ML051020355

Annual Report for the University of Texas at Austin

ML051020355
Person / Time
Site:	University of Texas at Austin
Issue date:	03/31/2005
From:	O'Kelly D University of Texas at Austin
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML051020355 (66)

Text

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THE UNIVERSITY OF TEXAS AT AUSTIN Nuclear Engineering Teaching Laboratory Austin, Texas 78758 512-232-5370 - FAX512-471-4589 httpllwww.me.ttexas.eduf-netblnethtml March 31, 2005 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington D. C. 20555

Subject:

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

Dear Sir:

Enclosed is the 2004 Annual Report for the Nuclear Engineering Teaching Laboratory at The University of Texas at Austin. This report could not be submitted electronically due to the NRC requiring new submittal information. This report is being submitted in accordance with Section 6.6 of the Technical Specifications.

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

Sincer Sean NETL Director

Enclosure:

2003 Annual Report cc: A. Adams, DRIP/RTR Project Manager CF#5-30 C)Q,

C)o

The University of Texas at Austin Nuclear Engineering Teaching Laboratory 2004 Annual Report NRC Docket 50-602 DOE Contract No. DE-AC07-ER03919

'a-2004 NETL Annual Report r

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2004 NETL Annual Report Tables of Contents ii Executive Summary iii Forward iv 1.0 Nuclear Engineering Teaching Laboratory 1-1 1.1 Introduction 1-1 Purpose of the Report Availability of the Facility Operating Regulations NETL History 1.2 NETL Building 1-4 J.J. Pickle Research Campus NETL Building Description Laboratories, Equipment 1.3 UT-TRIGA Mark II Research Reactor 1-7 Reactor Description Experiment Facilities Beam Port Facilities 1.4 Nuclear Engineering Academic Program 1-12 1.5 NETL Divisions 1-13 Operations and Maintenance Laboratory Operations Health Physics 2.0 Annual Progress Report 2-1 2.1 Faculty, Staff, and Students 2-1 2.2 Education and Training Activities 2-8 2.3 Research and Development Projects 2-9 2.4 Publications, Reports, and Papers 2-14 3.0 Facility Operating Summaries 3-1 3.1 Operating Experience 3-1 3.2 Reactor Shutdowns 3-1 3.3 Utilization 3-4 3.4 Maintenance 3-4 3.5 Facility Changes 3-4 3.6 Laboratory Inspections 3-7 3.7 Radiation Exposures 3-9 3.8 Radiation Surveys 3-15 3.9 Radioactive Effluents, Radioactive Waste 3-20 iii

2004 NETL Annual Report EXECUTIVE

SUMMARY

The Nuclear Engineering Teaching Laboratory (NETL) facility continues to support the academic and research missions of The University of Texas but has begun to provide these support functions to other institutions. The NETL and NRE programs received an Innovations in Nuclear Infrastructure and Education (INIE) grant from the DOE in June of 2002. The INIE Southwest Consortium is a partnership between the University of Texas, Texas A&M University, the University of Newv Mexico and the Sandia National Laboratories. The funds from this program have permitted significant upgrades of the experimental facilities and research programs. The environmental research and analysis services perforned by the NETL during this past year supported the Sandia National Laboratories, Los Alamos National Laboratory. Oak Ridge National Laboratory, the Canadian government, the National Oceanic and Atmospheric Administration, the University of Illinois, Texas A&M University and the State of Texas.

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2004 NETL Annual Report FORWARD The mission of the Nuclear Engineering Teaching Laboratory at The University of Texas at Austin 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 commullity.

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 and nuclear science. In addition, students in non-nuclear fields such as physics, chemistiy, and biology use the reactor in laboratory course work.

It may also be used in education programs for nuclear power plant personnel, secondary schools students and teachers, antc the 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, material analysis, and radiographic analysis of objects and processes.

Such services establish beneficial links to off-campus users, expose faculty and students to multidisiplinary research and commercial applications of nuclear science, and earn revenues to help support Nuclear Engineering activities.

Sheldon Landsberger Director Nuclear Engineering Teaching Laboratory v

i-Chapter 1

2004 NETL Annual Report 1.0 NUCLEAR ENGINEERING TEACHING LABORATORY 1.1 Introduction Purpose of the Report The Nuclear Engineering Teaching Laboratory (NETL) at The University of Texas at Austin prepares an annual report of program activities. Infornation in this report provides an introduction to the education, research, and service programs of the NETL. A TRIGA nuclear reactor is the major experimental facility at the Laboratory. The reactor operates at power levels up to 1100 kilowatts or with pulse reactivity insertions up to 2.2% Ak/k.

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Figure 1-1 NETL - Nuclear Engineering Teaching Laboratory The annual reports also satisfy requirements of the University Fuel Assistance Program, U.S. Department of Energy (DOE) [contract number DE-AC07-ER03919, Amendment A015; C85-110742 Task Order 2, Mod. 1], and the licensing agency, the U.S. Nuclear Regulatory Commission (NRC) [docket number 50-602]. This annual report covers the period from January 1, 2004 to December 31, 2004.

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2004 NETL Annual Report Availability of the Facility The NETL facility serves a multipurpose role. The use of NETL by faculty, staff, and students in the College of Engineering is the Laboratory's primary function.

In addition, the development and application of nuclear methods are done to assist researchers from other universities, industry, and government. NETL provides services to industry, goveniment and other laboratories for the testing and evaluation of materials. Public education through tours and demonstrations is also a routine function of the laboratory operation.

Operating Regulations Licensing of activities at NETL involve both Federal and State agencies.

The nuclear reactor is subject to the terms and specifications of Nuclear Regulatory Commission (NRC)

License R-129, a class 104c research reactor license.

Another NRC license, SNM-I80, for special nuclear material, provides for the use of a subcritical assembly with neLtro011 SourCS.

Both licenses are responsibilities of the NETL. For general use of radioisotopes the University maintains a broad license with the State of Texas, L00485. Functions of the broad license are the responsibility of the University Office of Environmental Health and Safety.

NETL History Development 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 remains to this day.

The program installed, operated, and dismantled a TRIGA nuclear reactor at a site oil the main campus in the engineering building, Taylor Hall. Initial criticality for the first UT reactor was August 1963 vith. the final operation in April 1988. Power at startup was 10 kilowatts (1963) with one powver upgrade to 250 kilowatts (1968). Thle total burmup during a 25 year period from 1963 to 1988 was 26.1 megawatt-days.

Pulse capability of the reactor was 1.4% Ak/k with a total of 476 pulses during the operating history.

Dismantling and decommissioning of the facility were completed in December 1992.

Planning for a new facility, which led to the shutdowvn of the campus facility, began in October 1983, with constniction commencing in December 1986 and continUinig until Mlay 1989.

The final license wvas issued in January 1992, and initial criticality occurred on March 12, 1992.

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2004 NETL Annual Report The newv facility, including support laboratories, administrative offices, and the reactor is the central location for all NETL activities.

Land use in the area of the NETL site began as an industrial site during the 1940's.

Following the 1950's, lease agreements between the University and the Federal government led to the creation of the Balcones Research Center. In the 1990's, the University became offner of the site, and in 1994 th6 site name was changed to the J.J. Pickle Research Campus to honor retired U.S. Congressman James "Jake" Pickle.

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lIt 2004 NETL Annual Report 1.2 NETL Building J.J. Pickle Research Campus The J.J. Pickle Research Campus (PRC) is a multidiscipline research campus with a site area of 1.87 square kilometers. Areas of the site consist of two approxinmately equal east and wvest tracts of land. An area of about 9000 square meters on the east tract is the location of the NETL building.

Sixteeh separate research units and at least five other academic research programs, including the NETL facility, have research efforts with locations at the research campus. Adjacent to the NETL site is the Center for Research in Water Resources and Bureau of Economic Geology, which are examples of the diverse research activities on1 the campus. A Commons Building provides cafeteria service, recreation areas, meeting rooms, and conference facilities. Access to the NETL site is shown in Figure 1-2.

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2004 NETL Annual Report 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 sq ft), eight support laboratories (217 sq m, 2340 sq fl), and six supplemental areas (130 sq m, 1430 sq fi). Conference and office space is allocated to 12 rooms totaling 244 sq in (2570 sq ft). One of the primary laboratories contains the TRIGA reactor pool, biological shield structure, and the neutron beam experiment areas. A second primary laboratory consists of 1.3 meter (4.25 ft) thick walls for use as a general purpose radiation experiment facility. Other areas of the building include support shops, instrument laboratories, measurement laboratories, and material handling laboratories.

Laboratories. Equipment 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, a gamma irradiator, various radioisotope sources, and several radiation producing machines.

The gamma irradiator is a multicurie cobalt-60 source with a design activity of I 0,000 curies. The gamma irradiator is in permanent storage and is not currently available for use.

Radioisotopes are available in millicurie quantities for calibration of radiation detection equipment.

Neutron sources of plutonium-beryllium and califomnium-252 are available. A subcritical assembly of 20% enriched uranium in a polyethylene moderated cylinder provides an experimental device for laboratory demonstrations of neutron multiplication and neutron flux measurements.

Laboratories provide locations to setup radiation experiments, test instrumentation, prepare materials for irradiation, process radioactive samples and experiment with radiochemical reactions.

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2004 NETL Annual Report 1.3 UT-TRIGA MARK II Research Reactor The TRIGA Mark II nuclear reactor at the Nuclear Engineering Teaching Laboratory of The University of Texas at Austin is an above-ground, fixed-core research reactor. The nuclear core, containing uranium fuel, is located at the bottom of an 8.2 meter deep wvater-filled tank surrounded by a concrete shield structure. The highly purified water in the tank serves as the reactor coolant, neutron ifloderator, and a transparent radiation shield. Visual and physical access to the core is possible at all times. The TRIGA Mark II reactor is a versatile and inherently safe research reactor conceived and developed by General Atomics to meet the requirements of education and research. The UT-TRIGA research reactor provides sufficient power and neutron flux for comprehensive and productive work in many fields including physics, chemistry, engineering, medicine, and metallurgy. The word TRIGA stands for Training. Research, Isotope production, General Atomics.

