear Engineering Teaching Laboratory (NETL) is one of several education and research functions within the School. Current Level 1 personnel are reported in Table 2.3.2.1.1 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.6 2012 NETL Annual Report2.1.2 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 Engineering The 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 Department manages 8 areas of study, including Nuclear and Radiation Engineering.

Table 2.3The University of Texas at Austin Administration (Level 1)William Powers Jr., JD, President Steven W. Leslie, PhD, Executive Vice President and ProvostGregory L. Fenves, PhD, Dean, Cockrell School of Engineering Jayathi Murthy, Chair of Department of Mechanical Engineering 2.2 Level 2 Personnel The Nuclear Engineering Teaching Laboratory operates as a unit of the Department ofMechanical Engineering at The University of Texas. Level 2 personnel are those with directresponsibilities 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 2.4.7 2012 NETL Annual ReportTable 2.4Facility Staff & NRE FacultyNETL Facility StaffNRE FacultyDirectorAssociate DirectorReactor Supervisor Health Physicist

& Lab managerAdministrative Associate Electronics Technician/

Reactor OperatorHealth Physics Technician S. Biegalski P. M. WhaleyM. KrauseT. TippingD. JudsonL. WelchE. HerraraN. MohammedA. DavisJ. NavarU. Chatterjee J. SimsS. Biegalski S. Landsberger E. Schneider M. Deinhert2.2.1 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.

2.2.4 Safety Oversight Safety oversight is provided for radiation protection and facility safety functions.

A University of Texas Radiation Safety Committee is responsible programmatically for coordination, trainingand oversight of the University radiation protection

program, with management of the program8 2012 NETL Annual Reportthrough a Radiation Safety Officer.

Current personnel on the Radiation Safety Committee arelisted on Table 2.5.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 committee function 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 2.6.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 2.5Radiation Safety Committee 2012-2013 Gerald W. Hoffmann, Ph.D., Chair, Department of PhysicsJuan M. Sanchez, Ph.D., Vice Chair, Vice President for ResearchNeal Armstrong, Ph.D., Vice ProvostKevin Dalby, Ph.D., College of PharmacyW. Scott Pennington, ex-officio, Office of Environmental Health & SafetyJon D. Robertus, Ph.D., Department of Chemistry

& Biochemistry Bob G. Sanders, Ph.D., School of Biological SciencesPeter Schneider,

Director, Office of Environmental Health & SafetyTracy Tipping, Nuclear Engineering Teaching Laboratory http://www.utexas.edu/research/resources/committees#rsc, 07/31/2013 Radiation Safety Officer.

A Radiation Safety Officer holds delegated authority of the Radiation Safety 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.

Radiation Safety Officer responsibilities are outlined in The Universit, of Texas at AustinRadiation Safet, 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.9 2012 NETL Annual ReportA 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 2.6Reactor Oversight Committee 2011-2012 Erich Schneider (ME), ChairHoward Liljestrand (CAEE)Lynn Katz (CAEE)Steven Biegalski (ME)Lawrence R. Jacobi (External Representative)

Jodi Jenkins (External Representative)

Jayathi Murthy, ex-officio (ME)Michael Krause, ex-officio (NETL)Tracy Tipping, ex-officio (NETL)Mike Whaley, ex-officio (NETL)John G. Ekerdt, ex-officio Scott Pennington, other (Radiation Safety Officer)http://www.engr.utexas.edu/faculty/committees/225-roc, 07/31/2013 2.3 Level 3 Personnel 10 2012 NETL Annual ReportLevel 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 2.4.2.3.1 Reactor Supervisor The 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, implements modifications 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 Physicist The Health Physicist function is incorporated into a Laboratory Manager position, responsible for 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.11 2012 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-time Undergraduate 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 personnel such 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 educational missions 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, including proposal 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 industrial organizations and/or groups.The NETL provides unique facilities for nuclear analytic techniques, including but notlimited to elemental analysis (instrumental neutron activation

analysis, prompt gamma analysis),

12 2012 NETL Annual Reportmeasurements 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 Personnel Reactor 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 Undergraduate Research 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.2.6 Faculty and Facility Users13 2012 NETL Annual ReportThe complement of faculty and facility users at the NETL is extremely variable.

Functionally faculty 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 Utilization The NETL is integrated in the Nuclear and Radiation Engineering program (NRE) of Mechanical Engineering (ME). The ME faculty complement directly supporting the nuclear education program is listed in Table 2.7. 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.

