ML20081K103

Annual Rept 1994 Nuclear Engineering Teaching Lab Jj Pickle Research Campus Univ of Tx at Austin

ML20081K103
Person / Time
Site:	University of Texas at Austin
Issue date:	12/31/1994
From:	Bauer T TEXAS, UNIV. OF, AUSTIN, TX
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9503280400
Download: ML20081K103 (66)

Text

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. . ' DEPARTMENT OF MECHANICAL. ENGINEERING

! y THE UNIVERSITY OF TEXAS AT AUSTIN 'I

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% y Nuclear Engineering Teaching Laboratory - (512) 471-5787 FAX (512) 471-4589

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I March 23,1995  !

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Nudear Regulatory Conunission j Document Control Desk j Washington, DC 20555 'l

Subject:

Docket 5-602 q AnnualReport 1994 j

Dear Sir:

i A report is endosed for the R-129 license activities of The University of Texas at ,

Austin. The report covers the activities during the 1994 calendar year.

i i

Sincerely,  !

Mu2hw f Thomas L. Bauer i

~ Assistant Director, f Nudear Engineering Teaching Laboratory  !

i endosure: 1994 AnnualReport  !

l cc: Region IV w/endosure I copy l A. Adams w/ enclosure 1 copy j B. Wehring w/endosure 1 copy D. Klein w/endosure I copy i

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Street Addresr 10100 Burnet Road Austin, Texas 78758 MailAddrns: Balconn Rnearch Center Bldg.159 Austin. T - 3 78712 9503280400 941231 PDR ADOCK 05000602 R PDR

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r1 h Annual Report 1994 Nuclear Engineering Teaching  !

Laboratory e

J.J. Pickle Research Campus The University of Texas at Austin i

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• l 4- l Table of Contents l

Tables of Contents 11 List of Figures _iii List of 'lables iv l Executive Summary v  ;

1.0 Nuclear Engineering Teaching Laboratory 1-1 1.1 Introduction 1-1 Purpose of Report Availability of Facility  :

Operating Regulations NETL History .

1.2 NETL Building 1-4  ;

J.J. Pickle Research Campus NETL Building Description l Laboratories, Equipment  ;

1.3 UT-TRIGA Mark II Research Reactor 1-8 Reactor Description  !

Experiment Facilities Beam Port Facilities 1.4 Nuclear Engineering Academic Program 1-13 1.5 NETL Divisions 1-14 Reactor Maintenance & Operation Nuclear Analytical Services

• Neutron Beam Projects 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  ;

2.3 Service and Commercial Activities 2-7  !

2.4 Research and Development Projects 2-9 t 2.5 Significant Modifications 2-16 l 2.6 Publications, Reports & Papers 2-18 3.0 Facility Operating Summaries 3-1 3.1 Operating Experience 3-1  !

3.2 Reactor Shutdowns 3-1 i 3.3 Utilization 3-4 t 3.4 Maintenance 3-7 -

3.5 Facility Changes 3-7  :

3.6 Laboratory Inspections 3-9 3.7 Radiation Exposures 3-10 3.8 Radiation Surveys 3-16 3.9 Radioactive Effluents, Waste Disposal 3-17  !

11  ;

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List of Figures '

Figure- ,

~ 1-1 NETL - Nuclear Engineering Teaching Laboratory 1-1 1-2 NETL Site - J.J. Pickle Research Campus 1-4  !

t 1-3 NETL Building - Profile 1-5 i 1-4 NETL' Building - Layout 1-6 7-5 TRIGA Reactor Core 1-8  ;

1-6 Reactor Pool and Beam Ports 1-10 1-8 NETL Staff Organization 1-15 2-1 NETL Administrative Structure 2-1  !