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2004 NETL Annial Report Reactor Description Reactor Operation. The UT-TRIGA research reactor can operate continuously at nonminal powers up to 1 MW, or in the pulsing mode where typical peak powers of 1500 MW can be achieved for durations of about 10 msec. The UT-TRIGA with its new digital control system provides a unique facility for performing reactor physics experiments as well as reactor operator training. The pulsing operation is particularly useful in the study of reactor kinetics and control.

Neutrons produced in the reactor core can be used in a wide variety of research applications including nuclear reaction studies, neutron scattering experiments, and nuclear analytical and irradiation services.

Special neutron facilities include a rotary specimen rack, which is located in the reactor graphite reflector, a pneumatically operated "rabbit" transfer system, which penetrates the reactor core, and a central thimble, which allows samples to be inserted into the peak flux region of the core. Cylindrical voids in the concrete shield structure, called neutron beam ports, allow neutrons to stream out away from the core. Experiments may be done inside the beam ports or outside the concrete shield in the neutron beams.

Nuclear Core. The reactor core is an assembly of about 100 fuel elements surrounded by an annular graphite neutron reflector. Each element consists of a fuel region capped at top and bottom with a graphite section, all contained within a thin-walled stainless steel tube. The filel region is a metallic alloy of low-enriclhed uranium evenly distributed in zirconium hydride (UZrH). The physical properties of the TRIGA fuel provide an inherently safe operation. Rapid power transients to high powers are automatically suppressed without using mechanical control; the reactor quickly returns to normal power levels. Pulse operation, which is a normal mode of operation, is a practical demonstration of this inherent safety feature.

Reactor Reflector. The aluminum-canned graphite neutron reflector surrounding the reactor was flooded in 2000 by the NETL staff to correct pressurization problems. Thle reflector was replaced this reporting year with slight modification.

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l Ix 2004 NETL Annual Report Reactor Control. The instrumentation for the UT-TRIGA research reactor is contained in a compact microprocessor-driven control system. This advanced system provides for flexible and efficient operation with precise power and flux control. It also allowvs permanent retention of all pertinent data. The power level of the UT-TRIGA is controlled by four control rods. Three of these rods, one regulating and two shim, are sealed stainless steel tubes containinig powdered boron carbide followed by UZrH. As these rods are withdrawn, boron (a neutron absorbcr) leaves the core and UZrH (fuel) enters the core, increasing power. The fourth control rod, the transient rod, is a solid cylinder of borated graphite followed by air, clad in aluminum, and operated by pneumatic pressure to permit pulse operation. The sudden ejection of the transiciit rod produces an immediate burst of power.

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2004 NETL Annual Report Experiment Facilities The experimental and irradiation facilities of the TRIGA Mark II reactor are extensive and versatile. Experimental tubes can easily be installed in the core region to provide facilities for high-level irradiations or small in-core experiments. Areas outside the core and reflector are available for large experiment equipment or facilities.

The reactor is equipped with a central thimble for access to the point of maximum flux in the core. The central thimble consists of an aluminum tube that fits through tile center hole of the top and bottom grid plates. Experiments with the central thimble include irradiation of small samples and the exposure of materials to a collimated beam of neutrons or gamlmnia rays.

A rotary multiple-position specimen rack located in a well in the top of the graphite reflector provides for batch production of radioisotopes and for the activation and irradiation of multiple samples. When rotated, all forty positions in the rack are exposed to neutron fluxes of the same intensity. Samples are loaded from the top of the reactor through a tube into the rotary rack using a specimen lifting device. A rack design feature provides pneumatic pressure for insertion and removal of samples from the sample rack positions.

A pneumatic transfer system permits applications with short-lived radioisotopes. Tile in-core terminus of the system is non-nally located in the outer ring of fuel element positions, a region of high neutron flux. The sample capsule (rabbit) is conveyed to a sender-receivcr station via pressure differences in the tubing system. An optional transfer box permits the sample to be sent and received from one to three different sender-receiver stations.

Special cadmium-lined facilities have been constricted that utilize an internal area of the core created by removing three fuel elements.

Beam Port Facilities Five neutron beam ports penetrate the concrete biological shield and reactor water tank at core level. These beam ports wvere designed with different characteristics to accommodate a wvide variety of experiments. Specimens may be placed inside a beam port or outside the beam port in a neutron beam from the beam port. When a beam port is not in use, special shielding reduces the radiation levels outside the concrete biological shield to safe values. This shielding consists of an inner shield plug, outer shield plug, lead-filled shutter, and circular steel cover plate.

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2004 NETL Annual Report Beam Port (BP) #1 is connected to BP #5, end to end, to form a through beam port. The through beam port penetrates the graphite reflector tangential to the reactor core, as seen in Figure 1-6. This configuration allows introduction of specimens adjacent to the reactor core to gain access to a high neutron flux, allows access from either side of the concrete biological shield, and can provide beams of thenrnal neutrons with relatively low fast-neutron and gammiia-ray contamination.

Beam Port #2 is a tangential beam port, ternminating at the outer edge of the reflector.

However, a void in the graphite reflector extends the effective source of neutrons into the reflector to provide a thermal neutron beam with minimum fast-neutron and gamima-ray backgrounds. Beam Port #2 is out of commission due to Reflector flooding.

Beam Port #3 is a radial beam port. The beam port pierces the graphite reflector and terminates at the inner edge of the reflector. This beam port permits access to a position adjacent to the reactor core, and can provide a neutron beam wvith relatively high fast-nLeutron and ganinia-ray fluxes. Beam Port #3 contains the Texas Cold Neutron Source Facility.

Beam Port #4 is a radial beam port which also terminates at the outel-edge of the reflector. A void in the graphite reflector extends the effective source of neutrons to the reactor core. This configuration is useful for neutron-beam experiments which require neutron energies highler than thermial energies. Beam Port #4 is out of commission due to Reflector flooding.

A neutron beam coming from a beam port may be modified by using collimators, moderators and neutron filters. Collimators are used to limit beam size and beam divergence.

Moderators are used to change tie energy of neutron beams (e.g., cold moderator). Filters allow neutrons in selected energy intervals to pass through while attenuating neutrons with other energies.

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2004 NETL Annual Report Table 1-1 Physical Dimensions of Standard Beam Ports Beam Port Port Diameter BP#I, BP#2, BP#4 At Core:

At Exit:

BP #3, BP#5 At Core:

At Exit:

6 in.

8 in.

15.24 cmn 20.32 cm 15.24 cm 20.32 cm 25.40 cni 40.64 cm 6 in.

8 in.

10 in.

16 in.

BP #3 BP #4 131 *a BI, #1 Figure 1-5 Beam Ports 1-11

is 2004 NETL Annual Report 1.4 Nuclear Engineering Academic Program The Nuclear Engineering Program (NE) at The University of Texas at Austin is located within the Mechanical Engineering Department. The Program's undergraduate degree is the Bachelor of Science in Mechanical Engineering, Nuclear Engineering Option. It is best described as a major in Mechanical Engineering with a minor in Nuclear Engineering. As such, all Mechanical Engineering degree requirements must be met.

The Program's graduate degrees are completely autonomous; they arc Master of Siciuce in Engineering (Concentration in Nuclear Engineering) and Doctor of Philosophy (Concentration in Nuclear Engineering). Course requirements for these degrees and the qualifying examination for the Pli.D. are separate and distinct from other areas of Mechanical Engineering. A Dissertation Proposal and Defense of Dissertation are also required for the Ph.D. degree and are acted on by a NE dissertation committee.

Of the five undergraduate Nuclear Engineering courses and the dozen graduate Nuclear1 Engineering courses, five courses make extensive use of the reactor facility. Table 1-3 lists the courses that use the reactor and its experiment facilities.

Table 1-3 Nuclear Engineering Courses Undergraduate ME 361F Instrumentation and Methods ME 361G Reactor Operations and Control ME 177K Nuclear and Radiation Engineering Concepts Graduate ME 388R.3 Kinetics and Dynamics of Nuclear Systems ME 389R. I Nuclear Engineering Laboratory MIE 389R.2 Nuclear Analytical Measurement Techniques Mvl E 397M Radioactive Waste Management ME 337D Radiation and Radiation Protection In addition to these formal classes the NETL often provides short, one day short courses or tours for Texas agencies, high schools and the Boy Scouts of America. The NETL has participated in the IAEA Fellowvship programs for over five years. Several Fellowvs and Visiting Scientists spend 3-6 months at the NETL per year.

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2004 NETL Annual Report 1.5 NETL Divisions The Nuclear Engineering Teaching Laboratory operates as a unit of the Department of Mechanical Engineering at The University of Texas. Figure 1-8 shows the responsibility line organization of the Nuclear Engineering Teaching Laboratory. The staff includes the Health Physics and Reactor Operations to support the Experimenter and Users groups and to insure compliance with all licensed activities.

The Operation and Maintenance Division (OMD) is responsible for the safe and effective operations of the TRIGA nuclear reactor. Activities of OMD include neutron and gammnla irradiation service, operator/engineering training courses, and teaching reactor short courses.

Director Labors Health Physicist l El atory ManagerL t and Research Support I Faculty and Facility Users Associatel I

Dire ctorl Administrative and Clerical Staff Reactor Supervisor Electronics Technicia Reactor Operators

- Figure 1-6 NETL Staff Organization 1-13

2004 NETL Annual Report Reactor Operations and Maintenance Tile role of these individuals is the routine maintenance and safe operation of the TRIGA Mark II Research Reactor. With the assistance of the NETL licensed operators, Health Physicists and Electronics Technician this division perforns most of the work necessary to meet the Technical Specifications of the reactor license. Personnel implement modifications to reactor systems and furnish design assistance for newv experiment systems. The reactor operators may operate standard reactor experiment facilities.