Table 2.7University of Texas Nuclear and Radiation Engineering program FacultyDr. Sheldon Landsberger, Nuclear and Radiation Engineering Professor Dr. Steven Biegalski, Nuclear and Radiation Engineering Associate Professor Dr. Erich Schneider, Nuclear and Radiation Engineering Assistant Professor Dr. Ofodike A. Ezekoye, Thermal Fluids Systems Professor Dr. Kendra M. Foltz-Biegalski, Nuclear and Radiation Engineering Research EngineerDr. Elmira Popova, Operations Research Associate Professor Dr.Mark Deinert, Nuclear and Radiation Engineering, Thermal Fluid Systems, Assistant Professor Dr.Mitch Pryor, Robotics Research Group Research Associate Of the five undergraduate Nuclear Engineering courses and the dozen graduate NuclearEngineering

courses, five courses make extensive use of the reactor facility.

Table 2.8 lists thecourses currently in the UT course catalog, many of which use the reactor and its experiment facilities.

Table 2.8, Nuclear Engineering CoursesUndergraduate 14 2012 NETL Annual ReportME 136N, 236N: Concepts in Nuclear and Radiological Engineering ME 337C: Introduction to Nuclear Power SystemsME337F: Nuclear Environmental Protection ME 337G: Nuclear Safety and Security~il ME 361 E: Nuclear Operations and Reactor Engineering ME 361 F: Radiation and Radiation protection Laboratory GraduateME 388C: Nuclear Power Engineering ME 388D: Nuclear Reactor Theory IW']ME 388F: Computational Methods in Radiation Transportl 11ME 388G: Nuclear Radiation ShieldingP 1]ME 388H: Nuclear Safety and Security[1]

ME 388J: Neutron Interactions and their Applications in Nuclear Science and Engineeringl'l ME 388M: Mathematical Methods for Nuclear and Radiation Engineers1'1 ME 388N: Design of Nuclear Systems I1[1ME 388P: Applied Nuclear Physics1'1 ME 388S: Modem Trends in Nuclear and Radiation Engineeringr 1]ME 389C: Nuclear Environmental Protection NE 389F: The Nuclear Fuel Cycler11ME 390F: Nuclear Analysis Techniques ME 390G: Nuclear Engineering Laboratory ME390T: Nuclear-and Radio-Chemistry NOTE[]],

Academic courses with minimal or no use of the reactor facilities The 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 Dissertation Proposal 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 FloridaMemorial University in Miami Gardens, Florida have participated in this these educational efforts.15 2012 NETL Annual ReportIn 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.16 2012 NETL Annual Report3.0 FACILITY DESCRIPTION 3.1 NETL HistoryDevelopment of the nuclear engineering program was an effort of both physics and engineering faculty during the late 1950's and early 1960's. The program became part of the Mechanical Engineering 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 theResearch Office Complex, illustrating the diverse research activities on the campus. A17 2012 NETL Annual ReportCommons Building provides cafeteria

service, recreation areas, meeting rooms, and conference facilities.

3.3 NETL Building Description The 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.18 2012 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 metallurgy REArCTC BRflCE..,,

r COT O il0l URIVE*- THIMBLEaROTA ATT1 3 .E *Co I C. .DTAilFigure 4-1, UT TRIGA Mark II 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.19 2012 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 inherently safe 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.Figure 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 welding20 2012 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 performing reactor physics experiments as well as reactor operator training.

This advanced system providesfor flexible and efficient operation with precise power level and flux control, and permanent retention 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 (regulating and 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 134C 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.21 2012 NETL Annual Report5.0 EXPERIMENT AND RESEARCH FACILITIES Neutrons produced in the reactor core can be used in a wide variety of research applications including 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. Experiments may 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 radioisotope

sources, radiation producing

machines, and laboratories for spectroscopy and radiochemistry.

5.1 Upper Grid Plate 7L and 3L Facilities The 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-element spaces).

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.22 2012 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 laboratory room, and the third operates in conjunction with an automatic sample changer and countingsystem.5.5 Beam Port Facilities Five 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 accommodate a wide variety of experiments.

Shielding reduces radiation levels outside the concrete biological shield 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).

23 2012 NETL Annual ReportBP #3BP #4BP #5I ! 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.