3-1 Operating History 3-1 l 3-2 Summary of All SCRAM Events 3-4'  ;

3-3 Operating Data 1994 - Monthly Burnup 3-5 3-4 Opereting Data 1994 - No. of Sample Irradiations 3-6 l 3-5 Location of Environmental TLD's 3-13 i f

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-.- l List of Tables Table 1-1 Physical Dimensions of Standard Experiment Systems 1-11 ,

1-2 Physical Dimensions of Standard Beam Ports 1-13 1-3 Nuclear Engineering Courses using NETL 1-14 1-4 Health Physics Survey Equipment 1-19  ;

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

2-2 The University of Texas at Austin Administration l 2-2 2-3 UT Radiation Safety Committee 2-3 2-4 UT Nuclear Reactor Committee 2-3 .;

2-5 NETL - Personnel 2-4 2-6 Supplemental Funds 2-5 2-7 Public Access 2-6 3-1 Protective Action Definitions 3-2 3-2 ICS System Protective Action Events 3-3 j 3-3 Summary of Safety System Protective Actions 3-3 3-4 Summary of Utilization 1994 - UT TRIGA Operation 3-5 3-5 Summary of Utilization 1994 - UT TRIGA Experiments 3-6 3-6 Committee Meetings 3-9 i 3-7 Dates of License Inspections 3-9 3-8 Annual Summary of Personnel Radiation Doses 3-10 '

3-9 Radiation Protection Requirements and Frequencies 3-12  :

3-10 Total Dose Equivalent Recorded on Area Dosimeters Located Within the NETL Reactor Facility 3-14 .;

3-11-Total Dose Equivalent on TLD Monitors Around the NETL Reactor Facility 3-15  ;

3-12 Annual Summary of Radiation Levels and Contamination Levels During Routine Radiation Surveys 3-16 3-13 Monthly Summary of Gaseous Effluent Releases to the Atmosphere 3-17 3-14 Monthly Summary of Liquid Effluent Releases to the Sanitary Sewer 3-18 '

3-15 Annual Summary of Solid Waste Generated and

. Transferred 3-18 iv

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

1. preserve, disseminate, and create knowledge,

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. .

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.

i 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 work by students in non-nuclear fields such as physics, chemistry, and biology. It may also be used in education programs for nuclear power plant personnel, secondary schools students and teachers, and the general public.

The UT-TRIGA research reactor provides opportunities to do research in nuclear science and engineering. It can also contribute to multidisiplinary studies in medicine, epidemiology, environmental sciences, geology, archeo]pgy, paleontology, etc.

Research reactors, one megawatt and larger, constitute unique and essential research tools for examining the structure of crystals, magnetic materials, polymers, biological molecules, etc.

v

The UT-TRIGA research reactor benefits a wide range of on-campus and cff-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 applications of nuclear science, and earn revenues to  !

help support Nuclear Engineering activities.

Bernard W. Wehring, Director Nuclear Engineering Teaching Laboratory i

i i

vi l

. 1994 Annual Report 1.0 NUCLEAR ENGINEERING TEACHING LABORATORY 1.1 Introduction Purnose of the Renort 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 l introduction to the education, research, and service programs of the NETL. A TRIGA nuclear reactor is the major experimental ,

facility at the Laboratory. The reactor operates at power levels up to 1100 kilowatts or with pulse reactivity insertions j up to 2.2% Ak/k.

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@Yk Figure 1-1 NETL - Nuclear Engineering Teaching Laboratory The annual reports also satisfy requirements of the University Flel Assistance Program, U.S. Department of Energy (DOE) [ contract number DE-AC07-ER03929, Amendment A015), and the licensing agency, the U.S. Nuclear Regulatory Commission (NRC)

[ docket number 50-602]. This annual report covers the period from January 1, 1994 to December 31, 1994.

1-1

4 1994 Annual Report l

1 Availability of the Facility i l

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

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

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other laboratories for the testing and evaluation of materials. .

Public education through tours and demonstrations is also a f routine function of the laboratory operation. i i

Operating Regulations Licensing of activities at NETL involve both Federal and j State agencies. The nuclear reactor is subject to the terms and f

specifications of R-129 a class 104c research reactor license.  !