Services provided to other divisions at the laboratory include assistance in tile areas of initial experiment design, fabrication, and setup. Maintenance, repair support, and inventory control of computer, electronic, and mechanical equipment is also provided. Building systems maintenance is also coordinated by the OMD. Other activities include scheduling and coordination of facility tours.

Laboratory and Research Activities The principal objectives of the Laboratory research staff involve support of the resealich and educational missions of the university at large. Elemental measurements using instr1um11ental neutron activation analysis provide nuclear analytical support for individual projects ranging from student project support for classes to measurements for faculty research projects. Project support is in the areas of engineering, chemistry, physics, geology, biology, zoology, and other areas. Research project support includes elemental measurements for routine environmental and innovative research projects. In tie area of education, tie division, wvitl available state-of-tile-art equipment, helps stimulate the interest of students to consider studies in the areas of science and engineering. Education in tile irradiation and measurement of radioactivity is presented to college, higsh school and other student groups in class demonstrations or oil a one-on-one basis.

The neutron activation analysis technique is made available to different state agencies to assist wvith quality control of sample measurements. Analysis of samples for the presence of various elements and measurements of environmental effects assists detection of toxic elements.

Radiation measurement systems available include several high purity germilalliuli detectors with relative efficiencies ranging from 20 to 40%. The detectors are coupled to several Canberra and ORTEC PC-based systems. Two of the detectors are equipped wvith an automatic samlple changer for full-time (i.e., 24 hirs a day) utilization of the counting equip)ment. One 1-14

2004 NETL Annual Report detector operates in a Compton Gamma Ray Suppression Systemi that provides improved low background measurements. A PC based acquisition and analysis system supports the analysis of Compton Suppression spectra and short half-life nuclear reaction.

The group also manages the use of the five beam ports. Experiments at the beam ports may be permanent systems which function for periods in excess of one or two years or temporary systems. Temporary systems function once or for a few months, and generally require removal and replacement as part of the setup and shutdown process. The reactor bay contains floor space for each of the beam ports. Available beam paths -range from 6 meters (20 ft) to 12 meters (40 ft). The objectives of the research function are to apply nuclear methods at the forefront of modern technology and to investigate fundamental issues related to nuclear physics and condensed matter. Another mission of the division is to obtain new, funded research programs to promote the capabilities of the neutron beam projects division for academic, governilcmt and industrial organizations and/or groups.

The Laboratory Manager is responsible for coordinating all phases of a project, beginning with the proposal and design, proceeding to the fabrication and testing, and concluding with the operation, evaluation and dismantlement.

Projects available at NETL are the Texas Cold Neutron Source, Neutron Depth Profiling, Neutron Guide and Focusing System, Prompt Gamma Activation Analysis Neutron Radiography and Texas Intense Positron Source.

The Laboratory Management group is also responsible for radiation safety and protection of personnel at the NETL as well as the protection of the general public. The laws mandated by Federal and State government agencies are enforced at the facility through various measures. Health physics procedures have been developed that are facility-specific to ensuirc that all operations comply with the regulations. Periodic monitoring for radiation and contamination assures that the use of the reactor and radioactive nuclides is conducted safely with no hazard to personnel outside of the facility. Personnel exposures are always maintained ALARA ("as low as is reasonably achievable"). This practice is consistent with the mission of the NETL.

Collateral duties of the Health Physics group include the inventory and monitoring of hazardous materials, and environmental health.

The Laboratory and Health Physics group consists of one full time Health Physicist/Nuclear Laboratory Manager with part-time student support. The Health Physicist is functionally responsible to the Management of the NETL and the Department Chairman, but 1-15

2004 NETL Aniual Report maintains a reporting relationship to the University Radiation Safety Office. This arrangement allows the Health Physicist to operate independent of NETL operations constraints to insure that safety is not compromised. One or more part-time Undergraduate Research Assistant (URA) may assist as Health Physics Technicians. The URA reports to the Health Physicist and assists with technical tasks including periodic surveys, equipment maintenance, equipmIIenlt calibration, and record keeping.

The Laboratory Safety Group provides radiation monitoring, personnel exposure monitoring, and educational activities. Personnel for whom permanent dosimeters arc required must attend an eight hour course given by the Health Physicist. This course covers basic radiation principles including general safety practices, and facility-specific procedures and rules.

Each trainee is given a guided tour of the facility to familiarize him with emergency equipmnlet and to reinforce safety/emiergency procedures. The group supports University educational activities through assistance to student experimenters in their projects by demonstration of the proper radiation work techniques and controls. The Health Physics group participates in emergency planning between NETL and the City of Austin to provide basic response requirements and conducts off-site radiation safety training to emergency response personnel such as the Hazardous Materials Division of the Fire Department, and Emergency Medical Services crews.

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2004 NETL Annual Report Chapter 2 2-1

2004 NETL Annual Report 2.0 ANNUAL PROGRESS REPORT 2.1 Faculty, Staff, and Students Oruanization. The University administrative structure overseeing the NETL program is presented in Figure 2-1. A description follows, including titles and names of personnel, of the administration and committees that set policy important to NETL.

Radiation Safety Committee President University of Texas at Austin Executive Vice President and Provost I

Dean College of Engineering Nuclear Reactor Committee Chairman Department of Mechanical Engineering Director Nuclear Engineering Teaching Laboratory Figure 2 University Administrative Structure over NETL Administration. The University of Texas at Austin is one campus of 15 campuses of the University of Texas System. As the flagship campus, UT Austin consists of 16 separate colleges and schools. The College of Engineering consists of six engineering departments Nvith separate degree programs. NETL is one of several education and research functions within the college.

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2004 NETL Annual Report Table 2-1 and Table 2-2 list The University of Texas System Board of Regents which is the governing organization and the pertinent administrative officials of The University of Texas at Austin.

Table 2-1 The University of Texas System Board of Regents for 2003 Chairman Vice Chairman Vice Chairman Vice Chairman Executive Secretary UT System Chancellor James R. Huffines Rita C. Clements Woody L. Hunt Cyndi T. Krier Francie A. Frederick M. G. Yudof Table 2-2 The University of Texas at Austin Administration President Larry R. Faulkner Executive Vice President and Provost ad interim Dean of College of Engineering Chairman of Department of Mechanical Engineering Sheldon Ekland-Olson Benjamin Streetman Joseph J. Beaman 2-3

2004 NETL Annual Report Radiation Safety Committee.

The Radiation Safety Committee convenes to review radiological safety practices at the University during each academic term.

Tile committee comnposition is showvn in Table 2-3. Committee general responsibilities are review of activities of University research programs that utilize radiation source materials.

r Table 2-3 2003 Radiation Safety Committee Chair Member Member Memnber Member Member Ex officio member Ex officio member J.M. Sanchez G. Hoffinann S.A. Monti J. Robertus B.G. Sanders D. J. O'Kelly S.Pennington E. Janssen Nuclear Reactor Committee. The Nuclear Reactor Committee convenes to revicw tile activities related to facility operation during each quarter of the calendar year. The committee composition is shown in Table 2-4. Committee general responsibilities are reviewv of reactor operation and associated activities.

Table 2-4 Nuclear Reactor Committee Chairman Member Member Member Member Member Ex officio member Ex officio member Ex officio member Ex officio member Ex officio member K. Ball S. Biegalski R.T. Johns H. M. Liljestrand S. Landsberger S. Pennington J. Beaman R. J. Charbeneau D. J. O'Kelly M. Krause D. S. O'Kelly 2-4

S 2004 NETL Annual Report Table 2-5 NETL Personnel V.

NETL Facility Staff Director Associate Director Reactor Supervisor Laboratory and Safety Manager Research Associate (Positron)

Research Associate (NAA/Rad Effects)

Electronics Technician/Reactor Operator Reactor Operator Health Physics Technician Administrative Associate S.Landsberger D. S. O'Kelly M.G. Krause D. J O'Kelly B. Hurst S. Aghara L. Welch J. Hedlund D. Tillman J.L. Wiley NRE Faculty S. Biegalski D.E. Klein S. Landsberger 2-5

D 2004 NETL Annual Report Funding.

NETL funding is provided by state appropriations, research grants, and service activities. Research funding supplements tile base budget provided by the State and is obtained mostly through the process of competitive project proposals.

Funds from service activities supplement the base funds to allow the facility to provide quality data acquisition and analysis capabilities.

Both sources of supplemental funds, research projects and service activities, contribute to the cducation and research environment for students.

Innovations in Nuclear Infrastructure and Education (INIE). The NETL received a significant grant in 2002 in a partnership with Texas A&M University, The University of Newv Mexico and Sandia National Laboratories. This five-year grant wvill enable the facilities to acquire advanced experimental equipment and provide shared resources wvithin the so-called SoutIIwVest Consortium.

Reflector Replacenient Proiect. The NETL reactor wvas shutdowvn from late Mlarch to early J.uly to replace the reactor reflector assembly. This significant shutdown curtailed the normal reactor operational and experimental programs.

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2004 NETL Annual Report NETL/NRE Research 2004

1. Radiation shielding testing of advanced tungsten composite materials to reduce environmental hazards of lead shielding (Ecomass Techrnologies)

2. Radiation shielding tests and modeling of composite gloves for handling transuranic materials (LANL)

3.

Tensile strength degradation of composite shielding gloves from higlh alpha and neutron doses (LANL)

4. Trace impurities and iodine background levels in groundwater (Illinois Geological Survey)

5. Neutron Activation Analysis (NAA) of travertine and anthracite from Civil War-era ships for nautical archaeology.

6. NAA of plant materials and soils to detennine Arsenics and Antimony pollution levels on U.S/Mexico border (UT Pan Am)

7. Gennanium compounds irradiated to produce Arsenic products for tumor therapy for the UT Medical Branch at Dallas

8. Heavy-metal particulate pollution levels over Russian smelters (NOAA)

9. Particulate atmospheric pollution levels over Finland (U of Alaska/NOAA)

10. Prompt gamma activation analysis of carbon composite flywheels (NASA/UT)

11. Radiation damage modeling of integrated chip packaging materials (Tcxas A&M/Tcxas Instruments)

12. Prompt gamma activation analysis of hydrogen in electrochemical batteries

13. NAA of Archaeological Artifacts (UT Middle Eastern Studies) 2-7

2004 NETL Annual Report Other projects and descriptions are given below:

Projects supervised under Dr. Stephen Biegalski:

Hydrodynamic Analysis of CWS South June 2003

$45,304 Dr. Ball for STP Nuclear Power Station Texas to Aug.