24 2012 NETL Annual ReportA reactor-based slow positron beam facility is being fabricated at BPl. 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 13+ 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, tenninating 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 characteristic energy 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.25 2012 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 environmental samples 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+01I.E+001.E-01c 1.E-02o:1.E-031.E-040 1000 2000 3000 4000 5000 6000 7000 8000Energy [keVJFigure 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.26 2012 NETL Annual Report~~j~7Ja Rn -abXL-V zp Mbmg-G Igj~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 moderator chamber 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 facilities 27 2012 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 illuminate a sample. The intensity of the exiting neutron field varies according to absorption and scattering characteristics of the sample. A conversion material generates light proportional to the intensity of the neutron field as modified by the sample.Disk woiatReact"r Reflector cmI FirstCollimator ScondiraFigure 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 30gtm) over a small (approximately 1/2/2 in.) field of view. A larger image can be obtained using amore conventional 7X7 in.26LiF/ZnS scintillation screen.28 2012 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 conversion apparatuses can eb 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 Facilities The NETL facility makes available several types of radiation facilities and an array of radiation detection 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 Radioisotopes

Radioisotopes are available in a variety of quantities.

Gamma and beta sources generally inmicrocurie to millicurie quantities are available for calibration and testing of radiation detection equipment.

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 radiochemical reactions.

29 2012 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 Laboratories There 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 radiochemistry laboratory was developed with support from the Department of Energy (DOE). The laboratory consists 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 Utilization Figure 5-1 provides the number of hours of reactor operation allocated to experiments in theapplicable

facility, with abbreviations in Figure 5.1 explained in the table following.

There were1180.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of utilization for experiments; operations supported irradiation in more than oneexperiment facility simultaneously for 30.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in 2011, therefore total time for reactoroperations was 1149.9 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 experiments includesthe "console key on" time.30 2012 NETL Annual Report2012 Experiment Hours Distribution Tours and Pulses Classroom and Maintenance NAA RSR NAA TPNT2% Operator Training 6% 4% 3%12%2P%3L' 1%BP20%Figure 5-1, Utilization of Experiment HoursTable 5.1Terminology for Figure 5-1PGNAAPb3LCd3LNAAEPTNTNAA TPNTNAA RSRTourClassesTrainingPulseRadiography Prompt 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 epithermal neutrons) 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 rackGeneral 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 radiography 31 2012 NETL Annual Report5.8 Nuclear Program Faculty Activities Projects and publications associate with the NETL during 2012 are provided below.Table 5.4, Publications

-2012CA Rios Perez, SR Biegalski, MR Deinert, "Methodology for using prompt gamma activation analysis to measure the binary diffusion coefficient of a gas in a porous medium,"

NuclearInstruments and Methods:

B, 293, 21-25, 2012.S.R. Biegalski, TW Bowyer.,

P Eslinger, JA Friese, LR Greenwood, DA Haas, JC Hayes, 1.Hoffman, M Keillor, HS Miley, M. Moring, "Analysis of Data from Sensitive U.S. Monitoring Stations for the Fukushima Daiichi Nuclear Reactor Accident,"

Journal of Environmental Radioactivity, 114, 15-21,2012.

C. Rios Perez, J. Lowrey, S. Bieglski, M. Deinert, "Xenon Diffusion Studies with PromptGamma Activation Analysis,"

Journal of Radioanalytical and Nuclear Chemistry, 291(1), 261-265, 2012.C. Egnatuk, J. Lowrey, S. R. Biegalski, D. Haas, J. Orrell, V. Woods, M. Keillor, "Production of 47Ar in the University of Texas TRIGA Reactor Facility,"

Journal of Radioanalytical andNuclear Chemistry,291(1),

257-260, 2012.J. Lowrey, S. Biegalski, "Comparison of Least-Squares vs. Maximum Likelihood Estimation for Standard Spectrum Technique of b-g Coincidence Spectrum Analysis,"

NuclearInstruments and Methods:

B, 270(1), pp. 116-119, 2012.C. Egnatuk, S. Biegalski, "Production of 37Ar through the Irradiation of Ca-Containing Compounds,"