Another license, SNM-180, for special nuclear material provides j for the use of a subcritical assembly with neutron sources.

l Both licenses are responsibilities of the NETL. For general use -l of radioisotopes the university maintains a broad license with the State of Texas, L00485. Functions of the broad license are f the responsibility of the University Safety Office. f NETL Historv -

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Development of the nuclear engineering program was an i effort of both physics and engineering faculty during the late f

1950's and early 1960's. The program became part of the Mechanical Engineering Department where it remains. The program f installed, operated, and dismantled a TRIGA nuclear reactor at a j site on the main campus in the engineering building, Taylor i Hall. Operating requirements were intermittent from 1963 to 1988, accumulating a total burnup of 26.1 megawatt-days. [

Reactor initial criticality was August 1963 with the final operation in April 1988. Power at startup was 10 kilowatts (1963) with one power upgrade to 250 kilowatts (1968). Pulse l capability of the reactor was 1.4% Ak/k with a total of 476  :

pulses during the operating history. Dismantlement and 1

1-2 i i

1994 Annual Rsport {

decommissioning of the facility were completed in December 1992. ,

I Planning for a new facility, which Jed to the shutdown of the campus facility,. began in October 1983, with construction f taking from December 1986 to May 1989.

The final licensing was  ;

I issued January 1992 with initial criticality occurring March r

1992. The new facility, including support laboratories,- l administrative offices and the reactor is the central location  !

for all NETL activities. f Land use in the area of the NETL site began as an l industrial site during the 1940's. Following the 1950's, lease

-l agreements between the University and the Federal government led j to the creation of the Balcones Research Crater. In the 1990's, the University became owner of the site, and in 1994 the site l name was changed to the J.J. Pickle Research Campus. j i

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.. 1994 Annual R: port 1.2 NETL Building 1J. Pickle Research Camnus The J.J. Pickle Research Campus (PRC) is a multidiscipline research campus on 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 i 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, j recreation areas, meeting rooms, and conference facilities.

Access to the NETL site is shown in Figure 1-2.

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. 1994 Annual Report I

NETL Buildine Descriotion 1

The NETL building is a 1950 sq meter (21,000 sq ft), l facility with laboratory and office areas. Building areas ,

consist of two primary laboratories of 330 sq m (3600 sq ft) and 80 sq m (900 sq ft), 8 support laboratories (217 sq m, 2340 sq l ft), and 6 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 and shield structure including neutron i beam experiment areas. A second primary laboratory consists of l

1.3 meter (4.25 ft) thick walls for use as a general purpose l

radiation experiment facility. Other areas of the building ,

include support shops, instrument laboratories, measurement '

1 laboratories, and material handling laboratories. Figure 1-3 l and 1-4 show the building and floor layouts for office and l i

laboratory areas. '

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1994'Annun1 Report Inhoratories. Eauloment

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The NETL facility makes available several types of  !

radiation facilities and an array of radiation detection  :

equipment. Besides.the reactor, facilities include a-  !

subcritical assembly, a gamma irradiator, miscellaneous -

radioisotope sources and one or more radiation producing machines. ,

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

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

cesium-137, and radium-226 are available in millicurie [

quantities. i Neutron sources of plutonium-beryllium and californium-252 ,

i are available. A subcritical assembly of 20% enriched uranium in a polyethylene moderated cylinder provides an experiment ,

device for laboratory demonstrations of neutron multiplication j and neutron flux measurements. l Radiation producing equipment such as x-ray units for radiography and density measurements are available as both fixed

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

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1.3 UT-TRIGA MARK II Research Reactor The TRIGA Mark II nuclear reactor at the Nuclear Engineering Teaching Laboratory of The University of Texas at l Austin is an above-ground fixed-core research reactor. The ,

nuclear core, containing uranium fuel, is located at the bottom of a 8.2 meter deep water-filled tank surrounded by a concrete i 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 possible at all times. The TRIGA Mark II reactor is a versatile and inherently safe research reactor conceived and developed by l General Atomics to meet requirements for education and research.

