ML20137A571

1996 Annual Rept for Nuclear Engineering Teaching Lab Jj Pickle Research Campus

ML20137A571
Person / Time
Site:	University of Texas at Austin
Issue date:	12/31/1996
From:	Bauer T TEXAS, UNIV. OF, AUSTIN, TX
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9703200378
Download: ML20137A571 (75)

Text

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}' s DEPARTMENT OF MECHANICAL EhGINEERING U! THE UNIVERSITY OF TEXAS AT AUSTIN h'OW, Y llUEngineering 7'eaching laboratory (512) 471-5787 FAX (512) 471-4589 6/ Nuclear

%g.Y March 11,1997 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Subject:

Docket 50-602 Annual Report 1996

Dear Sir:

A report is enclosed for the R-129 license activities of The University of Texas at Austin. The report covers the activities during the 1996 calendar year.

Sincerely, h w 'Ai W ~

Thomas L. Bauer Assistant Director, Nuclear Engineering Teaching Laboratory enclosure: 1996 Annual Report ,

cc: Region IV w/ enclosure 1 copy A. Adams w/ enclosure 1 copy

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J. IIowell w/ enclosure 1 copy 1 D.Klein w/ enclosure 1 copy P. Lamb w/ enclosure 1 copy B. Streetman w/ enclosure 1 copy B. Wehring w/ enclosure I copy 9703200378 961231 PDR ADOCK 05000602 llElEll3El@lEl][]$jjj R PDR Street Add ess: 10100 Burnet Road Austin, Texas 78758 MailAddress:J.J. Pickle Research Campus Bldg.159 Austin, lixas 78712

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i NUCLEAR REACTOR LABORATORY TECHNICAL REPORT THE UNIVERSITY OF TEXAS COLLEGE OF ENGINEERING DEPARTMENT OF MECHANICAL ENGINEERING g--

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l Annual Report 1996 1 1

Nuclear Engineering Teaching Laboratory J.J. Pickle Research Campus The University of Texas at Austin

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i Table of Contents Tables of Contents 11

List of Figures lii List of Tables iv Executive Summary v 1.0 Nuclear Engineering Teaching Laboratory 1-1 1.1 Introduction 1-1

! Purpose of the Report

. Availability of the Facility I -

Operating Regulations

. NETL History

. 1.2 NETL Building 1-4 i J.J. Pickle Research Campus a NETL Building Description

! Laboratories, Equipment 1.3 UT-TRIGA Mark II Researcn Reactor 1-8 Reactor Description Experiment Facilities Beam Port Facilities 1.4 Nuclear Engineering Academic Program 1-14 1.5 NETL Divisions 1-14 Operations and Maintenance Division Nuclear Analytical Services Division Neutron Beam Projects Division Health Physics Group 2.0 Annual Progress Report 2-1 2.1 Faculty, Staff, and Students 2-1 2.2 Education and Training Activities 2-6 l 2.3 Service and Commercial Activities 2-7 1 2.4 Research and Development Projects 2-10 I 2.5 Significant Modifications 2-22 2.6 Publications, Reports, and Papers 2-24

- 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 3-7 3.5 Facility Changes 3-8 3.6 Laboratory Inspections 3-10 3.7 Radiation Exposures 3-12 3.8 Radiation Surveys 3-18 3.9 Radioactive Effluents, Radioactive Waste 3-19 11

l List of Figures i

Figure 1-1 NETL - Nuclear Engineering Teaching Laboratory 1-1 l

1-2 NETL Site - J.J. Pickle Research Campes 1-4 1-3 NETL Building Profile 1-5 1-4 NETL Building - Layout 1-6 1-5 TRIGA Reactor Core 1-8 1-6 Reactor Pool and Beam Ports 1-10 1-8 NETL Staff Organization 1-15 2-1 University Administrative Structure over NETL 2-1 3-1 Operating History 3-1 3-2 Summary of All SCRAM Events 3-4 3-3 Operating Data 1995 - Monthly Burnup 3-5 3-4 Operating Data 1995 - No. of Sample Irradiations 3-6 3-5 Environmental TLD Locations 3-14 4

4 111

s List of Tables 4

Table

1-1 Physical Dimensions of Standard Experiment Systems 1-11 1-2 Physical Dimensions of Standard Beam Ports 1-13 j 1-3 Nuclear Engineering Courses 1-14

1-4 Health Physics Survey Equipment 1-19 l 5

2-1 The University of Texas System Board of Regents 2-2

2-2 The University of Texas at Austin Administration 2-2  ;

l- 2-3 Radiation Safety Committee 2-3 j_ 2-4 Nuclear Reactor Committee 2-3 I

. 2-5 NETL Personnel 2-4 )

l 2-6 Supplemental Funds 2-5 l 1~

1 2-7 Public Access 2-6 3-1 Protective Action Definitions 3-2

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3-2 ICS System Protective Action Events 3-3 l

3-3 Summary of Safety System Protective Actions 3-3

! 3-4 Summary of 1995 UT-TRIGA Operation 3-5 i 3-5 Summary of Utilization 1995 UT-TRIGA Experiments 3-6

! 3-6 Committee Meetings 3-10

! 3-7 Dates of License Inspections 3-10

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1 3-8 Annual Summary of Personnel Radiation Doses l Received Within the NETL Reactor Facility 3-13 I i 3-9 Total Dose Equivalent Recorded on Area Dosimeters i Located Within the NETL Reactor Facility 3-15 1

3-10 Total Dose Equivalent Recorded on TLD Environmental Monitors Around the NETL Reactor Facility 3-16 3-11 Radiation Protection Program Requirements and

! Frequencies 3-17

- 3-12 Annual Summary of Radiation Levels and l Contamination Levels Within the Reactor Area and l NETL Facility 3-18 3-13 Monthly Summary of Argon-41 Effluent Releases 3-19 l 3-14 Monthly Summary of Liquid Effluent Releases to the Sanitary Sewer From the NETL Reactor Facility 3-20 3-15 Monthly Summary of Solid Waste Transfers for Disposal 3-21 l 1

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FORWARD The mission of the Nuclear Engineering Teaching-Laboratory at The University of Texas at Austin is to:

1. prcseria, disseminate, and create knowledge, i

2. help educate those who will serve in the

! rebirth of nuclear power and in the expanding use of nuclear technology in industry and

medicine, and

! 3. provide specialized nuclear resources for educational, industrial, medical, and government organizations.

l j The above objectives are achieved by carrying out a

! well-balanced program of education, research, and service. The focus of all of these activities is the new TRIGA research reactor, the first new U.S.

university reactor in 20 years.

l The UT-TRIGA research reactor supports hands-on education in reactor physics and nuclear science. In

, addition, the reactor can be used in laboratory course j 4

work by students in non-nuclear fields such as physics,

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chemistry, and biology. It may also be'used in l

education programs for nuclear power plant personnel, i secondary schools students and teachers, and the general ,

public.

l The UT-TRIGA research reactor provides opportunities to do research in nuclear science and engineering. It can also contribute to multidisiplinary f

studies in medicine, epidemiology, environmental 1 sciences, geology, archeology, paleontology, etc.

l Research reactors, one megawatt and larger, constitute

< unique and essential research tools for examining the i

] structure of crystals, magnetic materials, polymers, biological molecules, etc.

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The UT-TRIGA research reactor benefits a wide range of on-campus and off-campus clientele, 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

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applications of nuclear science, and earn revenues to help support Nuclear Engineering activities.

Bernard W..Wehring, Director Nuclear Engineering Teaching Laboratory vi i

1996 Annual Report

1.0 NUCLEAR ENGINEERING TEACHING LABORATORY 1.3 Introduction Puroose of the Reoort The Nuclear Engineering Teaching Laboratory (NETL) at The University of Texas at Austin prepares an annual report of program activities. Information in this report provides an

introduction to the education, research, and service programs of

] the NETL. A TRIGA nuclear reactor is the major experimental l~ facility at the Laboratory. The reactor operates at power

levels up to 1100 kilowatts or with pulse reactivity insertions

o up to 2.2% Ak/k.

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[;.*Id 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

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! 110742 Task Order 2, Mod. 1], and the licensing agency, the U.S.

Nuclear Regulatory Commission (NRC) (docket number 50-602].

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1996 Annual Report This annual report covers the period from January 1, 1996 to December 31, 1996.

1 Availability of the Facility The NETL facility serves a multipurpose role. The use of l NETL by faculty, staff, and students in the College of Engineering is the Laboratory's primary function. In addition, 1

the development and application of nuclear methods is done to l assist researchers from other universities, industry, and government. NETL provides services to industry, government 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.

Onerating Regulations  ;

l Licensing of activities at NETL involve both Federal and i State agencies. The nuclear reactor is subject to the terms and specifications of Nuclear Regulatory Commission (NRC) License R-129, a class 104c research reacter license. Another NRC i license, SNM-180, for special nuclear material provides for the use of a subcritical assembly with neutron sources. Both j licenses are responsibilities of the NETL. For general use of radioisotopes the university maintains a broad license with the i State of Texas, LOO 485. Functions of the broad license are the ;

responsibility of the University Office of Environmental Health l 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 on the main campus in the engineering building, Taylor Hall. Reactor initial criticality was August 1963 with the final operation in April 1988. Power at startup 1-2

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l 1996 Annual Report was 10 kilowatts (1963) with one power upgrade to 250 kilowatts (1968). The total burnup during a 25 year period from 1963 to 1988 was 26.1 megawatt-days. Pulse capability of the reactor I was 1.4% Ak/k with a total of 476 pulses during the operating history. Dismantlement and decommissioning of the facility were completed in December 1992.

Planning for a new facility, which led to the shutdown of the campus facility, began in October 1983, with construction commencing in December 1986 and continuing until May 1989. The final license was issued in January 1992, and initial criticality occurred on March 12, 1992. The new facility, including support laboratories, administrative offices, and the reactor is the central location for all NETL activities.

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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 owner of the site, and in 1994 the site name was changed to the J.J. Pickle Research Campus.

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t 1996 Annual Report l.2 NETL Building

11. Pickle Research Camnus

, 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 approximately equal east and west tracts of land. An area of about 9000 square meters on the east tract is the location of the NETL building. Ten separate research units and several 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 on 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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1996 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 ft), and six supplemental areas (130 sq m, 1430 sq ft).

Conference and office space is allocated to 12 rooms totaling 244 sq m (2570 sq ft). One of the primary laboratories contains the TRIGA reactor pool, biological shield structure, and the

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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.

Figure 1-3 and 1-4 show the building and floor layouts for office and laboratory areas.