Dr.

Projects 2004 Landsberger Multiple Isotope Contribution Veridian Feb. 2003

$19,077 Analysis (MICA) Software Tool to Jan.

2004 NuGET Experiment Validation Sandia Julne 2003 S40,000 Dr.

to Sept.

Landsber-er 2003 Dr. Chariton Computational Support for Safe Sandia Julne 2003

$50,000 Dr.

Operations of SNL's Nuclear to May Landsberger Reactors 2005 Development of a Prototype Design Los Alamos Julne 2003 S222,4S6 Dr.

for an Automated System Able to to Feb.

Landsbcr-cr do Required Chemistry and 2005 Preparation of a Sample Suitable for Analysis Identification of Isotopes for Lawrence Jan. 2004 S20,965 Forensic Studies of Nuclear Fuel Livermore to Dec.

Activities with ANIS 2005 Investigation of Radiative Behavior Sandia Jan. 2005

$97,310 Dr. Howell of Spent Fuel to Jun.

2_005 Development of Portable PGAA Brookhaven Jun. 2004 S 14,609 System for Soil Analysis to Aug.

2004 Development of Portable PGAA Brookhaven Dec. 2004

$43,429 System for Soil Analysis (Rev. I) to May 2005 Computational Support for Safe Sandia Julne 2003

$53,070 Operations of SNL's Nuclear to May Reactors (Rev. 3) 2005 Threat Characterization ORNL Oct. 2003 S50,000 Dr.

Department of Homeland Security to June Landsberier Project 2005 Software Package for Synthesis of Los Alamos Jan. 2005

$69,223 Germaniumn Detector Efficiency to Jan.

Curves 2006 2-S

2004 NETL Annual Report Publications and Presentations Peer Reviewed Journal Articles For 2004

1. 0. Doron, S. R. Biegalski, S. O'Kelly, B. J. Hurst, "Development of a Transport System for the Copper Source of the Texas Intense Positron Source Facility," submitted for publication in Nuclear Instrunients and Methodls: B, 2004.

2. B. J. Vieira and S. R. Biegalski, "Atmospheric Trace Metal Characterization in Industrial Area of Lisbon, Portugal," submitted for publication in the Journal of Ra(lioanalpuicil anid Nuclear Chelnisto,, 2004.

3. S.R. BiegalskiT.C. Green, E. Alvarez, S. Aghara, "Sources of Background at Thle University of Texas PGAA Facility," submitted for publication in the Journal of Ralioanalytical anld Nuclear Chenzistry, 2004.

4. KR. Jackinan and S.R. Biegalski, "Monte Carlo Genlerated Spectra for QA/QC of Autontated NAA Routine, "submnittedfor publication in the Journal of Radioanalytical and Nuclear Chemistry, 2004.

5. S. R. Biegalski, T. C. Green, G. A. Sayre, W. C. Charlton, D. J. Dorsey, S. Landsbcrger, "Flux Weighted Efficiency Calibration of The University of Texas at Austin PGAA Facility," accepted for publication in the Journal of Radioanalytical ncfid Nuclear C'hemnistry, 2004.

6. S. R. Biegalski and 0. Doron "Positron Research Review," Journal of Raclioatin'lylical and Nuclear Chemnist',, Vol. 262, No. 3, pp. 789-796, 2004.

7. S. R. Biegalski and P. Hopke, "Total Potential Source Contribution Function Analysis of Trace Elements Found in Aerosol Samples Collected near Lake Huron," Envirownellial Scienice and Technology, Vol. 38, 4276-4284, 2004.

8. K. M. F. Biegalski, S. Biegalski, "Deconvolution of three-dimensional beta-gaminma coincidence spectra from xenon sampling and measurement units,".Iourlnal of Raclioanalytical and Nuclear Czenistry, 263(1), 25 9-265, 2005.

9. S. Biegalski, T. Vilarel, "Correlations Between Atmospheric Aerosol Trace Element Concentrations and Red Tide at Port Aransas, TX On the Gulf of Mexico," Journal of Radioanalytical and Nuclear Chenmistry, 263(3), 767-772, 2005.

10. S. Landsberger, S. Biegalski, D.J. O'Kelly, S. Basunia "Use of Coincident and Non-Coincident Gamma Rays in Compton Suppression Neutron Activation Analysis," Journal of Raclioanalytical and Nuclear Cheinistny, 263(3) pp. 817-821, 2005.

11.

2-9

2004 NETL Annual Report Peer Reviewved Conference Proceedings during Period of Perfornance

1. K.R. Jackman and S.R. Biegalski, "Simulated Spectra for QA/QC of Spectral Analysis Software" Transactions of thie American: Nuclear Society, Vol. 91., 2004.

2. S. Biegalski and S. M. Whitney "Isotopic Ratios for Nuclear Fuel Cycle Analysis Applicable to AMS" Tr(insactions of t/he merican Nuclear Society, Vol. 91., 2004.

3. S. Biegalski and S. Landsberger " Laying tile Foundation for Learning Beyond tile Baccalaureate Degree," Transactions of The Imerican Nuclear Socie', Vol. 91., 2004.

4. W.S. Charlton, G. Sayre, S. Biegalski, T. Green, and S. Landsberger, "Comparison of Measured and Calculated Prompt Gamma Ray Yields and Spectra for Verification of MCNP5"Proceedings for the American Nuclear Society 14th Pacific Basin Nuclear Conference, Marcl,2004.

5. Chariton, W. S., S. Biegalski, T. Green, G. Sayre, and S. Landsbergcr, "'Comparison ol' Measured and Calculated Prompt Gammu-a-Ray Yields and Spectra flor Verification of 1ICNP5", 14th Pacific Basin Nuclear Conference held in Honolulu, Hlawaii lIoni March 21-25, 2004.

6. Landsberger, S., L. Katz and D. J. O'Kelly, "Graduate Education in Nuclear and Radiocilemistry at the University of Texas at Austin," Trans. ANS, 91. 801 -803 (2004).

7. Pratt, V. S., K.M. Foltz-Biegalski, T. Pintel, E. Strassberg, and S. Landsberger "Development of Nonproliferation Assessment Tool Software" Trans. ANS, 91

)

309-3 10 (2004).

Talks

1. S. Biegalski, "Thle Future of Nuclear Power," invited luncheon speaker, Lions Club1 ol Austin, Autiust 5, 2004.

2. S. Biegalski, "Activation Analysis at The University of Texas at Austin," invited semilnar at CENESTEN, Rabat, Morocco, June 24, 2004.

3. S.R. Biegalski, T.C. Green, E. Alvarez, S. Aghara, " Sources of Background at The University of Texas PGAA Facility," presentation at tile Modern Trends in Activation Analysis (MTAA) conference, Guilford, England, June 21-24, 2004.

4. K. Jackman and S.R Biegalski, " Monte Carlo Generated Spectra for QA/QC of Automated NAA Routine "presentation at the Moderm Trends in Activation Analysis (NITAA) conference, Guilford, England, Junc 21-24, 2004.

5. S. Biegalski and S. Whitney, "Isotopic Ratios for Nuclear Fuel Cycle Analysis Applicable to AMS," invited seminar by CAMS group at LLNL, Livermore, CA,.uLinc 4, 2004.

2-10

2004 NETL Annual Report

6. S. Biegalski, E. Alvarez, T. Green, S. Aghara, S. Landsberger, "Detection Limits Assessment at the University of Texas PGAA Facility" 227th ACS National Meeting, Anaheim, CA, March 28-April 1, 2004.

7. Defee, T., H. Wheat and S. Landsberger, "Corrosion for Welded Stainless Steel", 2 0 5h' Electrochemical Society Meeting, May 9-14, San Antonio, 2004.

8. Landsberger, S., "Radiochemistry Training of Graduate Students in a Nuclear and Radiation Engineering Program", 2 27th ACS National Meeting, March 28-April 1, 2004, Anaheim, California, 2004.

9.

Landsberger, S. Biegalski, S. R., S.K. Aghara, T. Green and E. Alvarez, "Detection Limits Improvements at the University of Texas PGAA Facility", 227"' ACS National Meeting, March 28-April 1, 2004, Anaheim, California, 2004.

10. Landsberger, S. L. Katz, S. O'Kelly, and A. Plionis, "Development of Nuclear and Radiocheemistry Laboratories" American Association of Engineering Education, 2004 Annual Conference, Salt Lake City, June 20 - June 24, Utah (2004).

11. Plionis, A., D. Haas, S. Landsberger, G. Brooks, "Creating a Rapid, Reproducible, Automated Electrodeposition Procedure for Trace Actinide Analysis in Environmental Samples" 5 0th Conference on Bioassay, Analytical and Environmental Radiochlemistry",

Cincinnati, Ohio, October 31-November 1, 2004.

2-11

2004 NETL Annual Report Education and Training Activities Tours and special projects are available to promote public awareness of nuclear energy issues. Tours of the NETL facility are routine activities of NETL staff and students. A typical tour is a general presentation for high school and civic organizations. Other tours given special consideration are demonstrations for interest groups such as physics, chcmistry and(I science groups.

A total of 3221 visitors wvere given access to the facility during the reporting period. Thle total includes tour groups, official visitors, and facility maintenance personnel. Tours for 15 groups with an average 20 persons/group were taken through the facility during thle reCpOr-till" period. The NETL typically hosts three international visitors on IAEA (International Atomic Energy Agency) Fellowships a year.