The UT-TRIGA research reactor provides sufficient power and  ;

neutron flux for comprehensive and productive work in man; ,

) fields including physics, chemistry, engineering, mediciae, and l

, metallurgy. The word TRIGA stands for Training, Research, Isotope production, and General Atomics. Figure 1-5 is a a picture of the reactor core structure. i i

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Reactor Descr& tion Reactordneration. The UT-TRIGA research reactor can operate

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continuously at nominal powers of up to 1 MW or in the pulsing mode where typical peak powers of 1500 MW can be achieved for short times of about 10 msec. The UT-TRIGA with its new digital control system provides a unique facility for performing reactor  :

I physics experimente and reactor operator training. The pulsing operation is particularly useful in the study of reactor kinetics and control. Neutrons produced in the reactor core can be used in a wide variety of research applications including nuclear reaction studies, neutron scattering experiments, and nuclear analytical and irradiation services. l.

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 1 neutron beam ports, allow neutrons to stream out away from the l core. Experiments can be done inside the beam ports or outside the concrete shield in the neutron beams.

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Nuclear Core. The reactor core is an assembly of about 90 fuel l 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 rises to high powers are automatically suppressed without using mechanical control; the reactor quickly returns to normal power levels. Pulse operation j which is a normal mode of operation is a continual demonstration j of this inherent safety feature.

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l 1-9

.- 1994 Annual Report "

ReactorControl 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  :

t power level of the UT-TRIGA is controlled by four control rods.

Three of these rods, one regulating and two shim, are sealed l

stainless steel tubes containing powdered boron carbide followed by UZrH. As these rods are withdrawn, boron (neutron absorber) leaves the core and UZrH (fuel) enters the core, increasing power. The fourth control rod, the 1.ransient 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 immediate I burst of power. l i

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1994 Annual Report  !

t Frneriment Facilities  ;

The experimental and irradiation facilities of the TRIGA  !

Mark II reactor are extensive and versatile. Experimental tubes can easily be installed in the core region to provide facilities for high-level irradiations or small in-core experiments. Areas outside the core and reflector are available for large experiment equipment or facilities. Table 1-1 lists the I workable experiment volumes available in the standard experiment f I

facilities.

I Table 1-1 ,

Physical Dimensions of Standard Experiment Systems t Center Tube  ;

Length: 15.0 in. 38.1 cm ,

Tube oD: 1.5 in. 3.81 cm Tube ID: 1.33 in. 3.88 cm i Rotary Rack f Length: 10.8 in. 27.4 cm '!

Diameter: 1.23 in. 3.18 cm i Pneumatic Tube .

Length: 4.5 in. 11.4 cm ,

Diameter: 0.68 in. 1.7 cm l i

The reactor is equipped with a central thimble for access  ;

to the point of maximum flux in the core. The central thimble  !;

consists of an aluminum tube that fits through the center hole  ;

of the top and bottom grid plates. Experiments with the central [

thimble include irradiation of small samples and the exposure of k materials to a collimated beam of neutrons or gamma rays. j A rotary multiple-position specimen rack located in a well in the top of the graphite reflector provides for batch f;

production of radioisotopes and for the activation and irradiation of multiple samples. All forty positions in the f rack when rotated are exposed to neutron fluxes of the same  !

intensity. Samples are loaded from the top of the reactor j 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.

i 1-11  ;

4 1994 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 can 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 being used, 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 (BP) #1 is connected to BP #5, end to end, to form a through beam port. The through beam port penetrates the graphite reflector tangential to the reactor core. See Fig.

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 relatively low fast-neutron and gamma-ray contamination.

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 providing a thermal neutron beam with minimum fast-neutron and gamma-ray backgrounds.

Beam Port #3 is a radial beam port, pierces the graphite reflector, and terminates at the inner edge of the reflector.