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I 1996 Annual Report inhoratories. Eauipment The NETL facility makes available several types of l 1

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. l The gamma irradiator is a multicurie cobalt-60 source with i

a design activity of 10,000 curies. Radioisotopes of cobalt-60, ,

cesium-137, and radium-226 are available in millicurie quantities.

Neutron sources of plutonium-beryllium and californium-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.

Radiation producing equipment such as x-ray units for radiography and density measurements are available as both fixed and portable equipment. 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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l 1996 Annual Report i

1.3 UT-TRIGA MARK II Research Reactor

! The TRIGA Mark II nuclear reactor at the Nuclear 1

j Engineering Teaching Laboratory of The University of Texas at Austin is an above-ground, fixed-core research reactor. The l nuclear core, containing uranium fuel, is located at the bottom i

l of an 8.2 meter deep water-filled tank surrounded by a concrete

! shield structure. The highly purified water in the tank serves

! as the reactor coolant, neutron moderator, and a transparent radiation shield. Visual and physical access to the core is l' possible at all times. The TRIGA Mark II reactor is a versatile i

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 j 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. Figure 1-5 is a picture of the reactor core structure.

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1996 Annual Report Reactor Descriotion Reactoroperation. The UT-TRIGA research reactor can operate continuously at nominal 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

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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.

Norlear Core. The reactor core is an assembly of about 90 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 fuel region is a metallic alloy of low-enriched 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.

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i 1996 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 allows 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 containing powdered boron carbide followed by UZrH. As these rods are withdrawn, boron (a neutron absorber) 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 transient rod produces an I immediate burst of power.

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-1996 Annual Report t

i Erneriment Facilities l

The experimental and irradiation facilities of the TRIGA l 4

Mark II reactor are extensive and versatile. Experimental tubes i

. can easily be installed in the core region to provide facilities 1'

for high-level irradiations or small in-core experiments. Areas I >

outside the core and reflector are available for large experiment" equipment or facilities. Table 1-1-lists the workable experiment volumes available in the standard experiment facilities.

. Table 1-1

, Physical Dimensions of Standard Experiment Systems l

Center Tube l Length: 15.0 in. 38.1 cm- '

Tube oD: 1.5 in. 3.81 cm Tube ID: 1.33 in. 3.88 cm Rotary Rack j Length: 10.8 in. 27.4 cm i Diameter: 1.23 in. 3.18 cm Pneumatic Tube l Length: 4.5 in. 11.4 cm'-

Diameter: 0.68 in. 1.7 cm I The reactor is equipped with a central thimble for access to the point of maximum flux in the core. The central thimble I consists of an aluminum tube that fits through the 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 gamma 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.

9 1-11

1996 Annual Report A pneumatic transfer system permits applications with short-lived radioisotopes. The in-core terminus of the system is normally located in the outer ring of fuel element positions, a region of high neutron flux. The sample capsule (rabbit) is conveyed to a sender-receiver station via pressure differences in the tubing system. An optional transfer box permits the sample to be sent and received from one to three different sender-receiver stations.

Beam Port Facilities Five neutron beam ports penetrate the concrete biological shield and reactor water tank at core level. These beam ports were designed with different characteristics to accommodate a wide 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.

Beam Port (. B P) #1 is connected to BP #5, end to end, to form a through beam port. The through beam port penetrates the l graphite reflector tangential to the reactor core, as seen in l 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 thermal neutrons with  !

• 1 relatively low fast-neutron and gamma-ray contamination.

l Beam Port #2 is a tangential beam port, terminating 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 gamma-ray backgrounds.

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 1-12

1996 Annual Report to the reactor core, and can provide a neutron beam with relatively high fast-neutron and gamma-ray fluxes. I f Beam Port #4 is a radial beam port which also terminates at the outer edge of the reflector. A void in the graphite a

j reflector extends the effective source of neutrons to the

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reactor core. This' configuration is useful for neutron-beam

) experiments which require neutron energies higher than thermal 4

! energies.

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A neutron beam coming from a beam port may be modified by i using collimators, moderators and neutron filters. Collimators are used to limit beam size and beam divergence. Moderators are i used to change the energy of neutron beams (e.g., cold j

l moderator) . Filters allow neutrons in selected energy intervals to pass through while attenuating neutrons with other energies.

i Table 1-2 i Physical Dimensions of Standard Beam Ports Ream Port Port Diamater 1

BPil, BPi2, BPi4 1 At Core: 6 in. 15.24 cm l At Exit: 8 in. 20.32 cm

, BP #3, BPf5 At Core: 6 in. 15.24 cm l 8 in. 20.32 cm I

10 in. 25.40 cm j At Exit: 16 in. 40.64 cm I

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1996 Annual Report 1.4 Nuclear Engineering Academic Program l 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 l

of Science in Mechanical Engineering, Nuclear Engineering Option. It is best described as a major in Mechanical .

j 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 are Master of Science in' Engineering (Concentration in Nuclear Engineering) and Doctor of Philosophy (Concentration in l

! Nuclear Engineering). Course requirements for these degrees and  ;

) the qualifying examination for the Ph.D. are separate and distinct from other areas of Mechanical Engineering. A Dissertation Proposal and Defense of Dissertation are also j required for the Ph.D. degree and are acted on by an NE l

dissertation committee.

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

l Table 1-3 Nuclear Engineering Courses Undergraduate ME 361F Instrumentation and Methods ME 361G Reactor operations and Control Graduate ME 388R.3 Kinetics and Dynamics of Nuclear Systems

. ME 389R.1 Nuclear Engineering Laboratory ME 389R.2 Nuclear Analytical Measurement Techniques 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 staff organization of 1-14

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4

1996 Annual Report the Nuclear Engineering Teaching Laboratory. It is based on  ;

three divisions, each with a manager and workers. The remaining staff including the Health Physics group is called the

]

administration, and supports the three divisions.

l The Operation _and Maintenance Division (OMD) is responsible for'the safe and effective operations of the TRIGA nuclear I reactor. Other duties include maintenance of the 14-MeV neutron 1 facility, the gamma irradiation facility, industrial x-ray

j. units, and the NETL computer system. Activities of OMD include

]' neutron and gamma irradiation service, operator / engineering training courses, and giving reactor short courses.

j l Director l

\ l l Clerical

] Staff I

i I ,

i Health l Physicist- i f Assistant Director ,

+ l 5

I I i operations Nuclear

! and Neutron Beam Analytical Maintenance Projects Services l

i Figure 1-8 NETL Staff Organization l

1 5 The Nuclear Analytical Services Division (NAS) is i

j responsible for providing, in a safe and effective manner, i analytical services such as Neutron Activation Analysis (NAA),

a I low level radiation counting, and isotope production. Other e service activities of NAS include teaching NAA short courses.

] The Neutron Beam Projects Division (NBP) is responsible for I the development and operation of experimental projects associated with neutron beam tubes. One permanent facility, a cold neutron source / neutron guide tube facility, is a unique facility for experimenting with low energy neutrons.

1-15

1996 Annual Report Operation and Maintenance Division The primary purpose of the Operation and Maintenance Division (OMD) is the routine maintenance and safe operation of the TRIGA Mark II Research Reactor. This division performs most of the work necessary to meet the Technical Specifications of the reactor license. Division personnel implement modifications to reactor systems and furnish design assistance for new experiment systems. The division operates standard reactor experiment facilities.

~

Other activities of the division include operation and maintenance of radioisotope irradiators, such as the cobalt-60 irradiator, and radiation producing equipment. Radiation producing equipment consists of a 14-MeV neutron generator, and I industrial x-ray machines.

Services provided to other divisions at the laboratory include assistance in the areas of initial experiment design, j fabrication, and setup. Maintenance, repair support, and l inventory control of computer, electronic, and mechanical equipment is also provided. Building systems maintenance is j also coordinated by the Operation and Maintenance Division. l l

Other activities include scheduling and coordination of facility j tours. l Nuclear AnalyticalService Division The principal objectives of the Nuclear Analytical Services Division (NAS) involve support of the research and educational missions of the university at large. Elemental measurements l using instrumental 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 the  ;

area of education, the division, with available state-of-the-art l equipment, helps stimulate the interest of students to consider I

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1996 Annual Report l ,

studies in the areas of science and engineering. Education in the irradiation and measurement of radioactivity is presented to j- college, high school and other student groups in class i demonstrations or on a one-on-one basis. The neutron activation

analysis technique is made available to different state agencies to assist with quality control of sample measurements. Analysis of samples-for the presence of various elements and measurements l of environmental' effects assists detection of toxic elements.

Radiation measurement systems available include several i

j' a

high purity germanium detectors with relative efficiencies

ranging from 20 to 40%. The detectors are coupled to a

! Vaxstation 3100. Two of the detectors are equipped with an i automatic sample changer for full-time (i . e . , 24 hrs a day) 1 utilization of the counting equipment. The Vaxstation is f connected to a campus wide network. This data acquisition and

{ ' analysis system can be accessible from any terminal on campus

and to any user with proper authorization, a modem and the t

necessary communication software. Safeguards by special protocols guard against unauthorized data access.

Neutron Beam Projects Division j The Neutron Beam-Projects Division (NBP) manages the use of l the five beam ports. Experiments at the beam ports may be permanent systems which function for periods in excess of one or l 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 l

(40 ft) .

j The main objective of the Neutron Beam Projects division is to develop and operate experimental research projects associated l

j' with neutron beams. The objectives of the research function are to apply nuclear methods at the forefront of modern technology j and to investigate fundamental issues related to nuclear physics

! and condensed matter. Another mission of the division is to i

1-17

1996 Annual Report obtain new, funded research programs to promote the capabilities of the neutron beam projects division for academic, government and industrial-organizations and/or groups.

The Neutron Beam Projects manager is responsible for 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, Gadolinium Neutron Capture Therapy studies and Texas Intense Positron Source.

Health Physics Groun The Health Physics (HP) group is responsible for radiation safety and protection of personnel at the NETL as well as the i 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 ensure 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 l 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 i* environmental health.

The Health Physics group consists of one full time Health

• Physicist. The Health Physicist is functionally responsible to the Director of the NETL, but maintains a reporting relationship 4

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.

A part-time Undergraduate Research Assistant (URA) may assist

{

j the Health Physicist. The URA reports to the Health Physicist J

l 1-18

1996 Annual Report and assists with technical tasks including periodic surveys, equipment maintenance, equipment calibration, and record

. keeping.