Transactions of the American Nuclear Society, Vol. 106, 2012.M. Deinert, Los Alamos National Laboratory, December 13, 2012. Transport processes andthe detection of clandestine nuclear materials and testsM. Deinert, American Society of Mechanical Engineers International Mechanical Engineering Congress and Exposition, November 11-15, 2012, Houston, TX. Traveling wave reactors, thefuture of sustainable nuclear power?M. Deinert, American Nuclear Society Annual Meeting, November I I-1 5,2012, San Diego,CA. Velocity of a fission front in a traveling wave reactorM. Deinert, American Nuclear Society Annual Meeting, June 24-28, 2012, Chicago, IL.Increasing Inert Matrix Fuel BurnupM. Deinert, Society of Industrial and Applied Mathematics Conference on Non-Linear Wavesand Coherent Structures, June 13-16, 2012, Seattle, WA. Propagation of a constant velocityfission waveM. Deinert, Pacific Northwest National Laboratory, June 12, 2012. Advance fuel cycles andreactors for sustainable nuclear powerM. Deinert, Physics of Reactors (Physor) 2012, April 15-20, 2012, Knoxville TN. Axialgrading of Inert Matrix FuelsM. Deinert, Physics of Reactors (Physor) 2012, April 15-20, 2012, Knoxville TN. Neutrondamage reduction in a traveling wave reactorM. Deinert, MARC 2012, March 27, 2012, Kona Hawaii. Differential transport of Noble gasesin porous media and its effect on isotopic ratiosAmerican Society of Mechanical Engineers International Mechanical Engineering Congressand Exposition,

Houston, November 11-15, 2012. Performance of inert matrix fuel foractinide transmutation.

GD Recketenwald, MR Deinert.American Society of Mechanical Engineers International Mechanical Engineering Congress32 2012 NETL Annual Reportand Exposition,

Houston, November 11-15,2012.

A simple model for the intensity andangular distribution of radiation transmitted through clouds. GD Recketenwald, MR DeinertAmerican Society of Mechanical Engineers International Mechanical Engineering Congressand Exposition,

Houston, November 11 -15, 2012. Measuring diffusion coefficients for Noblegasses through a geological medium using prompt gamma activation analysis.

CR Perez, MRDeinertTFS/NRE student seminar series. March 29, 2012. Study of xenon diffusion on aComprehensive Nuclear-Test-Ban Treaty frame using prompt gamma activation analysis.

CRPerez, MR DeinertAmerican Society of Mechanical Engineers International Mechanical Engineering Congressand Exposition,

Houston, November 11-15,2012.

Scale effects in the latent heat of liquid-solid phase transitions.

J-H Shin, MR DeinertAmerican Society of Mechanical Engineers International Mechanical Engineering Congressand Exposition,

Houston, November 11-15, 2012. How Dynamic Cloud Cover Affects thePerformance of Solar Power Facilities.

BL Stoll, MR DeinertTFS/NRE student seminar series. March 29, 2012. How dynamic cloud cover affects theperformance of solar power facilities.

BL Stoll, MR DeinertRecktenwald, GD, MR Deinert (2012): Cost probability analysis of reprocessing spent nuclearfuel. Energy Economics, 34, 1873-1881

Osborne, A, GD Recktenwald, MR Deinert (2012): Propagation of a solitary fission wave.Chaos, 22, 0231480Osborne, AG, GD Recktenwald, MR Deinert (2012): Propagation velocity of a fission front ina traveling wave reactor.

Transactions of the American Nuclear Society, Vol. 107Recktenwald, GD, MR Deinert (2012): Increasing Inert Matrix Fuel Burnup. Transactions ofthe American Nuclear Society, Vol. 106Osborne, AG, MR Deinert (2012): Neutron damage reduction in a traveling wave reactor.Proceedings of Physor 2012, Knoxville, TN, April 15-20, 2012Recktenwald, GD, MR Deinert (2012): Axial grading of Inert Matrix Fuel. Proceedings ofPhysor 2012, Knoxville, TN. April 15-20, 201233 2012 NETL Annual Report6.0 FACILITY OPERATING SUMMARIES 6.1 Operating Experience The UT-TRIGA reactor operated for 1160 hours0.0134 days <br />0.322 hours <br />0.00192 weeks <br />4.4138e-4 months <br /> on 215 days in 2012, producing a total energyoutput of 591.8 MW-hrs. The history of operations over the past seventeen years of facilityoperation is provided in Figures 6-1 and 6-2. As illustrated, operating time has shown a markedincrease from the first several years and has been relatively stable for the past decade. Varyingresearch requirements over the past few years have led to a decrease in total energy generation.