This beam port permits access to a position adjacent to the 1-12

. i 1994 Annual Report reactor core and can provide a neutron beam with relatively high  !

fast-neutron and gamma-ray fluxes. [

Beam Port #4 is a radial beam port also terminating at the  !

outer edge of the reflector. A void in the graphite reflector  !

extends the effective source of neutrons to the reactor core.  !

I This configuration is useful for neutron-beam experiments requiring neutron energies higher than thermal energies.

A neutron beam coming from a beam port can be modified by  !

using a collimator and/or neutron filter. Collimators are used to limit beam size and/or beam divergence. Filters allow ,

neutrons in selected energy intervals to pass through while  ;

attenuating neutrons with other energies. .

i' Table 1-2 Physical Dimensions of Standard Beam Ports ,

Beam Port Port Diameter BP f l, BPf2, BPf4 {

At Core: 6 in. 15.24 cm  ;

At Exit: 8 in. 20.32 cm BP #3, BPf5 At Core: 6 in. 15.24 cm At Exit: 8 in. 20.32 cm i 10 in. 25.40 cm l 16 in. 40.64 cm  !

i 1.4 Nuclear Engineering Academic Program 4 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 of Science in Mechanical Engineering, Nuclear Engineering Option. It is best described as a major in Mechanical Engineering with a minor in Nuclear Engineering. As such, all Mechanical Engineering degree requirements must be met.

1-13

e 1994 Annual Report Tha Program's graduate degrees are completely autonomous; they ara Master of Science in Engineering (Concentration in Nuclear Engineering) and Doctor of Philosophy (Concentration in Nuclear Engineering). Course requirements for these degrees and the qualifying examination for the Ph.D. are separate and distinct from other areas of Mechanical Engineering. A Dissertation Proposal and Defense of Dissertation are also required for the Ph.D. degree and are acted on by an NE dissertation committee.

Of the five undergraduate Nuclear Engineering courses and the dozen graduate Nuclear Engineering cours'es, five make extensive use of the reactor facility. h hle 1-3 lists the courses that use the reactor and its experiment t'acilities.

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 is under the Department of Mechanical Engineering at The University of Texas.

The attached figure shows the staff organization of 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.

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

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, 1994 Annual R port units, and the NETL computer system. Activities of OMD include neutron and gamma irradiation service, operator / engineering training courses, and giving reactor short courses.

l Director l l

Clerical Staff I

Health Physicist Assistant Director I I operations Beam Port Nuclear and Projects Analytical Maintenance services Figure 1-8 NETL Staff organization The Nuclear Analytical Services Division (NAS) is responsible for providing, in a safe and effective manner, analytical services such as Neutron Activation Analysis, low level radiation counting, and isotope production. Other service activities of NAS include teaching NAA short courses.

The Neutron Beam Projects Division (NBP) is responsible for 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.

Operation and Maintenance Division The primary purpose of the Operation and Maintenance Division is the routine maintenance and safe operation of the TRIGA Mark II Research Reactor. This division performs most of the work necessary to meet Technical Specifications of the reactor license. Work by the division implements modifications to reactor systems and furnishes design assistance for new 1-15

i 1994 Annual Report experiment systems. The division operates standard reactor f experiment facilities.

Other activities of the division include operation and maintenance of radioisotope irradiators, such as'the cobalt-60 f I

irradiator, and radiation producing equipment. Radiation producing equipment consists of a 14-MeV neutron generator, and -

industrial x-ray machines.  :

Services provided to other divisions at the laboratory l

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include assistance in the areas of initial experiment design, fabrication, and setup. Maintenance and repair support for computer, electronic, and mechanical equipment is provided. [

Coordination of building systems maintenance is also coordinated ,

by the Operation and Maintenance Division.