The equipment currently used by the Health Physics group is presented in Table 1-4. Supplementing the health physics equipment are supplies such as plastic bags, rubber gloves, radiation control signs / ropes for routine and emergency use.

. Table 1-4 Health Physics Equipment l

l Eaulnment Radiation Nirmhe r High and low range I self-reading pocket dosimeters gamma >10 Thin window friskers alpha / beta / gamma >8 Scintillation micro l remmeter low level gamma 1 1 High range portable ion chamber beta / gamma 2 BF3 proportional counter neutron 2 Hand and Foot monitor beta / gamma 1 Low level gas-flow proportional counter alpha / beta / gamma 1 continuous air particulate monitor alpha / beta / gamma 1 Gaseous Ar-41 effluent monitor beta 1 The Health Physics Group provides radiation monitoring, personnel exposure monitoring, and educational activities.

Personnel for whom permanent dosimeters are 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 equipment and to reinforce safety / emergency 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 1-19

I i 1996 Annual Report 4

in emergency planning between NETL and the City of Austin'to I 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.

0 l l

l l

i i

9 e

1-20

1996 Annual Report 2.0 ANNUAL PROGRESS REPORT 2.1 Faculty, Staff, and Students Organization. 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.

President

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

Dean College of Engineering Nuclear Reactor Committee Chairman Department of Mechanical Engineering i

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 with separate degree programs. NETL is one of several education and research functions within the college.

2-1

1 1996 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.

i 3

Table 2-1 The University of Texas System Board of Regents 1

Chairman B. Rapaport Vice Chairman T.O. Hicks Vice Chairman M.E. Smiley

} . Executive Secretary A.H. Dilly

}

Chancellor William Cunningham i

Mamber 1997 Member 1999 Mambe r 2 0 01 l Z.W. Holmes, Jr. T.o. Hicks L.F. Deily

] B. Rapaport L.H. Lebermann T. Loeffler l E.C. Temple M.E. Smiley D.L. Evans J

J l

4

Table 2-2

! The University of Texas at Austin

{ Administration i

4 President Robert Berdahl I

i Executive Vice President and Provost Mark Yudof

! Dean of College of Engineering Herbert Woodson (8/31/96)

Ben Streetman (1/1/97)

,. Chairman of Department of Mechanical Engineering Kenneth Diller (1/15/96)

Parker Lamb (1/16/96) 3 i

J-J 5

2-2

+ ,e >

. . _ . _ _ _ _ ~

_ .. . - - _ ~ . - - _ - . . .- . - - - . - - . - - --. . _ -

1996 Anr. cal Report Radiation Safety Committee. The Radiation Safety Committee convenes to review radiological safety practices at the University during each academic term. The committee composition is shown in Table 2-3. Committee general responsibilities are j review of activities of University research programs that i utilize radiation source materials.

4 d

Table 2-3 Radiation Safety Committee l Chairman E.L. Sutton

, Member G. Hoffmann

, , Member D.E. Klein Member S.A. Monti

,i Member J. Robertus

( Member J. Sanchez (95-96)

Member B.W. Wehring

. Ex officio member G. Monroe Ex officio member J.C. White

Nuclear Reactor Committee . The Nuclear Reactor Committee convenes i to review the activities related to facility operation during each quarter of the calendar year. The committee composition is i shown in Table 2-4. Committee general responsibilities are l j review of reactor operation and associated activities, j

)

! Table 2-4 1

Nuclear Reactor Committee Chairman R. Charbeneau (1995-96)

Member D. Blackstock (1995-96)

Student Member R. Canaan (1995-96)

Student Member R. Radulescu (1996-97)

Member E. Peters Member D.E. Klein (1995-96)

. Member B.W. Wehring Member K. Ball (1996-97)

Member R. Corsi (1996-97)

Ex officio member T.L. Bauer Ex officio member J. White Ex officio member K. Diller (1/15/96)

P. Lamb (1/16/96)

Ex officio member J. Howell (1996-97) 2-3

1996 Annual Report Personnel. NETL state funding supports full-time positions for a Reactor Supervisor / Assistant Director, three managers, a Health Physicist, and a Senior Administrative Associate.

External funding by research grants and service activities support student assistantships. The personnel involved in the NETL program during the year are summarized in Table 2-5.

Table 2-5

. NETL Personnel NETL Facility Staff Director B.W. Wehring Reactor Supervisor / Assist. Dir. T.L. Bauer Manager NAS(Research Scientist) F.Y. Iskander Manager NBP(Research Scientist) K. Unlu Manager O&M(Res,earch Associate) M.G. Krause Health Physicist (Research Associate) A.J. Teachout sr. Administrative Associate J.G. Rawlings Faculty N. Abdurrahman B.V. Koen D.E. Klein B.W. Wehring Student Assistants Graduate Level:

Gursoy Akgue Syed Zain Mujtaba  ;

Brahim Boumakh Georgeta Radulescu '

Mohamed Elsawi Horia Raul Radulescu Sinan Goktepeli Ed Reott l Young Jo Mehmet Saglam Mark Kelly Bill Spiesman Undercraduate Level: l Muhammad Syed Smdmg. NETL funding is provided by state appropriations,

. research grants, and service activities. Research funding supplements the 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 education and research environment for students. Table 2-6 lists the current supplemental funds.

2-4

_ . . _ __ ____._ _ _ _ _ _ _ . _ _ __ _ _ _ _ ._ . _ . _ _ _ .m .. _ _ _ _ _ . . _ . _ _ _ _ _ _

a 1996 Annual Report 4

I Table 2-6 Supplemental Funds i

1 Project Title Fit nd i ng Funding Amount j Period Source f

i Instrumentation for the j University of Texas Reactor 9/30/92-9/29/96 DOE 26,506 1

Analysis for Selenium 9/01/95-8/31/96 TPW 5,020 1

• Radiation Damage and

, Microstructural Changes of i Stainless Steel Due to

} Long-term Irradiation by I

• Alpha Particles Emitted from Plutonium 6/1/95-1/15/97 ANRCP 167,414

Water-Reactor Options for 4 Disposition of Weapons Plutonium 6/1/95-1/15/98 ANCRP 157,747 Developnent of Non Destructive Assay Methods for Weapons Plutonium and MOX Fuel Safeguards 6/1/95-8/31/97 ANCRP 342,011 Neutron Imaging System for Materials Characterization Research at The University of Texas Reactor -9/15/95-8/31/96 NSF 75,000 ALCOA gift 3/22/95-3/15/98 10,490 Gallium Interaction with Zircalloy 6/1/96-1/15/97 ANCRP 126,878 Reactor Based Intens<a Positron Beant for Materials Characterizai.lons 1/1/96-12/31/97 TATP 240,120 2-5 j

, 1996 Annual Report 3-4

) i

! 2.2 Education andTraining Activitws Tours and special projects are available to promote public j awareness of nuclear energy issues. Tours of the NETL facility  ;

j are routine activities of NETL staff and students. A typical l tour is a general presentation for high school and civic l organizations. Other tours given special consideration are demonstrations for interest groups such as physics, chemistry f l and science groups.

j A total of 1432 visitors were given access to the facility 1 ..

j during the reporting period. The total includes tour groups, official visitors, and facility maintenance personnel. Tours l* for 25 groups with an average 15 persons / group were taken 3

through the facility during the reporting period.

l Table 2-7 Public Access Tour Groups 389 )

Individuals 479 '

Workers lii Total 1432 Presentations by NETL staff, including demonstrations with laboratory equipment, were given to several high school organizations. These presentations were done as part of school wide programs sponsored by the high schools.

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l 1996 Annual Report i,

2. 3 Service and Commercial Activities a

I PROJECT: Determination of Selenium and Other' Toxic

Elements SPONSOR: Texas Parks And Wildlife Department Tissue from muscle and liver of fish samples from several

Texas lakes are analyzed for selenium, mercury, arsenic, chromium and zinc. These measurements are part of an

! environmental project for the State of Texas to examine the j conditions of waters subjected to certain types of power plant or industrial effluent releases, i

. PROJECT: Determination of Toxic and Other Elements in Mexican Cigarettes

..! SPONSOR: NETL The concentration of 27 elements was determined in j wrapping paper and cigarette tobacco in several Mexican cigarette brands. The results were compared to the concentration of these elements in the American and other a

national cigarette brands. In a closed environment, the accumulation of cigarette ash may represent a source of potentially toxic elements in particular to children.

Therefore, the concentration of the same elements were also

]

j measured in the cigarette ash.

PROJECT: Multielement Determination in Plants used in 3

Mexican Folklore Medicine SPONSOR NETL The study focused on the concentration of various elements

! in 31 plants used in Mexican folklore medicine. This study has f* two goals. The first goal is to estimate the intake of toxic or potentially toxic elements during the course of treatment. The

!.. second goal is to establish whether or not a specific element is found in higher' concentration in one group of plants used for the treatment of specific diseases.

i j

I

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a . a 1996 Annual Report l

PROJECT: Multielement Determination in Airborne j Particulate ,

SPONSOR NETL Airborne particulates from 30 locations in Zacatecas, I Mexico were collected. All samples were analyzed to determine the concentration of toxic and other elements around the city.

The results will help in mapping the concentration of each element. Concentration distributions may provide data to identify the source of pollution.

PROJECT: Measurements of Cu and Zn in Alloys SPONSOR Kwikset Corporation, Denison, Texas

. Alloy materials use for making locks were analyzed by )

l instrumental neutron activation analysis to measure copper and zinc contents. The analysis was performed as quality assurance on the raw starting materials received by the suppliers.

Replacement of the cheaper soft metal zinc for the harder expensive copper will effect the product quality. l l

PROJECT: Chemical Profile in K/T Boundary Section in Central Eastern Desert, Egypt SPONSOR Department of Geology, The University of Texas at Austin Platinum group element Ir that is abundant in meteorites and in the earth's mantle but rare in the crust was found in above normal concentrations in Cretaceous-Tertiary Boundary (KTB) samples from Italy, Denmark, and New Zealand. Osmium in the KTB indicates an extraterrestrial source. Uranium and thorium isotope anomalies have also been reported in KTB sites.

In this study neutron activation analysis is used to measure the elements of interest at trace and ultra-trace concentration.