0 25.0020.00.2161 5.000.0E 5-00z0.00JanuaryJApril July OctoberFigure 6-1, Days of Operation 25.0-.20.015.00310.05.00.0JanuaryAprilJuly OctoberFigure 6-2, Energy Generation 34 2012 NETL Annual Report6.2 Unscheduled Shutdowns Reactor 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 ofthe manual scram switch in normal reactor shutdowns is not a protective action. The following definitions in Table 6.1 classify the types of protective actions recorded.

Table 6.1, Protective Action Definitions Description Protective ActionSafety System SettingLSSSCondition for Operation LCO -(analog detection)

Condition for Operation LCO -(digital detection)

Manual Switch(protective action)Automatic 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 12 unscheduled shutdowns that occurred in 2012, all of which were initiated bythe reactor safety system.Table 6.2, SCRAM Log for 2012Date02/09/2012 02/22/2012 02/23/2012 03/02/2012 03/02/2012 03/02/2012 03/26/2012 04/02/2012 06/15/2012 09/28/2012 11/02/2012 11/20/2012 Time14:2616:2213:4508:4608:4908:5414:3913:5611:3611:2314:3009:38TypeSCRAM FTISCRAM KEY OFFSCRAM KEY OFFSCRAM KEY OFFSCRAM KEY OFFSCRAM KEY OFFSCRAM FTISCRAM FTISCRAM FTISCRAM OP ERRORSCRAM OP ERRORSCRAM OP ERRORCommentsThermocouple Intermittent FailureSpurious Intermittent Key Contact BreakSpurious Intermittent Key Contact BreakSpurious Intermittent Key Contact BreakSpurious Intermittent Key Contact BreakSpurious Intermittent Key Contact BreakThermocouple Intermittent FailureThermocouple Intermittent FailureThermocouple Intermittent FailurePower Fluctuations in Auto Operation ModeOperator Error in Pulse Operation Power Fluctuations in Auto Operation ModeThe five key off scrams were the major contributor to the safety system scrams that took place in2012. In all the instances the Key-Off Scrams occurred due to potential intermittent contact35 2012 NETL Annual Reportcontinuity issues between the reactor key and its slot. Due to the intermittent behavior of thecontact, it was attributed to potential oxidation at the contact point. However, the symptomsstopped following more usage. Attempts to recreate the failure have not been successful.

Thefailure mode is conservative and acceptable until the channel fails in a more consistent mode.There were four temperature channel trips related to thermocouple intermittent.

In all cases,time dependent data indicates fuel temperatures were normal and the trips occurred because ofsignal transients not indicative of actual fuel temperature.

Attempts to isolate the trip to aspecific component or recreate the failure have not been successful.

The failure mode isconservative and acceptable until either the channel fails in a more consistent mode or thecharacteristics leading to the actuations can be identified.

Power level monitoring signals during steady state operations fluctuate because the digital powerlevel monitoring has some intrinsic noise related to signal sampling and analysis.

Three reactortrips occurred as transient fluctuations during high power operations exceeded the steady statepower level trip point. Safety analyses demonstrate transients (pulses) to orders of magnitude greater than the steady state power level limit do not result in unacceptable consequences, andthese trips are not a safety issue.6.3 Utilization Utilization 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.

Fig. 6-3 provides a representation ofthe facility research with these categories.

Table 6.3 list the external research collaborations atNETL since 2009. Facility usage is largely dominated by the use of nuclear analytical techniques for sample analysis.

These techniques include neutron activation

analysis, neutronradiography, neutron depth profiling, and prompt gamma activation analysis.

36 2012 NETL Annual ReportFigure 6-3, Facility Utilization Table 6.3, NETL External Research Collaborations since 2009External Collaborator Location Facility Utilization Trinitek

Services, Inc.Environment CanadaBridgeport Instruments Carollo Engineering Evergreen SolarKaizen Innovations Idaho National Laboratory Illinois State Geological SurveyUT BiologyDepartment of Geological SciencesLos Alamos NationalLaboratory