Nuclear Analytical Service Division The main objectives of the nuclear analytical services division include services and education. In the area of services, the division serves the university at large. -

Elemental measurements using instrumental neutron activation f analysis to provide nuclear analytical support for individual f

projects range 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 l innovative research projects. Similar services have been made  !

available to different state agencies in order to assist with  ;

quality control of sample measurements and evaluation of i environmental effects of some toxic elements. In the area of education, the division, with available state-of-the-art )

equipment, helps stimulate the interest of students about areas l of science and engineering. Education in the irradiation and i 1

measurement of radioactivity is presented to college, high j school and other student groups in class demonstrations or on a one-on-one basis.

1-16

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1994 Annual Report  !

t Radiation measurement systems available include several j high purity germanium detectors with relative efficiencies ranging from 20 to 40%. The detectors are coupled to a l Vaxstation 3100. Two of the detectors are equipped with an [

automatic sample changer for full-time (i.e., 24 hrs a day)  :

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 l and to any user with proper authorization, a modem and the {

necessary communication software. However, safeguards by i special protocols guard against any unauthorized access.

t Neutran Beam Projects Division The Neutron Beam Projects Division manages the use of the i

five beam ports. Experiments at the beam ports may be permanent j systems that will function for periods in excess of 1 or 2 years j or temporary systems. Temporary systems function once or for a l few months, generally requiring removal and replacement as part f'

of the setup and shutdown process. The reactor bay contains floor space for each of the beam ports with available beam paths l ranging from 6 meters (20 ft) to 12 meters (40 ft) .  !

The main objective of the Neutron Beam Projects division is to develop and operate experimental research projects associated with neutron beams. The objectives of the research function are i

to apply nuclear methods at the forefront of modern technology and to investigate fundamental issues related to nuclear physics  ;

and condensed matter. Another mission of the division is to lr create new funded research programs promoting the capabilities of the neutron beam projects division to academic, government l and indostrial organizations and/or groups.  !

The Neutron Beam Projects manager assists with all phases

[

of a project, beginning with the proposal, design, proceeding to j the fabrication, test, and concluding with the operation, l evaluation and dismantlement. Projects available at NETL are  !

both traditional, such as neutron radiography, and unique, such !L as the Texas Cold Neutron Source facility. Two nuclear

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1994 Annual Report- l diagnostic techniques, neutron depth profiling (NDP) and prompt gamma activation analysis (PGAA) are examples of neutron beam activities.  !

i Health Physics Groun The Health Physics group is responsible for radiation j safety and protecticn of personnel at the NETL as well as protecting the general public. The laws set down by Federal and i State government are maintained and enforced at the facility by  !

various means. Health Physics procedures have been developed l that are facility specific to ensure that operation complies with all facets of the regulations. Periodic monitoring for radiation and contamination ensures that the use of the reactor (

and radioactive nuclides is conducted safely with no hazard to  !

personnel outside of the facility. Personnel exposures are at  !

all times main: 'ined ALARA ("as low as is reasonably l achievable") consistent with the mission of the NETL.  !

Collateral duties of the Health Physics group include inventory  !

and monitoring of hazardous materials, and environmental health,

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f The Health Physics group consists of one full time Health Physicist. The Health Physicist is functionally responsible to  !

i the Director of the NETL, but maintains a reporting relationship i to the University Radiation Safety Office. This arrangement '

allows the Health Physicist to operate independent of NETL operations constraints to ensure that safety is not compromised.

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

the Health Physicist. The URA reports to the Health Physicist I

and assists with technical tasks including periodic surveys, equipment maintenance, equipment calibration, and record  !

keeping. ,

The equipment currently in use by the Health Physics group l I

is presented in Table 1-4. Other health physics equipment and supplies such as plastic bags, rubber gloves, radiation control ,

signs / ropes are kept available for immediate use. l l

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1994 Annual-Report j i

Table 1-4 l Health Physics Survey Equipment Ecru I rwnant Radlation R j High and low range l self-reading pocket  !

dosimeters gamma >10 l Thin window friskers alpha / beta /gama >8 l scintillation micro  ;

remmeter low level gamma 1 High range portable ,

ion chamber beta /gama 1  !