PROJECT: Measurement of Se in Fish Tissue SPONSOR PMT Jones and Neuse, Inc., Austin, Texas Selenium concentration in a refinery discharge was assessed by analyzing biological tissue and sediment samples. This study is a part of a project to study the environmental effect of plant effluent discharge. Neutron activation analysis was used 2-8

l 1996 Annual Report l l to determine the concentration of selenium is the samples l investigated. I l-I PROJECT: Trace Element Measurements in Polypropylene Used I

in a Medical Device

, SPONSOR Dr. W. Uland, San Antonio, Texas

Polypropylene components of a medical device that is to be 4

inserted intravenous was analyzed by neutron activation analysis trace elements measurements. The objective of the project is to 1

1 study the purity of Polypropylene and its suitability, with 4

regards to its composition, for intravenous use.

s

]

).

i PROJECT: Measurements of Ultra-trace Concentration of Several Elements in Silicon Wafer SPONSOR: Dr. Tim Hossian,. Advanced Micro Devices.

t The concentration of Na, K, Cr and Cu was measured in I

silicon wafer samples. INAA was the technique of choice due to

- its high sensitivity and minimum handling of the very high purity material (silicon wafer) . INAA minimizes the possibility of sample contamination.

i l

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i 1996 Annual Report 2.4 Research andDeveloomentProtects s

! PROJECT: Neutron Depth Profiling SPONSOR: NETL j A neutron depth profiling (NDP) instrument has been designed, constructed, and tested. The University of Texas (UT)

NDP instrument utilizes thermal neutrons from the tangential l

j beam port (BP#2) of the reactor. The NDP technique is not

[ normally available to the research community due to the limited

,. number of appropriate neutron sources.

i Neutron depth profiling is an isotope specific nondestructive technique used to measure the near-surface depth

{. distributions of several technologically important elements in l various substrates. NDP is based on neutron induced reactions i to determine concentration versus depth profiles. Because of I the potential for materials research, particularly for

$ semiconductor research, the UT-NDP facility has been developed i and is available for scientific measurements.

I The UT-NDP facility consists of a collimated thermal

$ neutron beam, a target chamber, a beam catcher, and necessary

data acquisition and process electronics. A collimator system l was designed to achieve a high quality thermal neutron beam with l good intensity and minimum contamination of neutrons above j thermal energies.

f A target vacuum chamber for NDP was constructed from 40.6 cm diameter aluminum tubing. The chamber can accommodate several small samples or a single large sample with a diameter

, up to 30 cm. The other degrees of freedom for an NDP measurement, location of charged particle detector and angle between sample and neutron beam, are set with the top cover of the chamber removed.

Depth profiles of various borophosphosilicate glass from Intel Corporation have been measured. Measurements were repeated at the National Institute of Standards and Technology (NIST) NDP facility using the same samples. The NETL results showed good agreement with the NIST depth profiles.

2-10

i

! I 1996 Annual Report l Other possible applications of the UT-NDP facility include the study of implanted boron in semiconductor material as a l function.of wafer treatment; study of nitrogen'in metals as it i affects wear-resistance, hardness, and corrosion; and study of i

helium behavior in metals, and metallic, and amorphous alloys.

! Gadolinium Neutron Capture Therapy Dosimetry 1 PROJECT: . Measurements l SPONSOR: NETL and The University of Texas MD Anderson j Cancer Center j- Neutron capture therapy (NCT) is a technique which employs l neutrons in conjunction with neutron-absorbing drugs to create f.

localized radiation damage. It shows promise in the treatment of some malignant tumors of the human central nervous system.

I

) Boron-10 is the material most often suggested for use as an NCT

agent due to its large thermal neutron absorption cross section '

I for the (n, alpha) reaction.

Another material, gadolinium, has been considered as an NCT agent. In comparison to boron, most of the energy from neutron capture in gadolinium is nonlocalized gamma radiation. Thus, gadolinium does not need to be located in or on tumor cells, but only in the tumor to deliver a radiation dose to the cancerous cells. A possible negative result of using gadolinium is that healthy cells may also be damaged. Thus, a knowledge of the j dose distribution near the tumor is very important. Several l calculations have predicted this spatial variation, but it has not been measured for Gadolinium Neutron Capture Therapy. A research program was initiated at the NETL to measure the low-LET dose distribution in a head phantom with and without a Gd j loaded tumor region.

. Epithermal neutrons give better results than thermal neutrons for the treatment of deep seated tumors. In order to provide epithermal neutrons BP #4 is used for the NETL study.

The problem with using this type of beam port is that high background of core gamma rays make it difficult to measure the dose delivered by the Gd gamma rays. This problem does not 2-11

1996 Annual Report l 1

exist for the corresponding Boron Neutron Capture Therapy (BNCT) experiment.

Neutron filters were designed to improve the quality of the l neutron beam, i.e., to decrease the dose rate of core gamma j rays, to facilitate Gadolinium Neutron Capture Therapy (GdNCT)

, dose measurements, and to decrease the flux of MeV neutrons to better simulate propcsed clinical neutron beams. Several neutron filters, to be placed midway in the beam port, were constructed which contained lead to attenuate core gamma rays, l cadmium to attenuate thermal neutrons, aluminum to attenuate neutrons with energies above 30 kev, and titanium to attenuate neutrons which leak through the aluminum with energies between I 10 and 30 kev.

A cylindrical head phantom made of brain tissue equivalent plastic was constructed by The University of Texas, M.D. l Anderson Cancer Center researchers. The phantom, a 16-cm diameter 16 cm long cylinder, consists of 11 disks. Gold foils and thermoluminescent dosimeter (type TLD-600 and TLD-700) were placed in depressions on the surfaces of some of the disks.

The initial efforts at measuring gadolinium dose rates were 1

not successful because the background gamma dose rate was too l high. Measurements and calculations indicate that the lead used to attenuate the core gamma dose also attenuates the kev neutrons. Thus, the signal to noise was not significantly improved. Extensive design calculations and measurements have been done during the past year for a new geometry for these measurements.

The current work involves scattering the neutron beam to create the dose on the head phantom. The geometry involves a D20 sphere placed at the exit of the beam port, and the head phantom placed near the D20 sphere perpendicular to the exiting neutron beam. The phantom was placed outside the beam port exit, shielded from the direct beam, 300 cm away from the core.

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i 1996 Annual Report Texas Cold Neutron Source PROJECT:

SPONSOR:

l Advanced Technology Program and the State of i a

Texas l J A cold neutron source has been designed, constructed, and i

tested by NETL personnel. The Texas Cold Neutron Source (TCNS) is located in one of the radial beam ports (.B P #3) and consists

of a cold source system and a neutron guide system.

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 i by the cold source system at ~36 K in a chamber within the 4

reactor graphite reflector. Mesitylene, 1,3,5-trimethylbenzene,

was selected for the cold moderator because it has been shown to j be an effective and safe cold moderator. The moderator chamber j for the mesitylene is a 7.5 cm diameter right-circular cylinder l 2.0 cm thick. The neon heat pipe (properly called thermosyphon) i is a 3-m long aluminum tube which is used for cooling the l 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 i 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 with a radius of curvature equal to 300 m. To block line-of-sight radiation streaming in the guides, the j

cross-sectional area of the guides is separated into three

, channels by 1-mm-thick vertical walls. All reflecting surfaces j are coated with Ni-58.

The TCNS system provides a low background subthermal neutron beam for neutron reaction and scattering research.

After installation of the external curved neutron guides and completion of the shielding structure, neutron focusing and a j Prompt Gamma Activation Analysis facility will be installed at the TCNS. The only other operating reactor cold neutron sources in the United States are at Brookhaven National Laboratory and j the National Institute of Standards and Technology. At least

2-13 e r -

1996 Annual Report 1

four major centers for cold neutron research exist in Europe, with another two in Japan.

PROJECT: Study of Neutron Focusing at the Texas Cold Neutron Source j SPONSOR: DOE j The design and construction of a neutron focusing system for use with the Texas Cold Neutron Source (TCNS) were thoroughly investigated. The focusing system is located at the end of the TCNS curved neutron guide to increase the neutron flux for neutron capture experiments which benefit from the low background at the end of the curved guide. One example of such an experiment is Prompt Gamma Activation Analysis, a ,

1 nondestructive nuclear analytical technique based on '

spectroscopy of neutron capture gamma rays.

After examining several methods for neutron focusing, a converging neutron guide was chosen for use as a focusing system. Different multielement converging guides were designed l and analyzed. Each consisted of a number of truncated rectangular conical sections coated with Ni-C/Ti supermirrors.

A four-element 80-cm-long converging guide was selected for use with the TCNS. Ovonic Synthetic Materials of Michigan, a small company which is the only company in the US capable of doing Ni-C/Ti coating for supermirrors, built the converging neutron guide focusing system to our specifications.

The focused cold neutron beam will be used for neutron capture experiments, e.g., Prompt Gamma Activation Analysis and Neutron Depth Profiling. Because of the increased intensity of the neutron beam due to neutron focusing, we will be able to analyze small samples with high sensitivity. The technique will l provide a unique capability to address a wide variety of analytical problems of importance in science and technology.

l 2-14 j

1996 Annual Report '

i PROJECT: Prompt Gamma Activation Analysis i SPONSOR: DOE and the State of Texas I i

A Prompt Gamma Activation Analysis (PGAA) faeliity has been designed and constructed. The UT-PGAA facility utilizes the

! focused cold-neutron beam from the Texas Cold Neutron Source.

The PGAA sample is located at the focal point of the converging guide focusing system. The use of a guided focused cold-neutron j beam provides a higher capture reaction rate and a lower I

background at the sample-detector area as compared to other facilities using filtered thermal neutron beams.

j The UT-PGAA facility has been designed taking into account i . the advantage of the low background. The following criteria j have been used during the design: a) The structure and shielding

materials for the UT-PGAA facility were chosen to minimize the j background contribution for elements to be detected in the samples to be studied. b) The sample handling system was f 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.

A 25% efficient gamma-ray detector in a configuration with an offset-port dewar was purchased to be used at the UT-PGAA facility. The detector was selected in order to incorporate a Compton suppression system at a later date. A gamma-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,

11) determination of H and B impurity levels in metals, alloys, j

- and semiconductor, iii) multielemental analysis of geological, l archeological, and environmental samples for determination of major components such as Al, S, K, Ca, Ti, and Fe, and minor or I 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.