2-12

2004 NETL Annual Report 2.3 Research Acitivities Beam Port 2 Area Neutron Depth Profiling and Prompt Gamma Activation System Beam Port 2 is a tangential beam and this results in a "softer" energy neutron beam because the beam is resulting only from scattered reactor neutrons. The thermal neutron energies have been optimized by installing a sapphire neutron energy filter in the beam. The beam port has been out of service'since the reflector flooded in the year 2000. Tlhc beam port is nowv returned to operation with the replacement of the reactor reflector this year.

Current projects in development include a reconstruction of the previous neutron depth profiling system and a thernmal prompt gamma activation analysis system as an installed co-experiment sharing the neutron beam.

Texas Cold Neutron Source The Texas Cold Neutron Source (TCNS) is located in one of the radial beam ports (BP

1. 3) and consists of a cold source system and a neutron guide system. The facility was originally constnrcted using Texas Advance Research Program funding but later improvements were funded by the Department of Energy or using internal NETL sources.

The cold source system includes a cooled moderator, a heat pipe, a cryogenic refrigerator, a vacuum jacket, and connecting lines. Eighty milliliters of mesitylene moderator is maintained by the cold source system at -36 K in a chamber Xwithin the reactor graphite reflector.

Mesitylene, 1,3,5-trimethlylbenzene, was selected for the cold moderator because it has been shown to be an effective and safe cold moderator. The moderator chamber for the mesitylecne is a 7.5 cm diameter right-circular cylinder 2.0 cm thick.

The neon heat pipe (properly called thernrosyphon) is a 3-in long aluminum tube which is used for cooling the moderator chamber.

The heat pipe contains neon as the working fluid that evaporates at the moderator chamber and condenses at the cold head.

Cold neutrons coming from the moderator chamber are transported by a 2-m-long neutron guide inside the beam port and a 4-m-long neutron guide (two 2-m sections) outside the beam port. Both the internal neutron guide and the external neutron guide are curved wvith a radius of curvature equal to 300 m. To block line-of-sight radiation streaming in the guides, the cross-sectional area of the guides is separated into three channels by 1-mm-thick vertical walls. All reflecting surfaces are coated with Ni-58.

The TCNS system provides a low background subthennal neutron beam for neutron reaction and scattering research. Installation and testing of the external curved neutron guides, 2-13

2004 NETL Annual Report the shielding structure, neutron focusing and a Prompt Gammnna Activation Analysis facility are completed. The only other operating reactor cold neutron source in the United States is at the National Institute of Standards and Technology and uses liquid hydrogen. At least four major centers for cold neutron research exist in Europe, with another two in Japan.

The TCNS was upgraded this past year with a larger cryorefrigerator, cold head and instrumentation system/ The larger refrigerator (22 watts from 4 watts) should cool the thermosyphon system faster and produce a more rapid cooldown and better thermal control at higher reactor powers. The automatic control system (shown below) will provide alarms and automatic shutdowns if normal parameters are exceeded.

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Figure 2-2 TCNS Control and Instrumentation Console Prompt Gaminia Activation Analysis Facilitv The UT-PGAA facility utilizes tile focused cold-neutron beam from, tile Texas Cold Neutron Source.

The PGAA sample is located at tile focal point of the converging guide focusing system. The use of a guided focused cold-neutron beam provides a higpher capture reaction rate and a lower background at the sample-detector area as compared to other facilities using filtered thennal neutron beams.

2-14

2004 NETL Annual Report The UT-PGAA facility lhas been designed taking into account the advantage of the low background.

The following criteria have been used during the design: a) The structure and shielding materials for the UT-PGAA facility were chosen to minimize the background contribution for elements to be detected in the samples to be studied. b) The sample handling system was designed to be versatile to permit the study of a wide range of samples with quick and reproducible sample positioning with a minimum of material close to the samples.

The shielding was improved to reduce the hydrogen capture gamma ray background A 25% efficient n-type gamma-ray detector in a configuration wvitlh an offset-port dewar wvas purchased to be used at the UT-PGAA facility in the early 1990's. The detector was selected in order to incorporate a Compton suppression system at a later date. Recent vacuum fiilures required repeated repairs to this detector. Thus, a new 66% p-type detector was purchased as a replacement. This system could be configured for Compton suppression if required. A gammina-spectrum analysis system with 16,000 channels is used for data acquisition and processing.

The applications of the UT-PGAA will include: i) determination of B and Gd concentration in biological samples which are used for Neutron Capture Therapy studies, ii) determination of H and B impurity levels in metals, alloys, and semiconductor. iii) multielemental analysis of geological, archeological, and environmental samples for determination of major components such as Al, S, K, Ca, Ti. and Fe, and minor or trace elements such as H, B, V, Mn, Co, Cd, Nd, Sm, and Gd, and iv) multielemental analysis of biological samples for the major and minor elements H, C, N, Na, P, S, Cl, and K, and trace elements like B and Cd.

1.E+01 I

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s Sr

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1000 2000 3000 4000 5000 6000 7000 8000 Energy [keV]

Figure 2-3 PGAA Spectra of Carbon Composite Flywhleel 2-15

2004 NETL Annual Report Neutron Radiography Facility The Neutron Radiography Facility at Beam Port 5 had not been significantly modificd in tile past 5 years. This changed in 2003 as Dr. Stephan Biegalski began to use the cxisting radiography camera, upgraded the image capture boards and PC image analysis softwvarc and purchased a much improved neutron imaging system from NOVA Scientific based onl Mlicro-Channel Plate technology. Thle system is still under initial testing but expected resolutions are on the order of 50 microns.

Figture 2-4 MCP Neutron Imaging Detector (NOVA Scientific)

Texas Intense Positron Souice A reactor-based slowv positron beam facility is being fabricated at the Nuclear Engineering Teaching Laboratory (NETL). Thle facility (Texas Intense Positron Source ) will be one of a few reactor-based slowv positron beams in the world when completed. The Texas Intense Positron Source consists of a copper source, a source transport system, a combined positron moderator/remoderator assembly, a positron beam line and a sample chamber.

I-gh-,l energy positrons from the source wvill be slowved dowvn to a fewv eV by a tungsten foil moderatorI that also acts as a reinoderator to reduce the beam size to enable beam transport to a target lor experimentation.

The beam wvill be electrostatically guided and will deliver about 108 positrons/sec in tile energy range of 0 - 50 keV.

Reactor-based positron beams utilizing a copper source have been implemented at Delft University of Technology, The Netherlands. There are several differences betw'een TIPS and these reactor based positron beams. The source/moderator array of the Delft positron beamil is located inside one of the neutron beam ports of their reactor and tile positron beam is transported out of the reactor and then remoderated before it enters into an experimental chamiber.

2-16

2004 NETL Annual Report Based on general experience on reactor based positron s6urces, we have decided that the moderator/remoderator assembly and the positron beam optics should be entirely outside the reactor biological shield. A source transport system will be placed in a 4 meter aluminum systcm for low activation that will be inserted into one of the neutron beam ports of the NETL I-MW TRIGA Mark II research reactor. The transport system will be used to move the source to the irradiation location and Out of the biological shield. The source will be moved away from the neutron beam line to an ultra high vacuum (at around 10-10 torr) chamber, wvhere the moderator assembly is located. The transporter, load-lock transfer sytem and ultra high vacuum systems will be separated by gate valves.

The copper source of TIPS will be irradiated across from the core in the graphite reflector, in the middle section of the through port (BPl-BP5). The isotope 6 4CU foriccl by neutron capture in 63Cu (69 % in natural copper) has a half life of 12.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />, and the branching ratio for b + emission is 19 %. Our current source design consists of copper clectroplated thinly onto a carbon backing. This source minimizes the unnecessary activation products because the positrons produced are relatively near the surface of the copper and may be ejected for moderation and beam focus.

Preliminary designs and construction of the source transport system are completed. The source transport system wvill use carbon fiber cord to move a sample carriage out near the reactor and back with minimal activation of transport components.

The positron source may be transferred with remote tools into the system Load-Lock device.

Cu-64 Load Locking System (top view)

F Radiolsotope Prep. C'haiber

.Lz F

Load-Lock Tranporter Source Chamber Figure 2-5 TIPS Load-Lock Source Transfer System 2-17

2004 NETL Annual Report The Load-Lock will maintain the primary source chamber at ultra-high vacuum while permitting source transfer at atmospheric pressures.

The design and construction of the copper source, moderator assembly, and the positron beam optics are completed and testing of these components are currently in progress. The high-intensity loxv-energy positron beam of TIPS will be applied to defect characterization of metals, semiconductors, and polymers. The first planned experimental use will be to cvaluate new low density, high k insulators for thle semiconductor industry and industrial coatings.

TIPS Positron Annlihilation Spectrometer (IAS)

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Figure 2-6 TIPS Positron Detection System 2-18

2004 NETL Annual Report Other Proiects at the NETL Neutrino Mass Experiment The UT Physics Department has obtained an NSF grant to investigate the theoretical mass of the neutrino. The neutrino is classically considered to be a massless particle but some theories dispute this and leave the potential for a mass (although very small). The NETL has a large shielded room that is beifig refurbished to house this five-year experiment.

Radiochemistry Laboratorv The Department of Energy provided initial funding to equip and develop a graduate-level radiochemistry laboratory to encourage students to enter this field and replace retiring radio chemists in the DOE laboratories.

Dr. Sheldon Landsberger and Dr. Donna O'Kelly have prepared several laboratories and several students are now working on projects directly sponsored by Los Alamos National Laboratory and Sandia National Laboratories. The laboratory consist of state-of-the-art Alpha Spectroscopy Systems, Liquid Scintillation Counting System and several High Resolution Gamma Counting Systems.

e 2I E

Figure 2-7, Room 3.106 Radiocliemistry Laboratory 2-19

2004 NETL Annual Report 2-20

2004 NETL Annual Report Chapter 3 r

3-1

2004 NETL Annual Report 3.0 FACILITY OPEIRATING SUMMARIES 3.1 Operating Experience The UT-TRIGA reactor operated for 113 days in 2004. The reactor produced a total energy output of 267 MW-hrs during this period. The burnup per year in the twelve years of operation is showvn in Figure 3-1.