Lolodine, LLCUT Health Science CenterPacific Northwest NationalLaboratory RMT, Inc.Signature ScienceBiomedical Engineering Department Southwestern University Comprehensive Nuclear-Test-Ban TreatyOrganization Clarkson University JWK Corporation Civil and Environmental Engineering Department Sandia Park, NMGatineau, Quebec,CanadaAustin, TXAustin, TXMarlboro, MAGeorgetown, TXIdaho Falls, IDChampaign, ILAustin, TXAustin, TXLos Alamos, NMJersey City, NJHouston, TXRichland, WAMadison, WIAustin, TXAustin, TXGeorgetown, TXVienna, AustriaPotsdam, NYAnnandale, VAAustin, TX37Soil sample analysisArctic air filter analysisRadiation detector development Radiation damage studiesSilicon wafer trace element analysisSoil sample analysisIsotope production Water sample analysisSoil sample analysisGeological sample irradiation Sample irradiations Nut AnalysisNanoparticle analysisIsotope Production Water sample analysisMaterial irradiations and shrapnelanalysisTissue sample analysisPlant sample analysis and studentlaboratories Radioxenon production Air filter analysisSample irradiations Fly ask sample analysis 2012 NETL Annual ReportTable 6.3, NETL External Research Collaborations since 2009External Collaborator Location Facility Utilization National Center for Energy,Science and Nuclear Rabat, Morocco Soil sample analysisTechnologies Nanospectra Biosciences,

Houston, TX Tissue sample analysisInc.U.S. Nuclear Regulatory Rockville, MD Reactor operations trainingCommission NTS Albuquerque, NM Isotope production Omaha Public Power District Blair, NE Boral coupon analysisTEKLAB Collinsville, IL Water sample analysisXIA Hayward, CA Radioxenon production Lawrence Livermore Livermore, CA Isotope production National LaboratoLs Various 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 3200samples were irradiated during 2011, fairly consistent with previous years of NETL operations as illustrated in Figure 6-4.Number of Samples Irradiated by YearMW0200010002003 2004 2005 2006 2007 2008 2009 2010 2011 2012YearFigure 6-4, NETL Sample Activation 38 2012 NETL Annual Report6.4 Routine Scheduled Maintenance All surveillances and scheduled maintenance activities were completed during the reporting yearat the required frequencies.

All results met or exceeded the requirements of the Technical Specifications.

6.5 Corrective Maintenance Activities this reporting period predominately consisted of adjustment of instrument systemcomponents (potentiometers or digital system constants) to re-tune or recalibrate the circuits torecommended levels. Corrective maintenance activities included the replacement of individual components or assemblies with like or similar replacement parts. The following list is asummary of the corrective maintenance activities accomplished by facility staff:* Replacement of burnt out indicator lamps in radiation monitoring systems from anincandescent lamp to an LED.* Adjustment of NMI 000 Startup Fission Chamber cable shield ground.* Replacement of Argon CAM reading meter from paper to digital record and indication

• Replacement of a cracked fitting to the pool water Purification Pump conductivity sensor* Replacement of control console video/computer monitors.

• Replacement of malfunctioning Action Pak in DAC6.6 Facility ChangesDuring the 2012 calendar year changes in in facility staffing included termination of two SeniorReactor Operator (SRO) Licenses.

Additionally there were two new operator licenses issued bythe NRC, one of which was a SRO License.

Facility modifications and procedures changes aredescribed below.6.6.1 Staff changes:There were two Senior Reactor Operator Licenses terminated during 2012, both of whomgraduated the University of Texas at Austin and left to further their careers'.

Two reactoroperator licenses were granted to undergraduate students (one of which was an SRO License)39 2012 NETL Annual Report6.6.2 Facility changesDuring 2012 enhancements to the existing facility access control and security monitoring systems supported by the Global Threat Reduction Initiative (DOE/NNSA) was done. Facilitymodifications included the upgrading and addition of security systems for the reactor facility.

6.6.3 Procedure revision/updates Several minor procedure revisions were made in 2012 and one new procedure change wasproposed.

Minor revisions were made in MAIN-5, OPER-2 and PLAN-E. These changes weremade to clarify some wording and better explain the reasoning for procedures, without changingthe procedures intent.Pending procedure updates include revision of security procedures based on NRC rulemaking in1OCFR73, and changes to HP procedures.

Additional changes pending include changes resulting from requested but not yet approved Technical Specification amendments.

6.6.4 Facility Changes Accomplished in Accordance with Other Regulatory Requirements:

There were no changes 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 Linder 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 shutdown).

A request for renewal of the facility operating license was made, with notification by tileUSNRC that the UT facility meets requirements for operation under "timely renewal."

40 2012 NETL Annual Report6.7 Oversight

& Inspections Inspections 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 April 18, 2012Second Quarter NoneThird Quarter NoneFourth Quarter November 28, 2012No recommendations were identified by the Committee.

Inspections 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.