2-15 j

l. I

. 1996 Annual Report .

l i l PROJECT: Radiation Damage And Microstructural Changes Of i Stainless Steel Due To Long-Term Irradiation By Alpha Particles Emitted From Plutonium

SPONSOR

Amarillo National Resource Center for Plutonium j (ANRCP) l This ANRCP sponsored project is a study to det. ~ ' ne radiation damage and microstructural changes in stainless steel l samples by helium (alpha particle) irradiation using a near I surface nuclear technique called Neutron Depth Profiling, along j, with Transmission Electron Microscopy measurements, and l j Rutherford Backscattering and Channeling Analysis. The long term effects of high dose alpha particle irradiation to the i.

s i

I

! stainless steel cover which surrounds the weapons grade Pu will i be investigated. Alpha particles with an energy spectrum up to l l 5 MeV will be implanted into the stainless steel up to a depth l of about 9 mm. The implanted dose rate is expected to be

greater than 10 15 alphas /cm 2 -year which corresponds to a dose of j greater than 1017 alpha /cm2 in 100 years. Such a high dose may 4

cause degradation of mechanical strength in the surface layer of the stainless steel, but more importantly, if the He diffuses to l

defects and forms localized bubbles of He gas, the internal pressure may cause exfoliation and/or could lead to the

! formation of cracks in the stainless steel. These cracks could propagate and lead to failure of the stainless steel cover. l l

i PROJECT: Collimator Design for Neutron Radiography SPONSOR: Department of Mechanical Engineering A collimator design is being developed for beam port #5 of j* the TRIGA reactor. The collimator will provide neutrons for f' imaging various objects for analysis by neutron radiography. An

. image intensifier, display and acquisition system and analysis j software are being acquired. The system will provide standard neutron radiography and provide for research into neutron tomography.

PROJECT: Cyclic Activation for Detection of Aluminum and Sodium.

j SPONSOR: Aluminum Company of America (ALCOA) i 2-16

+

-m

_ _ _ _ _ _ _ . _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ . . _ _ _ . _ _ _ . _ _ __m_

1996 Annual Report A gift of funds from ALCOA is being used to study the application of' neutron isotopic sources for the measurement of industrial process solutions. Neutron activation analysis detects and measures the concentrations of short-lived radio-nuclides. The work examines the measurement requirements, irradiation cell design, and effects of neutron source including use of fast or thermal neutrons. Analysis methods including simple activation and cyclic activation are being applied.

-Models of the irradiation and measurement process and the

~

facility design have been developed for general application.

. PROJECT: Texas Intense Positron Source SPONSOR: Advanced Technology Program and the State of Texas A reactor-based slow positron beam facility is being developed at the University of Texas (UT) at Austin, Nuclear Engineering Teaching Laboratory (NETL). This is a joint effort between UT-Austin and UT-Arlington researchers. The facility (Texas Intense Positron Source -TIPS) will be one of the few reactor-based slow positron beams in the world when completed.

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. High energy positrons from the source will.be slowed down to a few eV by a solid Kr moderator that also acts as a remoderator to reduce the beam size to enable beam transport to a target for experimentation. The beam will be electrostatically guided and will deliver about 108 positrons /sec in the energy range of 0 - 50 kev.

Reactor-based positron beams utilizing a copper source have been implemented at Brookhaven National Laboratory (BNL) and at Delft University of Technology, The Netherlands. There are l

~several differences between TIPS and these reactor based positron beams. The source / moderator array of the Delft positron beam is located inside one of the neutron beam ports of their reactor and the positron beam is transported out of the reactor and then remoderated before it enters into an experimental chamber. For the BNL positron beam, a 200 mg 2-17

____.__________.._.__-.___.____._m. ._

i

] 1996 Annual Report 1

copper pellet is irradiated in the High Flux Beam Reactor (8. 3x10" n/cm2 .sec) and then transported to their positron beam facility at a different location where the copper is evaporated i onto a source holder. The BNL positron beam uses solid Kr to i moderate the fast positrons while at Delft a tungsten moderator

is applied. The TIPS will have a joint moderator /remoderator j stage using solid Kr, an approach that is similar in concept to i 3

that suggested for a magnetically guided positron beam. A major  ;

! advantage is that our moderator /remoderator stage is operated in

$* a magnetic field free environment such that electric fields can j 1

j be established to increase its overall efficiency. l

!* Based on general experience on reactor based positron i

i sources, 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 long vacuum jacket that will be inserted into one of the neutron beam ports of the NETL 1-MW TRIGA Mark II research reactor. The vacuum jacket will be evacuated to l high vacuum and will have a rectangular section to allow for l

, some shielding materials inside the beam port. The transport 1

system will be used to move the source to the irradiation  ;

j location and out of the biological shield. The source will be I i,

moved away from the neutron beam line to an ultra high vacuum (at around 10-10 torr) chamber, where the moderator /remoderator l.

l assembly is located. The high vacuum and ultra high vacuum systems will be separated by a gate valve.

! The copper source of TIPS will be irradiated across from i the core in the graphite reflector, in the middle section of the' j through port. The isotope 84 Cu formed by neutron capture in 83Cu ,

1 l

(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 I branching ratio for + emission is 19 %. Our current source design consists of 400 copper cylinders with 1 cm height and 0.5 2

cm diameter mounted on a 10x10 cm copper plate forming a square lattice. The source activity will be around 100 Ci of which 14

} Ci or more is available for positron beam production. The i

j combined efficiency of the moderator /remoderator assembly is i 2-18

1996 Annual Report approximately 10-3 and, therefore, TIPS should deliver about 108 positrons /sec at the sample chamber.

Preliminary designs of the source transport system and the vacuum jacket are completed. The designs of the copper source,

- moderator /remoderator assembly, and the positron beam optics are J currently in progress. The high-intensity low-energy positron beam of TIPS will be applied to defect characterization of metals, semiconductors, and polymers. ,

i PROJECT: Gallium Interactions with Zircalloy Cladding SPONSOR: DOE and Amarillo National Resource Center for Plutonium This ANRCP sponsored project is a join effort between The University of Texas at Austin and Texas A&M University researchers. The effort is aimed toward determining a bound on Ga concentration in MOX pellets such that the Ga does not produce unacceptable damage to the cladding Although the real test will be the fuel qualification work, we should be able to experimentally simulate and examine some aspects of the Ga-cladding interaction. The Ga that is released from the pellet will be incident on the cladding while the cladding is also being irradiated with fission fragments, neutrons, betas, and gammas. Clearly, the Ga interaction will not be under thermal equilibrium conditions. The irradiation of the cladding, especially by the fission fragments, will probably lead to enhanced diffusion and possibly to enhanced chemical reactions. We do not know the Ga release rate from the pellet nor whether the Ga will be monatomic or in chemical form, i.e.,

possibly in an oxide of Ga. In the molecular case the irradiation conditions will probably lead to breakup of the, molecule so that in both cases the Ga will probably diffuse into the cladding.

Each ppm of Ga in the fuel corresponds to about SE16 Ga atoms /cm3 Since a pellet is about 1 cm3 surrounded by about 3 cm2 of' cladding, if all the Ga were released from the fuel, the cladding would be impacted by roughly 1E16 Ga atoms /cm3 For example, 100 ppm would give roughly 1E18 Ga atoms /cm 2, 2-19 5

1996 Annual Report 1

To approximate the situation, we are implanting Ga ions into Zircaloy to a shallow depth of about 400 A (100 kev ions).

Fluences are in the 1E17 to 1E18 range while maintaining the target at typical cladding temperatures. If there were no diffusion nor sputtering, a lE17 fluence would give a peak concentration of 40% in Zr (corresponding to a standard deviation in projected range of 229 A). The Ga depth profile can then be measured approximately using Rutherford backscattering (RBS) of energetic He ions. Unfortunately, since the mass of Ga is less than that of Zr, the sensitivity will only be in the percent range. Even so, major effects may be observable. Perhaps, the Ga totally indiffuses or totally outdiffuses or forms a well-defined compound layer.

The depth profile measurements will be supplemented with scanning electron microscopy for morphology, transmission electron microscopy for structure measurements, and electron microprobe measurements of especially the lateral distribution of Ga as well as the identification of possible compounds.

Laterally, it may be possible to determine whether Ga diffuses to grain boundaries.

PROJECT: Water-Reactor Options for Disposition of Weapons Plutonium SPONSOR: DOE and Amarillo National Resource Center for Plutonium Benchmarking efforts in support of the US/RF joint study on water reactors were carried out this year by the UT group of this project. A large body of results, the content of which we

= had agreed upon via discussions with ORNL, was delivered to ORNL in January for inclusion in the Feb. 1 report that was sent to

, Russia. These results included: evaluations (documentation and interpretation) of three sets of experimental benchmarks ("PNL",

"Saxton-65", and part of "Saxton-67"); MCNP results of all possible variants of one of the RF VVER-style computational benchmarks; and CASMO results of the entire set of US PWR-style computational benchmarks. Also, MCNP criticality calculations of many of the Saxton-65 experiments were completed early in the 2-20

4 1996 Annual Report I

quarter, and a draft report was delivered to ORNL in November.

Work began on the MOXDAR Virtual Library.

Progress continued on the Mixed Oxide Data Repository i (MOXDAR). The server was upgraded to Windows NT 4.0 and a l I

Variety search engine was installed. More documents were l 1

scanned, indexed, and placed on the MOXDAR Virtual Library.

i PROJECT: Development of Non Destructive Assay Methods for Weapons Plutonium and MOX Fuel Safeguards l SPONSOR: DOE and Amarillo National Resource Center for i b

Plutonium l 1

i The focus of this project is to develop and eventually aid

. in the implementation of practical nondestructive fissile assay j techniques to promote the nonproliferation of nuclear weapons.

Our activities during this year covered both ccmputational and

experimental related work. We continued our computational effort focusing on the neutronics of a new nondestructive assay concept that uses graphite slowing down time spectrometry. We have developed a computational model of a cylindrical graphite slowing down time spectrometer, and performed a number of assay simulations using a detailed BWR fuel assembly model. In addition, we investigated the isotopic resolving power and self shielding effect in the fuel assembly for the graphite spectrometer.

On the experimentally related part, we have successfully transferred the pulsed neutron generator, from The University of Michigan to The University of Texas at Austin. The neutron generator is now being set up at the Nuclear Engineering Teaching Laboratory of The University of Texas. We have completed the design and have started the fabrication of the a generator support structure which consists of several steel bases. We have also completed the assessment of the vacuum requirements of the new generator and are now in the process of ordering the required pumps and controllers for the new system.

2-21

1996 Annual Report 2.5 SignilicantModifications No significant modifications have been made to the NETL building, TRIGA reactor or experiment facilities. A summary of the types of modifications that did occur during the year follows. A significant effort from the previous year continues in progress during this year to test a cold neutron source for the reactor.

Building. Routine repair and maintenance of building equipment were the only activities. No changes to the building systems effect the safety of operation of the reactor.