Several experiments required 50% power or less so the burnup is less then what it wvould have been if tile reactor wvere operating at full plower. This most significant factor in reactor operations wvas an effective 5 month reactor shutdoWvn lor tile replacement of the reflector.

Observing the graph below indicates that the average reactor operating schedule in the last 5 years (6 month shutdowvn in 2000 and 5 mn1110th shutdown1 in 2004) is substantially increased from the early years of operation.

250.00 0

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200.00 150.00 100.00 50.00 0.00 1996 1998 2000 Year of Operation 35.00 30.00 (A

,, 25.00 a_ 20.00 ea 3 15.00 C3 1000 5.00 0.00 I' 0"Io1 --

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le 1992 1994 1996 1998 2000 2002 Year of Operation Figure 3-1 History of Reactor Operations 3-2 2004

2004 NETL Annual Report 3.2 Reactor Shutdowns The reactor safety system classifies protective action trips as one of three types, a limiting safety system (LSSS) trip, a limiting condition for operation (LCO) trip or a trip of the SCRAM manual switch. In the event the switch is used for a nonral reactor shutdown, the operation is not considered a protective action shutdown. The following definitions in Table 3-1 classify the types of protective actions recorded.

Table 3-1 Protective Action Definitions Protective Action Description Safety System Setting LS SS Condition for Operation LCO - (analog detection)

Setpoint corresponds to detection of limiting safety system setting.

Examples:

fuel temperature percent power Hardware action detects inoperable conditions within a safety channel or the instrument control and safety system.

Examples:

pool water level detector high voltage external circuit trips Software action detects inoperable conditions within a program function of the instrument control and safety system.

Examples:

watchdog timers program database errors Operator emergency shutdown Condition for Operation LCO - (digital detection)

Manual Switch (protective action)

Manual Swvitclh (intentional operation)

Operator routine shutdown There were 8 safety system protective unscheduled shutdowns in 2004. Twvo of these were thennocouple spurious trips on Fuel Temperature Channel 1. This trip seems to be only related to that circuit but attempts to recreate the failure have not been successful. Twvo scrams 3-3

2004 NETL Aniual Report wvere caused by operator error wvhile operating too close to a high powver scram sctpOint. Two other scrams were a result of instrumentation fluctuations at high power. These scrams wvill be corrected by increasing the licensed high power limits in the near future.

All scrams wcre reviewed by the Senior Reactor Operator prior to returning the reactor to normal operations.

2004 SCRAM Log Date Time Type Comments 2112/2004 9:35 SCRAM FT1 Thermocouple Intermittent Failure.

7/27/2004 15:00 SCRAM NM% or HV SCRAM @ 1 kW during Rod Cals 8/11/2004 13:02 SCRAM %PWR2 (NP)

Manual Mode fluctuations 83-105%; Hx on, Stirrer on. Detector adjustments.

9/22/2004 10:07 SCRAM %PWR2 (NP)

Operator Error: Switched to Auto Mode too soon to reach full power.

9/22/2004 10:20 SCRAM %PWR2 (NP)

Operator Error: Heavy finger while banking rods at full power.

10/25/2004 11:21 SCRAM FT1 Thermocouple Intermittent Failure.

11/1/2004 17:03 SCRAM %PWR2 (NP)

Power fluctuations while banking rods at full power.

11/22/2004 11:40 SCRAM NM% or HV Spurious trip at full power: Rods banked, no rod manipulations, auto mode.

3-4

2004 NETL Annual Report 3.3 Utilization Utilization was reduced for this reporting year due to a reactor shutdown to replace the reflector. However, this repair will place two beam ports back in operation and significantly increase the available neutron flux in all experiment locations. There were a significant number of sample irradiated and hours of operation during the reporting period because the NETL staff completed several projects early to avoid the pending reactor shutdown. Two operators received new licenses during the year. The NETL staff continues to perform activation and analysis services as a public service and in support of the overall UT mission. Neutron activation analysis accounted for much of the reactor utilization time with teaching labs and beam port research projects making up the remainder. The Prompt Gamma Analysis System was in use for m1LIuCh of the year for student projects and a project under the DOE Nuclear Engineering Education and Research (NEER) program.

3.4 Routine Scheduled Mainteniance All surveillances and scheduled maintenance xvere completed during the reporting year.

Some maintenance wvas scheduled to occur after the Reflector Replacement because the reactor xvas shutdown for 4 months.

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

3.5 Facility Changes and Corrective Maintenance TRIGA Reflector Replacement The TRIGA Reflector wvas flooded in the year 2000 to prevent further pressurization from gals buildup. The cause of the gas buildup is still being investigated. Funds were received through the DOE University Reactor Instrumentation Program to replace the Reflector. General Atomics agreed to wvaive some normal fees at the company was selected to build the replacement. Several design changes xvere approved by the University Nuclear Reactor Committee to the new Reflector. All changes were determined to not affect the original, as-designed replacement requirements. The following arc specific descriptions of Reflector changes and testing for the new Reflector Assembly 3-5

2004 NETL Annual Report Aluminum cans inserted into graphite voids of Beam Port 2 and Beam Port 4.

The flooding of the original Reflector caused tile large graphite void flux traps in BP 2 and 4 to flood, effectively shutting off the neutron beams. Two alminium void cans were inserted during construction of the newv Reflector to plrevent this in the event the Reflector were to ever fail again. These voids wecre helium leak tested prior to insertion into tile graphite.

2.

The upper grid plate wvas modified slightly to allowv more experiment flexibility.

Thle center 6-element cutout remains but an identical cutout was transposed to tile cdge of the core to minimize reactor perturbations wvhen used. The th1rece element cutouts wvcre also moved to reduce the flux perturbation and improve tile experimental flexibility. The new grid plate is shown below.

rI Figure 3.1 New Reactor Grid Plate

3.

Higher level Quality Assurance wvas performecd during the Reflector manufacturing. The NETL Reactor Supervisor traveled to San Diego to obscerve thle final wvelding and QA testing. GA specifications require that thle leak testing wvould be perfonned with only two psia helium pressure inside the reflector. Thie relatively high helium background in the wvelding facility required a shroud to be used to isolate thle Reflector. Additionally, anl NETL requested deviation of the testing procedure was aplproved. T'his required the actual gas pressure to be as high as thle delta-pressure under used which wvas 1 2 lpsia. A weld wvas found1L to be 3-6

2004 NETL Annual Report defective at this higher pressure. Hence, the requested higher testing pressures revealed a weld failure that would been discovered only after the newv Reflector failed under testing.

The Reflector was replaced without draining the reactor pool. This required the through tube of Beam Port 1 & 5 be plugged during the Reflector removal. Thle bellows assemblies were pressure tested to 5 psia following installation of the new Reflector. Tile reactor core wvas reloaded in July and fully tested and recalibrated. Tile TRIGA reactor was released for unrestricted operations on July 30, 2004.

Receipt of Reactor Fuel In August, the NETL received previously irradiated TRIGA fuel from the University of Illinois. Additionally, the facility received an essentially unused reactor core from the Manhattan College. This fuel will be used to eventually establish a new reactor core or subcritical system at the NETL. NRC License 50-129 and 70-180 wvcre changed to accommodate higher quantities of SNM and to receive irradiated fuels.

3.6 Laboratory Inspections Inspections of laboratory operations are conducted by university and licensing agency personnel.

Twvo committees, a Radiation Safety Committee and a Nuclear Reactor Committee, review operations of the NETL facility.

The Nuclear Reactor Committee convened at the times listed in Table 3-6.

Table 3-6 Committee Meetings Nuclear Reactor Committee First Quarter No meeting Second Quarter March 10, 2004 Third Quarter September 15, 2004 Fourth Quarter No meeting 3-7

2004 NETL Annual Report Inspections by licensing agencies include federal license activities by tile U. S. Nuclear Regulatory Commission (NRC), Nuclear Reactor Regulation Branch (NRR), and state license activities by the Texas Department of Health (TDH) Bureau of Radiation Control (BRC). NRC and TDH inspections were held at the times presented in Table 3-7. Thle NRC visited tile NETL four times in 2004. The inspections were: two normial facility inspections, one inspection of the reflector replacement and one observation of the annual cmergency drill. No violations were noted.

Table 3-7 Dates of License Inspections License Dates R-129 February, May, October, November SNM-ISO None L00485(48) iMarch 8, 2004 Routine inspections by tile Office of Environmental Health and Safcty (OEIIS) rot compliance with university safety niles and procedures are conducted at varying intervals throughout the year. In respo0lse to safety concerns at other sites on the main campus, several additional OEHS inspections have been made. Inspections cover fire, chemical, and radiological hazards. No significant safety problems were found at NETL, which reflects favorably on the positive safety culture for all hazard classes at the NETL. Safety concerns included such items as storage of comrbustibles, compressed gases, and fire extinguisher access.

3-8

2004 NETL Annual Report 3.7 Radiation Exposures A radiation protection program for the NETL facility provides monitoring for personnel radiation exposure, surveys of radiation areas and contamination areas, and measurements of radioactive effluents. Radiation exposures for personnel, building work areas and areas of the NETL site are showvn in the following tables. Site area measurements include exterior points adjacent to the building and exterior points awvay from the building.

Table 3-8 summarizes NETL personnel dose exposure data for the calendar year. Reactor fuel movement from the reactor pool to storage pits and back to the pool resulted in a higher total personnel dose. Diver dosimetry for the Reflector replacement is not included in Table 3-8 but shown else where. Figure 3-3 locates the building internal and external dosimetry sites. Dots locate fixed monitoring points within the building. Numbers identify the immediate site area radiation measurement points exterior to the building. These measurements do not indicate any measurable dose from work within the NETL building. Table 3-9 and Table 3-10 summarize doses recorded in facility work areas and the site areas. Table 3-1 1 contains a list of the basic requirements and frequencies of measurements.