An NRC inspection was conducted as indicated in Table 6.4. No findings ofsignificance were identified.

Table 6.4, License Inspections at the NETLTable 6.5, License Inspections License DatesR-129 NoneR-129 NoneSNM- 180 NoneL00485 (81) 27 march 2012Routine inspections by the Office of Environmental Health and Safety (OEHS) for compliance with 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.

No41 2012 NETL Annual Reportsignificant 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.Table 6.6, Other Oversight Inspections Function DatesFAA inspection for hazmat shipping 12 January 2012USDA inspection for Regulated Soils Permit 16 October 201242 2012 NETL Annual Report7.0 RADIOLOGICAL SUMMARY7.1 Summary of Radiological Exposures The Radiation Protection Program for the NETL facility provides monitoring for personnel radiation

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 Frequencies Frequency Radiation Protection Requirement Weekly 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.Background checks of low background alpha/beta counting system.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.Calibrate area monitors in neutron generator room.Perform Chi-square test, and determine HV plateaus and detection efficiencies on the low background alpha/beta counting system.Semi-Annual Inventory emergency locker.Calibrate portable radiation monitoring instruments.

Calibrate continuous air monitor, argon monitor, area rad. monitors.

Calibrate personnel pocket dosimeters.

Leak test and inventory sealed sources.Annual Conduct ALARA Committee meeting.Conduct personnel refresher training.

Calibrate emergency locker portable radiation detection equipment 7.2 Summary of Radioactive Effluents 43 2012 NETL Annual ReportThe radioactive effluent paths are ventilation for air-borne radionuclides, and the sanitary sewersystem for liquid radionuclides.

The most significant airborne radionuclide effluent is argon-41.

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 2011. A smallquantity of radioactive waste is stored for decay or aggregation for a shipment.

A small amountof liquid radioactive waste was transferred to OEHS for consolidation and disposal with otheruniversity radioactive waste.7.2.2 Discharged Airborne 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 6.79x106 ýtCi of argon 41 discharged during calendar year 2012, with the annual averagerelease 3% 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.

To date no discharges have occurred.

Small quantities of liquid scintillation cocktail or dilute concentrations below the limits of 10CFR 20 in the NETL laboratories may be disposed directly to the sanitary sewer. Liquiddisposals are infrequent.

7.3 Radiation Exposure Received by Facility Personnel and Visitors44 2012 NETL Annual ReportFor calendar year 2012, 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 dosimeter map. During 2012, the dosimeter vendor used by NETL went through an extensive upgrade oftheir processing system. Apparently due to the changes in progress throughout the year, theNETL environmental dosimeters experienced processing issues. The first quarter dosimeters were processed using a control value of 6 mrem per month (3 months of actual exposure timeplus approximately 2 weeks of transit time for shipping prior to and after the exposure period fora total of approximately 4 months or 24 mrem) without using the actual control badge value (41mrem). The reported doses for positions 1, 4, and 6 were "minimal"

(< I mrem), positions 3 and5 were 2 mrem, and position 2 was 4 mrem. Had the actual control dose been used, all positions would have been minimal.

For the second quarter, no control value was used and thus nobackground was subtracted.

The actual control value was 55 mrem. Reported doses for all thepositions ranged from 20 to 26 mrem. Again, had the actual control value been used, allpositions would have been minimal.

For the third quarter, the actual control value was used andall positions were reported as minimal dose. For the fourth quarter, an "average control value"of 25 mrem was used instead of the actual control value of 70 mrem. The reported doses for allthe positions ranged from 2 to 7 mrem. Again, had the actual control value been used, allpositions would have been minimal.

NETL continues to work with the vendor to reach aconsistent and reliable approach to processing the environmental dosimeters.

45 2012 NETL Annual ReportPARKINGFigure 7- 1, NETL Environmental Monitor Locations In addition to the NETL monitors, the Texas Department of State Health Services monitorsexterior locations near NETL indicated as positions I through 5 on the TDSHS TLD map. Theonly report received in 2012 was for the second quarter in which a dose of 0 mrem was reportedfor all positions.

In January 2013, TDSHS notified NETL that at the beginning of 2012, theyhad switched from an in-house dosimetry program to an external dosimetry vendor (the samevendor used by NETL) and they were experiencing significant issues with how results were to beinterpreted.

They hoped to provide monitoring results once they worked through the issues. Asyet, no additional reports have been received.

46 2012 NETL Annual ReportCooglemaps.

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