Reactor. No changes were made to the reactor core or basic instrumentation systems during the year. Funds have been obtained to upgrade two control rod drives taken from the Taylor Hall facility. The'two drives will be replaced with stepper motor drives. An amendment to the Technical Specifications will be necessary to correct language.regarding simultaneous motion of two or more control rods during automatic operation. This work remains in progress from the previous year.

Erneriment Facilities . Standard experiment facilities for the reactor are the center tube, pneumatic tube, rotary specimen l rack and beam ports. No significant modifications were made to l the original installation for any of the standard experiment )

l facilities.

The pneumatic tube (PNT), including support equipment is i not currently part of the installation. Installation of the pneumatic system was a low priority during this year, although planning and installation was in progress. The installation is 85% complete. An experiment authorization for the PNT was completed. Final installation and test of the irradiation terminal should occur during 1997. Modifications to the system are in the planning stage.

Testing of components of the neutron cold source has been in progress at various reactor power levels up to full power.

2-22

s

't

1996 Annual Report e

I' The cold neutron source system insertion into the beam port #3, takes advantage of the reflector penetrating port and 16 inch (40.6 cm) diameter access at the reactor shield exit. Operating i tests of the cold source at 250 Kw, 500 Kw, and 950 Kw were f completed in 1994. No unusual operating conditions that relate i to safety of the experiment system have been found. A review of j pressure and temperature data from the TCNS is still in l progress, however, to improve the understanding of the power i performance. A series of tests in 1995 demonstrated the j advantage of an improvement in refrigeration capacity. A l moderate gain in refrigeration capacity was sufficient to extend

indefinitely the stable operating time for the cold neutron

. source. An upgrade of the refrigerator was made in 1997. -j j Other changes to the Texas Cold Neutron Source were the j installation of a focusing element in the facility beam line. A j j number of experiments are still in progress to determine the j alignment and focusing properties of the new element. A prompt l gamma analysis system was installed on the TCNS beam line. ,

e i j Initial use of the prompt gamma analysis system has been with )

I i the cold neutrons from the wave guide but without the additional cooling or presence of the mesitylene moderator.

1

( l I

i 1

!' e l

2-23 4

)

1996 Annual Report

2.6 Publications, Reports, andPapers Reports, publications, and presentations on research done at NETL are produced each year by NETL personnel. The following l list documents research done by NETL faculty, staff, and

students during the reporting period.

i Ph.D.Diamartations

1. Kuo-Pen Cheng, " Measurement and Calculation of Gamma Dose ,

Localization in Gadolinium Neutron Capture therapy," Ph.D. I dissertation, The University of Texas at Austin, December

. 1996.

m Thesis / Reports

1. Brahim Boumakh, " Positron Source Moderator Design:

Computational Models for Positron Diffusion," M.S. Report, The University of Texas at Austin, August 1996.

]

Publications Swnmaries:

1. K On10, and B. W. Wehring, " Nuclear Analytical Techniques

, with Neutron Beams at the University of Texas at Austin,"

l Trans. Am. Nucl. Soc. 2A, 109 (1996).

2. B. W. Wehring, K. On10, A. R. K6ymen, and A. H. Weiss,

" Reactor-Based Slow Positron Beams," Trans. Am. Nucl. Soc.

21, 110 (1996).

i

3. Y.G. Jo, N.M. Abdurrahman, and B.W. Wehring, " Design of a Neutron Radiography Collimator System in a Through Beam Port at the TRIGA Reactor," Trans. Am. Nucl. Soc. 25, 113 (1996).

4. N. M. Abdurrahman, Y. G. Jo, and W. J. Spiesman, " Monte

. Carlo Design Calculations for a Neutron Imaging Facility 1 Collimator," Trans. Am. Nucl. Soc., 74, 112, (1996).

1 Papers

1. F.Y. Iskander. " Assessment of Trace Elements in Honey Produced on Uranium Mining Reclaimed Land." J. Sci Total

]

Environ. 192:119 (1996).

2-24

1996 Annual Report

2. A. J. Teachout, T. L. Bauer, K. On10, B. W. Wehring, "A Case Study in Control of Access to Radiation Beams: Neutron Depth Profiling at the Nuclear Engineering Teaching Laboratory, The i University of Texas'at Austin," American Nuclear Society l Proceedings 1996 Topical Meeting, Radiation Protection and Shielding, Vol.2:888 (1996).

3. J. Y. Kim, K. On10, and B. W. Wehring, " Neutron Focusing i System for Neutron Capture Experiments," The 5th Asian Sypmposium on Research Reactors ( AS RR-V) , May 29-31, 1996, J

Teajon Korea.

4. Y. D. Lee, N. M. Abdurrahman, R. C. Block, and R. E.

Slovacek, " Neutron Emission Tomography for Nuclear Fissile

. Materials Safeguards," Proc. of 5th Int. Conf. on Facility Operations-Safeguards Interface, American Nuclear Society,

. La Grange Park, Illinois, 1996.

5. Y. G. Jo, W. J. Spiesman, and N. M. Abdurrahman,

" Development of a Neutron Imaging Facility at The University of Texas Triga Reactor," Proc. of IEEE Southwest Symposium on Image Analysis and Interpretation, The Institute of Electrical and Electronic Engineering, Piscataway, New Jersey, 1996.

6. N. M. Abdurrahman, B. W. Wehring, T. L. Bauer, Y. G. Jo,

" Development of Neutron Imaging System for Real Time Neutron Radiography and Neutron Computed Tomography at The University of Texas Triga Reactor," Proc. of 5th World Conference on Neutron Radiography, Berlin, 1996.

Prasantations (speaker underlined)

1. H.R. Vega-Carrillo, F.Y. Iskander,, and E. Manzanres-Acuna. " Instrumental neutron activation analysis of plants used with medical purpose." Septimo Congreso Anual de la  !

Sociedad Nuclear Mexicana (Seventh Annual Meeting of the ,

Mexican Nuclear Society), November, 1996 Boca del Rio,  !

Veracruz, Mexico. l

2. F.Y. Iskander, H.R. Vega-Carrillo and E. Manzanres-Acuna.

" Toxic elements in medicinal plants used in folklore medicine." The 52nd Southwest Regional Meeting, American Chemical Society, Houston Texas Oct 1996.

3. K. On10, " Neutron Beam Research at the University of Texas Reactor," Department of Mechanical Engineering, Nuclear Engineering Seminar, February 22, 1996, Austin, Texas.

4. K. Onlu, " Neutron Capture Therapy," Texas A&M University, Department of Nuclear Engineering Seminar, March 20,1996, College Station, Texas.

2-25 l

I

4 l

1996 Annual Report i

i

) 5. K. On10, " Applications of Neutron Beam Techniques for

Materials Research," Department of Mechanical Engineering, Nuclear Engineering Seminar, October 17, 1996, Austin, Texas. i l

6. K. On10, " Nondestructive Determination of Boron Doses in j Semiconductor Materials Using Neutron Depth Profiling,"

(Invited Speaker), Greater Southwest Implant Users' Group Meeting, October 21, 1996, Austin, Texas.

i 7. K Onin, B. W. Wehring, " Nuclear Analytical Techniques with

! Neutron Beams at the University of Texas at Austin," Invited l l* presentation, American Nuclear Society, Annual Meeting, Reno ,

Nevada, June 16-20, 1996. l 4

!* 8. K. On10, B. W. Wehring, T. Z. Hossain, J. K. Lowell, I l' " Nondestructive Determination of Boron Doses in Semiconductor Materials using Neutron Depth Profiling," XI International j Conference on Ion Implantation Technology, Austin Texas, June 16-21, 1996.

9. B. W. Wehrino, K. On10, A. R. K6ymen, and A. H. Weiss, l " Reactor-Based Slow Positron Beams," 1996 Annual Meeting, j American Nuclear Society, Reno, Nevada, June 16 - 20, 1996.

10. K. On10, M. Saglam, B. W. Wehring, T. Z. Hossain, E. Custodio, and J. K. Lowell, " Nondestructive Determination of Boron

} Doses in Semiconductor Materials using Neutron Depth i Profiling," Presented, XI International Conference on Ion l Implantation Technology, June 16-21, 1996, Austin Texas,

! accepted for publication in IEEE Proceedings.

4 11. B. W. Wehring, and K. On10, " Applications of Cold-Neutron Prompt Gamma Activation Analysis at the University of Texas j Reactor," Invited paper, 3rd Topical meeting on Industrial

! Radiation and Radioisotope Measurements and Applications, 1 IRRMA '96, October 6-9, 1996, Raleigh, NC, to be published in Applied Radiation and Isotopes.

B. W. Wehring, K. P. Cheng, and K. On10, 1

12. " Low-LET Dose

' Calculations and Measurements for Gadolinium Neutron Capture

, Therapy," Presented in 3rd Topical meeting on Industrial

Radiation and Radioisotope Measurements and Applications, IRRMA '96, October 6-9, 1996, Raleigh, NC, to be published in Applied Radiation and Isotopes.

13. B. W. Wehring, "The University of Texas Nuclear Research l Reactor and Materials Research," Materials Science and j Engineering Seminar at The University of Texas at Austin, March 27, 1996, Austin, TX.

i 4

i 2-26 i

1996 Annual Report 3.0 FACILITY OPERATING SUMMARIES 3.1 operating Experience The UT-TRIGA reactor at the J.J. Pickle Research Campus became operational during 1992. Operating times remain about i 1

the same for each of the first five years of operation. Total  ;

energy production continues to increase by approximatley the same amount each year. The total burnup after five years of l operation is'11.4 MW-days. A total of 52.2 MW-hours were generated in the fifth year of operation. The reactor was critical for approximately 137 hours0.00159 days <br />0.0381 hours <br />2.265212e-4 weeks <br />5.21285e-5 months <br />. A summary of the burnup history is shown in Figure 3-1.

Burnup History MW Hrs 120 100 80 60 *

• 40 = * *

• 20 * * * *

• I 0 * * *

• 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 Figure 3-1 operating History 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 normal 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.

3-1

i 1996 Annual Report Table 3-1 Protective Action Definitions E g tive Action DescrIntion Safety System Setting Setpoint corresponds to detection of LSSS limiting safety system setting.

Examples:

fuel temperature

= percent power Condition for Hardware action detects inoperable operation conditions within a safety channel or LCo - (analog the instrument control and safety detection) system.

Examples:

pool water level ,

detector high voltage '

external circuit trips Condition for Software action detects inoperable i operation conditions within a program function of I LCo - (digital the instrument control and safety-detection) system.