Additional measurement data is available from the State of Texas Department of Health.

The state agency records environmental radiological exposures at five sites in the vicinity of the research reactor site. Samples are also taken for analysis of soil, vegetation, and sanitary waste effluents.

3-9

2004 NETL Annual Report Table 3-8 Annual Summary of Personnel Radiation Doses Received Within the NETL Facility for 2003 Personnel Group Average Annual Dose (mrem)(1)

Greatest Individual Dose (mrem)(1)

Total Person mrem per Group (1)

Whole Body DDE(2)

Lens of Eye LDE(3)

Extremities Whole Body Lens of SDE(4)

DDE(2)

Eye LDE(3)

Extremities Whole SDE(4)

Body DDE(2)

Lens of Eye LDE(3)

Extremities SDE(4)

(1) 'M" indicates that each of the beta-gamma or neutron dosimeters during the reporting period was less than the vendor's minimum measurable quantity of 10 mrem for x and gamma rays and thermal neutrons, 40 mrem for energetic betas, and 20 mrem for fast neutrons.

"N/A" indicates that there was no extremity monitoring conducted or required for the group (2), (3), (4) Deep, Eye, and Shallow Dose Equivalents (DDE, LDE, and SDE respectively). DDE applies to external whole-body exposure and is the dose equivalent at a tissue depth of 1 cm (1000 mg/cm2 ). LDE applies to the external exposure of the eye lens and is taken as the dose equivalent at a tissue depth of 0.3 cm (300mg/cm2). SDE applies to skin or extremity exposure, and is the dose equivalent at a tissue depth of 0.007 cm (7mg/cm2) averaged over an area of 1 cm.

(5) PD's are pocket ion chambers issued to persons who enter radioactive materials / restricted areas for periods of short duration, i.e., a few hours or days.

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a--

2004 NETL Annual Report ACCESS ROAD I

PARKING a

3 0

6 4S 4

0 0 NETL 0

5 PARK I NG 1 Sidewalk, NETL facility front entrance 2 Reactor bay exterior wall, east 3 Reactor bay exterior wall, west 4 VETL power transformer 5 METL service door 6 NETL roof stack Indicates location of dosimetry within the building SERVICE DRIVE Figure 3-3 Environmental TLD Locations 3-11

a 2004 NETL Annual Report Table 3-9 Total Dose Equivalent Recorded on Area Dosimeters Located Within the NETL Facility 2003 Location in Reactor Facility Monitor ID Total Dose (mrem) n Shallow (1,2) bq,x (4)

Deep (3)

Reactor Bay, North Wall 00277 1931 1918 1913 Reactor Bay, East Wall 00278 282 285 286 Reactor Bay, West Wall 00279 17831 18143 19605 Water Treatment Room 00280 26145 26228 26054 Shield Area, Room 1.102 00281 2

3 3

Sample Processing, Room 3.102 00173 8

8 8

Gamma Spectroscopy Lab, 3.112 00174 M

M M

Radiation Experiment Lab, 3.106 00175 1

1 1

Reception Area, 2.102 00176 M

M M

Office, Room 3.104 00222 8

9 7

(1) The total recorded dose equivalent values reported in mrem do not include natural background contribution and reflect the summation of the results of 12 monthly beta, x-and gamma ray or neutron dosimeters for each location. A total dose equivalent of "M" indicates that each of the dosimeters during the period was below the vendor's minimum measureable quantity of 10 mrem for x and gamma rays, 40 mrem for energetic betas, 20 mrem for fast neutrons, and 10 mrem for thermal neutron. "N/A" indicates that there was no neutron monitor at that location.

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

(3) Deep indicates Deep Dose Equivalent, which applies to external whole-body exposure and is the dose equivalent at a tissue depth of 1 cm.

(4) Shallow indicates Shallow Dose Equivalent, and applies to external exposure of the skin or an extremity, and is taken as the dose equivalent at a tissue depth of 0.007 cm averaged over an area of 1 square cm.

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2004 NETL Annual Report Table 3-10 Total Dose Equivalent Recorded on TLD Environmental Monitors Around the NETL Reactor Facility 2003 Monitor L.D Reactor Facility Location Total Recorded Dose Equivalent (1) (mrem) 00156 Sidewalk, NETL Front Entrance M

00157 NETL Power transformer M

00158 NETL Roof stack M

00159 Reactor bay exterior wall, East M

00160 Reactor bay exterior wall, West M

00161 NETL Service Door M

(1) The total recorded dose equivalent values reported in mrem do not include natural background contribution and reflect the summation of the results of 12 monthly beta. x-and gamma ray or neutron dosimeters for each location. A total dose equivalent of "M' Indicates that each of the dosimeters during the period was below the vendor's minimum measureable quantity of 10 mrem for x and gamma rays, 40 mrem for energetic betas, 20 mrem for fast neutrons, and 10 mrem for thermal neutron.

(2) X or gamma ray exposure. May be followed by an 'H' for energies greater than 250 keV effective or 'L' for energies less than 100 keV effective.

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2004 NETL Annual Report Table 3-11 Radiation Protection Program Requirements and Frequencies FreqCuencv 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 root Exchange personnel dosimeters and interior area monitoring dosimeters.

Review dosimetry reports.

Response check emergency locker portable radiation measuring equipment.

Review Radiation Work Permits.

Response check of the argon monitor.

Response check hand and foot monitor.

Conduct 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 and provide health physics coverage for maintenance operations.

Conduct orientations and training.

Quarterly Exchange TLD 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 [ IV 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, and area radiation 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 3-14

2004 NETL Annual Report 3.8 Radiation Surveys Radiation surveys of NETL work areas are shown in Table 3-12. Surveys with portable instruments and measurements of radioactive contamination are routine. Supplemental measurements are also made any time unusual conditions occur. Values in the table represent the result of routine measurements. Environmental monitoring at sample sites exterior to the building are generally done at random times or as a case by case evaluation.

Table 3-12 Annual Summary of Radiation and Contamination Levels Within the NETL Reactor Facility 2003 Accessible Location Area Radiation Levels (mrem/hr)

Contamination Levels (dpm/1 1 sq cm)

Avg.(1)

Max. (1)

Avg.

Max.

TRIGA Reactor Bay:

Reactor Bay North

<0.1 2

MDA MDA Reactor Bay South 0.15 15 (3)

MDA MDA Reactor Bay East

<0.1 6

MDA MDA Reactor Bay West 3.5 10 MDA MDA Reactor Pool Deck (3rd Floor)

<0.1 15 MDA MDA NETL Facility:

NAA Sample Processing (Rm 3.102)

<0.1 3

MDA MDA NAA Sample Counting (Rm 3.112)

<0.1 0.13 MDA MDA Health Physics Laboratory

<0.1 0.9 MDA MDA NAA Laboratory (Rm 3.106)

<0.1 0.4 MDA MDA (1)Measurements made with Victoreen 450B andlor Bicron Microrem portables survey meters in areas readily accessible to personnel.

(2)MDA for the G-5000 low level alpha-beta radiation counting system is 2.49 dpm/1OOcm 2 beta, and

.58 dpm/l100cm 2 alpha. Calculation of MDA based on NCRP Report #58.

(3)Water Treatment room at Ion exchanger.

3-15

2004 NETL Annual Report Radiation Exposure during Reflector Replacement Over several years, the NETL received incremental funding from the Department of Energy to replace the reflector and return the TRIGA reactor to full capability.

In order to minimize the time thle reactor needed to be shutdowvn and the impact to the educational and research mission, the NETL staff chose to perform the vork with the 10,000 gallon pool full and thus minimize the necessary irradiated component decay time. The facility had operated 100 MW-days since March 1992 with 80% of those hours being in the last 5 years. Although th]e neutron flux produced near a 1.1 Mw research reactor is relatively low (2E12 n/cm-sec), tile activation of reactor components represented a significant hazard.

The primary reactor components are constructed from 6061 aluminum wvith all fasteners fabricated friom 304 stainless steel.

Dose rate measurements from a similar reactor (USGS I Mw) in 1l989 indicated there would be significant dose rates possible (5 to 100 RMir) even followving a six mionths reactor shutdown period for decay. Calculated dose rates wvere unreliable due to the ranlge of reactor powver history and neutron flux profiles near tile core. Measured dose rates coul.d not he taken until immediately prior to commrencing reactor maintenance (following fucl removal) due tile high background radiation levels but when measurements wvere taken afler one month of tile two monith decay period thle measuremenits indicated peak contact dose rates of 20 R/hr oni the stainless steel hardwvare and 3 R/hr general area wVithin 30 cmi of the alumin11umil reflectolr.

A team of four divers from thle UT Applied Research Laboratories (ARL) was trained to performi these repairs by tile NETL staff and the UT Radiation Safety Office three weeks prior to the start of thle repairs. The UT ARL perfom-ms underwater research throughout thle world aind the divers are highly qualified and experience research divers but had no experience as radiation workers. The University's standard radiation training course for laboratory persoinel was used as a template for the radiation safety training for the divers. Sections of the training relevant to radioactive materials use in a research laboratory wvere omitted while other areas specific to tile dive operation wverc covered with added detail. After the general radiation safety traininig topics (time, distance, and shielding; contamination control; exposure risks, ctc.) were plresented, these topics wvere applied in task specific training. Task specific training included reviews of dose rate and contamination survey maps of the reactor pool, access controls, use of survey instruments, decontamination procedures, dosimetry, and emergency procedures.

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2004 NETL Annual Report The replacement of the reflector component with the reactor pool filled and a twvo-month decay period minimized the personnel radiation dose to the divers but provided a balance with the operational needs of the facility.