Examples: l watchdog timers l program database errors Manual Switch operator emergency shutdown (protective action)

Manual Switch operator routine shutdown (intentional operation)

Scrams are further categorized according to the technical

. specification requirement given in Table 3-2. External scrams which provide protection for experiment systems are system

, operable conditions.

The total number of safety system protective actions during 1996 was zero. Of the total protective action shutdowns none were actions of a safety system setting, or actions of a system operable condition (see Table 3-3).

3-2

- - . .- . - _. ... _ ..-..- - . - . ~ . . _- . , . - - .. . - . .__. - . .

1 1

1996 Annual Report 1

i l

! Table 3-2 l Instrumentation, Control and Safety System l Protective Action Events (1) '

Technical Specification Requirement Xsa Hn SCRAM Tyne 1

j Safety System Setpoint (LSSS) 0 0 System Operable Condition (LCO)

Analog detection (hardware) 0 0 .

i Digital detection (software) 0 0 j Manual Switch l

. , Protective action 0 0 Intentional operation (2) _ _

j i

Total Safety System Events 0 0 ,

1

1 (1) Tests of the SCRAM circuits are not recorded 1 (2) Intentional . SCRAMS (non-protective action) are not recorded

, A review is always done to determine if routine corrective l.

actions are sufficient to prevent the recurrence of a particular j reactor safety system shutdown.

i.

i i

i

. Table 3-3 l Summary of Safety System j Protective Actions Trio Action Number of

! occurrences Safety System Setpoint 0 f

• System operable Condition 0 l Total 0 4

1

, 3-3

l 1996 Annual Report i

i

! Previous SCRAM History j Number i of SCRAMS 16 14 l 12 10 l

8

, 4 . . .

2

. 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999

Year 4

4 j Figure 3-2 Summary of All SCRAM Events l

2 i

I 3.3 Utilization i Primary utilization of the reactor during the year was by I 5

NETL staff. Neutron activation analysis represents roughly half the utilization of reactor time and MW-hours with beam port projects representing the other half of reactor use.

Development testing of the Texas Cold Neutron Source (TCNS) continued throughout the year. The basic testing phase of the TCNS was complete in 1994. Analysis continued in 1996 to understand the full power and operating characteristics.

. Development of the beam guides for prompt gamma activation analysis without the refrigerator operating became a major effort for this experiment facility during 1996.

A summary of the reactor utilization for 1996 is presented in Table 3-4 with the monthly distribution shown in Figure 3-3.

Table 3-5 summarizes the sample irradiations and experiments.

Figure 3-4 records the historical trend of sample irradiations.

3-4

1996 Annual Report Table 3-4 Summary of 1996 UT-TRIGA Operation Q1 Q2 03 Q4 Total 5 of " Kev on" Hours ,

- Operator il 33.3 14.2 1.1 0.7 49.3 Operator #2 8.9 11.1 11.8 16.2 48.0

, testing / maintenance 3.2 2.0 34.6 0.0 39.8 Total hours 45.4 27.3 47.6 16.9 137.2 1

MW-Hours Enerav Operator #1 4.3 8.4 0.7 0.5 13.9 l Operator #2 3.6 9.3 10.2 13.3 36.4 testing / maintenance <0.1 <0.1 1.8 0.0 1.8 Total 7.9 17.7 12.8 13.8 52.2 Monthly Burnup Kw Hrs 16000 14000 12000

. 10000 8000 * *

• e 6000 * * *

• 4000 * * * * *

• 2000 * * * * * * * *

• 0 * * * * * * * * *

• JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC Figure 3-3 Operating Data 1995 3-5

- .-. . . - . - . . _ . . . - - ~ . _ . . . . . - . . . - . . . . ~ . . -..-

1 ---.- _-. - - ..- ~ . ....-.- -..-.. 1 j -

1996 Annual Report i

! Table 3-5

] Summary of Utilir.ation 1996 i UT-TRIGA Experiments

Q1 Q2 Q3 Q4 Total i

F l No. of Samnles In-core 52 170 89 93 404

. Ex-core 0 6 5 2 13 i

}

i No. o f F.rne rl man t s Type A 11 7 11 2 31 Type B 4 6 5 4 19 Other 0 1 1 0 2 Total 15 14 17 6 52 Number of Sample Irradiations No. of Samples 500 400 l l

l 300 l

. .200 100

• l

. o . . . . . . . .

JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC Figure 3-4 Operating Data 1996 3-6

j 1996 Annual Report 3.4 Maintenance I Maintenance in 1996 was routine. Replacements were made to several digital components of the reactor control system. The most significant digital system repair for the year was replacement of the Data Acquisition Computer (DAC) disk drive and controller. All changes were made to meet or exceed original manufacturer's specifications. No significant safety considerations were detected during the maintenance activities.

Two non routine control rod drive repairs were done during the year. One repair was replacement of the transient rod down limit switches. A sporadic failure of the indication functions of the rod drive led to replacement of the down limit switches.

The failure did not effect the safety function of the control rod. A shim rod roll pin was replaced after it was found broken. During removal and insertion of the shim control rod the rod exhibited a momentary stuck condition at the near full down position of the rod. Inspection of the control rod and the draw tube found a broken roll pin that could impede the rod movement near the full insertion position. The problem was found and corrected. The safety functions of the rod were still effective although a small loss (<2%) of the reactivity would occur if the rod became stuck. Inspections were subsequently made of all other roll pins in each control rod drive. No other broken pins were found.

A design flaw in the argon-41 monitoring system was found in 1994. The manufacturer of the argon counting system provided a replacement circuit. A test of the replacement circuit was unsuccessful and the circuit was rejected. Final resolution is awaiting response of the manufacturer. An interim replacement counting system continues to provide argon-41 count data until a permanent design for the defective part is available.

3-7

1996 Annual Report 3.5 Facility Changes One significant experiment authorization begun during 1993 is continuing in the test phase. The experiment authorization was for the installation, test and operation of the Texas Cold Neutron Source (TCNS). No unreviewed safety question was found during review of the Safety Analysis Report for the Texas Cold Neutron Source. Several tests of the system were done during 1994 to determine heat removal capabilities of the system.

Tests during 1994 and 1995 determined the effect of nuclear

~

heating on the TCNS heat removal capability. Changes have been made to improve the system. Work, including installation and tests, on the neutron-wave guide system were done throughout 1994 and 1995. Completion of the test program was delayed by a change in goals. A prompt gamma analysis facility has been designed and installed on the neutron wave guide. At present the prompt gamma measurements are being made without operation of the refrigerator and the use of mesitylene to cool the neutrons. Use of colder neutrons from the cold mesitylene source will await the conclusion of the testing of the TCNS.

Progress on the analysis of data continued in 1996. Preparation of the test results in a test analysis report is in progress and should be complete next calendar year.

The main components of the TCNS are a cold source cryostat system and a neutron guide tube system. Components of the cold source cryostat system are a vacuum system, neon gas handling system, and mesitylene moderator. The TCNS was designed to shift the energy of thermal neutrons available at the reactor to subthermal neutrons at an experiment. The process is done by moderating the neutrons at low temperature and transporting the cold neutrons to the experiment. Mesitylene, a room temperature liquid, is frozen to solid form in a chamber to act as the cooling moderator. A neon liquid-gas heat pipe provides cooling of the mesitylene moderator. Both moderator chamber and neon heat pipe are contained in a vacuum system with insulation from thermal heat sources.

3-8

1996 Annual Report The safety problems associated with commonly used moderators such as hydrogen, deuterium or methane are eliminated by using mesitylene, 1,3,5-trimethylbenzene, as a moderator.

The H2, D2, and. methane are gaseous at room temperature, and possible sudden temperature changes may lead to a dangerous pressure buildup in the moderator chamber. Mesitylene is a liquid at room temperature, and is not explosive. It is a hydrogenous material and its nuclear properties are comparable with hydrogen. The radiolysis of mesitylene and stored energy in the moderator chamber and mesitylene have been evaluated.

Possible ozone generation in vacuum chamber, radioactivity of components, and consequences of various system failures have been examined in detail. Also, the operation and the TCNS system's response to safety problems have been considered.

Examples of operating failures are mesitylene transfer system failure, neon handling system failure, loss of refrigeration and loss of vacuum. It was concluded that even with worst-case scenarios, failures will not create a safety issue related to damage to the reactor components or reactor core. Analysis demonstrated no credible accident involving the Texas Cold Neutron Source could cause damage to the reactor beam tube or to the reactor core or cause releases of radioactivity in excess of the limits in 10 CFR 20.

4 3-9

1 1996 Annual Report I

3.6 Laboratory Inspections i

Inspections of laboratory operations are conducted by

university and licensing agency personnel. Two committees, a Radiation Safety Committee and a Nuclear Reactor Committee,

- review operations of the NETL facility. These committees convened at the times listed in Table 3-6.

Table 3-6 committee Meetings l

i Radiation Safety Committee

! Spring Term April 11, 1996 Fall Term November 11, 1996 Nuclear Reactor Committee First Quarter February 6, 1996 Second Quarter April 2, 1996 Third Quarter July 16, 1996 Fourth Quarter none Inspections by licensing agencies include federal license activities by the 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.

Table 3-7 Dates of License Inspections License Dates R-129 none none SNM-180 None LOO 485(48) Sept. 25/27/30, 1996 (1) Site visit by the office for Evaluation and Analysis of Performance Data.

3-10 I I

_ __ ~_ __ _ _ - . . _ - . _ _ _ - . _ _ _ . _ . . - _ _ _ _ _ _ _

4 4

4 1996 Annual Report i

NRC made no inspections during the year. The routine site inspection is one every two years. The previous routine inspection was during 1995.

A State of Texas inspection of the university broad license

! for radioactive materials was conducted Sept. 25, 27 and 30. An a

j inspector from the Texas Department of Health, Bureau of j Radiation Control visited the Nuclear Engineering Teaching i Laboratory for compliance inspection of State licensed areas on j September 27, 1996. The inspector reported that the radiation 4

safety program, as pertains to current authorizations, adequate recordkeeping, and conformance to approved operating e.nd safety )

procedures, appeared to be in compliance with the applicable requirements of the Texas Regulations for the Control of

Radiation and/or Conditions of Registration.

I Routine inspections by the Office of Environmental Health l and Safety (OEHS) for compliance with university safety rules i and procedures are conducted at varying intervals throughout the lm year. In response 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 I significant safety problems were found at NETL, which reflects l

l favorably on the positive safety culture for all hazard classes )

i i at the NETL. Safety concerns included such items as storage of 1

combustibles, compressed gases, and fire extinguisher access.

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] 1996 Annual Report i

l 3.7 Radiation Exposures A radiation protection program for the NETL facility 4

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 shown in the j following tables. Site area measurements include exterior l points adjacent to the building and exterior points away from the building.

Table 3-8 summarizes NETL personnel dose exposure data for j the calendar year. Figure 3-5 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 1 l 3-11 contains a list of the basic Requirements and Frequencies i of measurements.

i Additional measurement data is available from the State of 4 Texas Department of Health. The state agency records environmental radiological exposures at five sites in the j vicinity of the research reactor site. Samples are also taken

for analysis of soil, vegetation, and sanitary waste effluents.

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1996 Annual Report ,

e Table 3-8 Annual Summary of Personnel Radiation Doses Received Within the NETL Reactor Facility 1

l Averaae Annual Dose (1) (mrem) l Personnel Students Visitors (5)

Whole Body,DDE(2) 1.7 0.3 0 (M)

Extremities,SDE(3) l ,

1.7 0.3 N/A (M)

Lens of eye,LDE(4) 5 0.3 N/A (M)

I ,

Greatent Tnd{vidual Dose (mrem) i Personnel Students Visitors (5) j Whole Body,DDE 10 2 0 (M)

Extremities,SDE

10 2 N/A (M) i Lens of eye,LDE l 30 2 N/A (M)

Total Person-mrem for Groug Personnel Students Visitors (5)

Whole Body,DDE 10 2 0 (M)

Extremities,SDE 10 2 N/A (M)

Lens of eye,LDE 30 2 N/A (M)

Notes to Table 3-9 (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, 20 mrem for fast neutrons. "N/A" indicates that there was no extremity i monitoring conducted or required for the group. l (2) DDE applies to external whole-body exposure and is the dose equivalent at a tissue depth of I cm (1000 mg/cm 2),

(3) SDE applies to skin or extremity external exposure, and is the dose equivalent at a tissue depth of 0.007 cm (7 mg/cm2 ) averaged over an area of 1 cm 2, (4) 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 (300 mg/cm2 3, (5) Pocket ionization chambers (PICS) are issued to persons who enter radioactive materials / restricted areas for periods of short duration, i.e., a few hours or days annually. A total of l 226 issuance cards were filled out, and none recorded a postive  ;

dose value.

3-13 l 1

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1996 Annual Report ACCESS ROAD L J PARKING e 1

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5 PARKitG 4 1 Sidewalk, NETL facility front entrance 2 Reacter bay esterior wall, east 3 meector boy enterior well, weet 4 NETL power transformer 5 NETL service door 6 NETL roof stack

• Indicates location of dosientry within the building Figure 3-5 Environmental TLD Locations 3-14

1996 Annual Report l

l l

Table 3-9 Total Dose Equivalent Recorded on Area Dosimeters Located Within the NETL Reactor Facility l

Location in Reactor Facility Monitor -Total Dose (1,2) (mrem)

In S. Y. X n Deep (3) Shallow (4) l l

Reactor Bay, North Wall 00167 M M M l Reactor Bay, East Wall 00168 M M 'M l Reactor Bay, West Wall 00169 1640 1660 M l Water Treatment Room 00170 960 960 M

.' Reactor Pool Area, Roof 00171 M M M Shield Area, Room 1.102 00172 M M M l Sample Processing, Room 3.102 00173 M M n/a l Gamma Spectroscopy Lab, 3.112 00174 10 10 n/a Radiation Experiment Lab, 3.106 00175 M M' n/a Reception Area, 2.102 00176 M M n/a (1) The total recorded dose equivalent values reported in mrom do no 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 measurable quantity of 10 mrem for x- and gamma rays, 40 mrem for energetic betas, 20 mrem for fast neutrons, and 10 mrem for thermal neutrons. "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 wall directly into an unrestricted I 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 (1,000 mg/cm )2 ,

(4) Shallow indicates shallow dose equivalent, and applies to the external exposure of the skin or an extremity, and is taken as the dose equivalent at a tissue depth of 0.007 cm (7 mg/cm 2)

, averaged over an area of one square centimeter.

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, 1996 Annual Report i

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v Table 3-10 Total Dose Equivalent Recorded on TLD Environmental Monitors

Around the NETL Reactor Facility Location in Reactor Facility. Monitor Total IIL h (1)(mrem)

Sidewalk, NETL front entrance 00156 M

', NETL power transformer 00157 M NETL Roof stack 00158 M Reactor bay exterior wall, east 00159 M  ;

Reactor bay exterior wall, west 00160 M , i NETL service door 00161 M (1) The total recorded dose equivalent values do not include natural background contribution and reflect the summation of the results of four quarterly TLD dosimeters for each locations. A total dose equivalent of "M" indicates that each of the dosimeters during the r period was below the vendor's minimum measurable quantity of 10 mrem for x- and gamma rays, 40 mrem for energetic beta particles.

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1996 Annual Report ,

l Table 3-11 Radiation Protection Program Requirements and Frequencies Frecuency Radiation Protection Recuirement 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.

e Neutron survey of the reactor bay (during reactor operation).

Monthly Gamma survey of exterior walls and roof.

Neutron survey of exterior walls and roof.

a Swipe survey of roof.

Exchange personnel dosimeters and interior area monitoring dosimeters.

Review dosimetry reports.

j 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 Process and record solid wastes and liquid effluent Required discharges.

l 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 survey of all non restricted areas.

Swipe survey of all non restricted areas.

Swipe survey of building exterior areas.

Calibrate personnel pocket dosimeters.

Perform Chi-square test, and determine IN plateaus and detection efficiencies on the low background alpha / beta countino system.

Semi- Inventory emergency locker.

Annual Calibrate portable radiation monitoring instruments.

Calibrate continuous air monitor, argon monitor, and area radiation monitors.

• Leak test and inventory sealed sources.

Annual Conduct AIARA Committee meeting.

Conduct personnel refresher training.

Calibrate emergency locker portable radiation detection equipment 3-17

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1996 Annual Report i

! 3.8 Radiation Surveys Radiation surveys of NETL work areas are shown.in Table 3-12. Surveys with portable instruments and measurements of f radioactive contamination are routine. Supplemental l measurements are also made any time unusual conditions occur.

j Values in the table represent the result of routine

} measurements. Environmental monitoring at sample sites exterior 4

to the building-are generally done at random times or as a case i by case evaluation.

Table 3-12 Annual Summary of Radiation Levels and Contamination Levels Within the Reactor Area and NETL Facility Accessible Location Whole Body Contamination Radiation Levels Levels 1

'(mrem /hr)(1) (dpm/100cm 2) l Average Maximum Average Maximum TRIGA Reactor Facility Reactor Bay North 0.37 4.5' 37.3 360.0 Reactor Bay South 0.013 3.8 MDA (2) MDA (2)

Reactor Bay East 0.04 0.14 spa (2) 56.4 Reactor Bay West 0.12 1.5 6.4 10.7 Reactor Pool Deck 0.025 3.6 12.4 530(3)

(third floor)

NETL Facility NAA Sample Processing 0.06 0.8 15.9 355.0 (Rm 3.102 NAA Sample Counting 0.02 0.8- 2.7 3.1 (Rm 3.112)

Health Physics 0.01 0.023 McA(2) MDA (2)

Laboratory Neutron Generator 0.2 2.3 upA(2) 11.5 (Rm 1.102)

Waste Storage (Rm 1.108) ..

(1) Measurements made with a Eicron Microrem portable survey meter in areas readily accessible to personnel.

(2) MDA for the G-5000 low level alpha-beta radiation counting system is 2.49 dpm/100 cm2 beta, and 0.58 dpm/100 cm 2 alpha. calculation of MDA based on NCRP Report No.

58.

(3) The contamination shown for this location assumes 100% smearing efficiency, and was immediately removed. As result, the average contamination level at this location during the reporting period was, for all practical purposes, <500 dpm per 100 cm 2, 3-18

1996 Annual Report 3.9 Radioactive Effluents, Radioactive Waste Radioactive effluents are releases to the air and to the sanitary sewer system. The most significant effluent is an airborne radionuclide, argon-41. Two 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.

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' Table 3-13 Monthly Summary of Argon-41 Effluent Releases (l)

Date of Discharge Total Quantity of Average Fraction of (Month, 1994) Argon-41 Release Concentration at Technical i (microCuries) Point of Release Specifications (2) )

(microcurie /cm3) (%) l January 4190 4.16E-10 0.02 February 63900 6.34E-09 0.32 March 32300 3.20E-09 0.16 l April 73300 7.27E-09 0.36 May 130000 1.29E-08 0.64 June 40100 3.98E-09 0.20 July 96300 9.55E-09 0.48 August 1.42 1.41E-13 <0.01 September 106000 1.05E-08 0.53 october 39300 3.90E-09 0.20 November 104000 1.03E-08 0.51

- December 0 0 0.00 ANNUAL VALUE 689391.42 5.60E-09 0.28 I

i i

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

(2) Technical Specification limit for continuous release is 2.00E-6 microcurie /cm 3, i

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1996 Annual Report 1 Releases to the sanitary sewer are done from waste hold up 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 forms prior to disposal. Liquid disposals are infrequent. -

l Table 3-14 Monthly Sumary of Liquid Effluent Releases to the l Sanitary Sewer From the NETL Reactor Facility Date of Release Total Quantity

-Discharge Volume of Radioactivity (Month, 1996) (m3 ) (Curies) 1 January No Releases February No Releases March No Releases April No Releases May No Releases June No Releases July No Releases August No Releases September No Releases october No Releases November No Releases December No Releases t

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1996 Annual Report Radioactive waste disposal of solids are shown in Table 3-15. The inventory of material in Table 3-15 represents the disposal of radioactive material as follows: March 1996, i NAA sample vials and no longer serviceable RSR rabbits; August 1996, 7 old tritium targets; September 1996, environmental samples (soil) containing small amounts of 90-Sr and 241-Am; December 1996, disposal of 2 x-ray flourescence sources that had been transferred from Petroleum Engineering (Chenevert) with

'unservicable support equipment. The total activity sent to disposal was 21 Ci. All transfers of material were made to the University Office of Environmental Health and Safety for disposal.

Table 3-15 Monthly Summary of solid Waste Transfers for Disposal r

Date of Release Total Quantity Discharge Volume of Radioactivity (Month, 1995) (m3 ) (millicuries)

January No Releases February No Releases.

March 0.2 7 April No Releases May No Releases June No Releases July No Releases August 0.06 21,046

. September 0.02 4.4E-05 october No Releases November 3.5 December 0.303 29.0 3-21