A full-scale mockup of the various components and specialized remote tools wvere provided and used by the divers in a'separate 15 meter deep training pool prior to performing the actual dive. General Atomics International (manufacturer of the TRIGA reactors) loaned a full size prototype reflector for this mockup training. This training wvas necessary to allow the divers to becoine familiar with the remote operating tools fabricated by the UT-NETL and test the operation of these job-specific tools. The divers realized very quickly during the mockup training howv difficult it 'vould be to operate pneumatic wvrenches on long-reach rods and work near the radioactive components. A mockup of a reactor bellowvs and flange system permitted the divers and NETL staff to test several options to purge a large pipe of coolant while reinstalling the reflector assembly in the reactor pool. Many hours of labor and potential exposures were saved because the procedures and equipment were tested prior to commencing the actual reactor repairs.

Due to the extensive undervater experience of the ARL divers, the primary safety concern was the prevention of personnel overexposures during the pool dive. The divers were continuously monitored from the surface of the 'pool and with submerged cameras by the health physics staff. The divers used umbilical equipment for air, light and voice communication. This eliminated the need to return to the surface to change breathing air bottles and provided continuous communication. Alarming radiation dosimeters wvere provided to each member of the two member diver team and wvere sealed in clear, leak-proof dive bags.

The divers %N'ere requested to routinely use the rate meters when performing newv tasks that could change the radiological conditions.

Monitoring of diver doses was performed' using Landauer Luxel optically stimuillated luminescent (OSL) dosimeters in multiple locations on each diver. The OSL dosimeters were capable of providing accurate dosimetry while submerged in the pool. Dosimetry vitas attached to the diver's upper and lower arms, upper and lower legs, front and back of the head, back, chest, and hands. Additional self-ready personal dosimeters wvere attached to the arnis, legs, chest, and back for immediate post-dive evaluation.

The NETL reactor pool is perhaps unique when compared to many underwater radiological projects because of the confined spacing. The pool has an approximately oval cross section 2 meter by 3 meters but is 8.1 meters deep (Figurel). The diameter of the reactor core and 3-17

2004 NETL Annual Report reflector in the pool is over one meter thus leaving very little room to work around tile radioactive components. A portable herculite-covered lead shield curtain wvas hung directly in front of the Reflector to reduce the background radiation in the area the divers had to wvork by a factor of 100. This shield wvas fabricated from layers of commercially available lead blankets to produce a curtain 1.5 by 0.5 meter by 10 cm thick. The weight of the shield (approximately 450 kg) required tile facility'cranc to lowver and hold it in position. The divers removed tile stainless steel bolts of the reflector by reaching around tile curtain with remote pnlCeulimaltic WIrencIles.

Remote tools wvere used to retrieve the removed radioactive stainless steel hardware from tile pool floor and deposit them in retrieval containers. The containers were fi-CeLILenltly pIulledC to tile pool surface and immediately emptied into a drop tube to transfer the material into a shielded container nine meters from the dive area.

The pool floor anid many components in the pool had been previously surveyed using small adhesive patches for sampling and found to be contaminated. Although tile contamination levels were not high (1000-5000 dpml) it was noted that decontamination of the diV'er' suits would be difficult and would significantly increase tile time tile (livers were wvearing their suits (tIlus interfering wvith tile rest periods).

Each diver wvore a set of painter's knee pads, and rubber overshoes (diver fins were not required) wvhen wvorking in the reactor pool. Standard diver's gloves were plrovi(ded for minimal contamination control but the divers had been trained to only use remote tools to manipulate reactor components. Finally, a set of rubber mats were laid uIo) the pool floor to provide a contamination barrier and thus permlit tile divers to crouch or lay on the pool floor if necessary.

Diver surveying and decontamination areas wvere established as close as possible to the pool exit area. The NETL facility wvas not designed for large amounts of vater to be collected neII thile pool area and the divers and equipment were decontaminated using portable, shallow1 pools and hand spray bottles in the pool area.

The divers wvre able to remove 31 of 32 sets of nuts and bolts on flan-es connecting tile reflector assembly to the neutron beam pipes but one nut seized during removal. All manual efforts failed and tile nut was finally removed using a hydraulic nut splitter operated from the pool surlaee. This particular probleml as a potential wvork issue had been discussed in pre-dive planning and preparations. \\When tile nut seizer occurred, the hydraulic nut splitter was rapidly delivered by overnight courier with very little loss in work progress.

3-18

2004 NETL Annual Report Four bolts attached the reflector assembly to the pool bottom but the clearance for the divers was less than 30 vertical centimeters. The confined spacing made it difficult for the divers to manipulate the long reach pneumatic wrenches.

One nut did seize during removal but the confined area prevented using another nut splitter.

The nut and bolt were removed by overtorquing the bolt using a manual wrench and breaking the bolt in two. The remaining bolts were removed using therpneumatic tools and the reflector assembly was removed from the pool.

Before the dive, expected doses to the divers wvere estimated to be a maximumll of 500 mrem.

To be conservative, it was decided that a change in operational procedures would occur if any diver received more than 50 mrem in one dive. As stated earlier, the divers were provided with multiple dosimetry.

Each diver had 13 OSL badges, finger badges, and six direct-reading dosimeters for each dive. Different sets wvere used for old reflector removal and new reflector installation. As seen in Table I, all recorded diver doses were much less than originally expected.

TABLE I Summary of Diver Exposures Deep Dose DequivlentRight Hand Left Hand Equivalent (mR)

(R)

(mR)

Diver 1 197 270 230 Diver 2 88 250 340 Diver 3 12 30 50 The direct reading dosimeters were heat sealed within two poly bags for each dive. After each surfacing, the dosimeters were read and the dose recorded. Prior to rc-usc, the dosimeters were checked for damage and water, re-zeroed, and resealed in poly bags.

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2004 NETL Annual Report Divers I and 2 perfonied thle majority of tile work over a two week period with many single dives of two or more hours. Diver 3 perfonned one dive during installation of the newv reflector.

Actual measured doses rates ranged from a general area of 1.5 RIlhr to hot spot dose rates of 60 R/hr. The highest whole body dose received was 44 rnremn to Diver I and 340 nirern extremity dose was received by Diver 2. Before the dive, discussions with the manulla.cturer of the direct-reading dosimeters deternined that health physics personnel could expect readings as much as 25% higher than tile OSL badges. This fact was seen afler receipt of the data firom Landaucr.

Lessons from this project include the benefits of good planning, directed and specific training prograums for radiation workers, and experiences in dealing with unexpected occurrences despite careful planning. The dive operation occulTed over a twvo week period with nmanly single dives exceeding, 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> underwater. The ARL divers set new dive time records during this project but received relatively low total doses.

3-20

2004 NETL Annual Report 3.9 Radioactivc Effluents, Radioactivc Waste Radioactive effluents are releases to the air and to the sanitary sewer system. Thle most significant effluent is an airborne radionuclide, argon-41. Twvo other airborne radionuclides, nitrogen-16 and oxygen-19, decay rapidly and do not contribute to effluent releases. Argon-41, with a half-life of 109 minutes is the only airborne radionuclide emitted by the facility. A summary of the argon-41 releases are shown in Table 3-13. Total quantity of Ar-41 released in 2003 was 41.8% of the T.S. allowance.

This is based on a conservative dilution Iactor.

Evaluation of the radioactive gaseous effluent by the COMPLY code indicates the NETL is in compliance wvith dose limits to the public with a calculated effective dose equivalent of 8.1 mrem/yr at the conservative receptor point.

Table 3-13 Monthly Summary of Argon-41 Effluent Releases 2001 (1)

Date of Discharge (Month, 2001)

Total Quantity of Ar-41 Average Concentration of Ar-Tech Spec. Percentage of Released (microcuries) 41 at Point of Release Ar-41 Released January 1.266E+06 1.256E-07 6.28%

February 2.490E+06 2.470E-07 12.35%/

March 2.605E+06 2.585E-07 12.930/

pril 0.000E+O0 0.OOOE+00 0.00%

May 0.OOOE+00 0.OOOE+00 0.00%

June 0.OOOE+00 0.000E+00 0.00%

July 5.759E+03 5.713E-10 0.03%

August 4.270E+05 4.243E-08 2.12%

September 1.270E+06 1.256E-07 6.28%

October 4.120E+05 4.090E-08 2.050/

November 4.670E+05 4.635E-08 2.320/

December 2.370E+05 2.350E-08 1.180/

ANNUAL VALUE 9.180E+06 7.587E-08 3.79°/

(1) Point of release is the roof exhaust stack. Concentration includes dilution factor of 0.2 for mixing with main exhaust.

(2) Technical Specification limit for continuous release is 2.OOE-6 microcuriestcubic cm.

3-21

2004 NETL Annual Report Large liquid releases to the sanitary sewer are done from waste hold utp tanks at irregular intervals. To date, no releases have been made. The liquid radioactive waste tanks allow for segregation of liquids for decay of the activity.

Liquids may also be processed on-site to concentrate the radionuclides into other formis prior to disposal.

Small quantities of liquid scintillation cocktail or dilute concentrations may be disposed directly to the sanitary sewer if belowv the limits of 10 CFR 20. Liquids captured during the Reflector replacement project were evaluated but no activity wvas released. There were no solid waste transfers off the NETL R-129 License in 2004.

Table 3-14 Monthly Summary of Solid WVaste Transfers for l)isposal and Liquid Effluent Releases to the Sanitary Sewer From the NETI Facility 20(03 Date of Disposal I Release Volume Total Activity Total Activity Released (millicuiries)

Discharge (Month.) (cubis meters)

(millicuries)

January

0)

NONE No Releases February 0

NONE No Releases March 0

NONE No Releases April 0

NONE No Releases May 0

NONE No Releases June 0

NONE No Releases July 0

NONE No Releases August 0

NONE No Releases September 0

NONE No Releases October 0

NONE No Releases November 0

NONE No Releases December 0

NONE No Releases 3-22

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