BF3 proportional counter neutron 2 {

Hand and Foot monitor beta 1 i Low level gas-flow  !

proportional counter alpha / beta 1 ,

continuous air particulate (

monitor alpha / beta 1  !

Gaseous Ar-41 effluent monitor beta 1 i

.i The Health Physics Group provides radiation monitoring, j personnel exposures, and educational activities. Personnel who l are issued permanent dosimeters are required to attend an eight f

hour course given by the Health Physicist. This course covers ,

basic radiation principles and facility specific procedures and  !

rules. Each trainee is given a guided tour of the facility to  !

familiarize him with emergency equipment and procedures. The group supports University educational activities by assisting i with student experiments and projects by demonstrating proper i radiation work techniques and controls to the students. The j Health Physics group participates in emergency planning between  !

NETL and the City of Austin to provide basic response requirements and radiation training to emergency personnel such l

as Fire and EMS crews. l I

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l 1994 Annual Rsport j I

2.0 ANNUAL PROGRESS REPORT f i

2.1 Faculty, Staff, and Students  !

Organimrinn. The University administrative structure overseeing the NETL program is presented in Figure 2-1. A I description follows, including titles and names of personnel, of f the administration and committees that set policy important to .

NETL. i t

i 1

President l University of Texas  !

at Austin  !

l E

Radiation i Safety '

Committee 7 Executive Vice r President and Provost  !

l  :

Dean i College of Engineering Nuclear Reactor Conunittee l Chairman l Department of Mechanical Engineering  ;

I .

Director Nuclear Engineering l Teaching Laboratory l Figure 2 University Administrative Structure over NETL AdminIrrration. 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 Er i neering consists of six engineering departments with separate o%g.e programs. NETL is one of several education and research functions within the college.

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n h :*- 1994 Annual R: port.

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 i Austin. l

)

1 Table 2-1  ;

The University of Texas System Board of Regents Chairman B. Rapaport (

Vice Chairman E.C. Temple  ;

Vice Chairman L.H. Lebermann, Jr. l Executive Secretary A.H. Dilly Chancellor William Cunningham f L

Member 1995 Member 1997 Member 1999 R.J. Cruikshank Z.W. Homes, Jr. T.o. Hicks  !

T. Loeffler B. Rapaport L.H. Lebermann i M.E. Ramirez E.C. Temple M.E. Smiley [

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I Table 2-2 l The University of Texas at Austin  !

Administration {

l' President Robert Berdahl Executive Vice President and Provost Gerhard Fonken 1993-94 ,

Mark Yudof 1994-95 j i

Dean of College of Engineering Herbert Woodson l Chairman of Department of Mechanical Engineering Kenneth Diller 2-2 j

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Radiarinn Kafety Comminre. The Radiation Safety Committee convenes to review radiological safety practices at the University during each academic term. The committee composition-l is shown in Table 2-3. Committee general responsibilities are  !

review of activities of University research programs that l utilize radiation source materials. l I

i Table 2-3 l Radiation Safety Committee  !

l Chairman E.L. Sutton  !

Member B.G. Cook Member M.A. Fox l Member G. Hoffmann Member D.E. Klein Member S.A. Monti l Member B.W. Wehring  !

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

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Nuclear Reactor Committee. The Nuclear Reactor Committee convenes  !

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

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l Table 2-4 l Nuclear Reactor Committee [

Chairman R. Charbeneau -

Member D. Blackstock li Student Member R. Canaan Member D.E. Klein  !

Member S. Morriss (1994-95) l Member J. Reis (1993-94) (

Member B.W. Wehring Ex officio member T.L. Bauer ,

Ex officio member J. White Ex officio member K. Diller  !

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1994 Annual Report l Personnel. NETL state funding supports full-time positions [)

for a Reactor Supervisor / Assistant Director, three managers, a Health Physicist, and a Senior Administrative Associate. l 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 Facilltv staff [

Director B.W. Wehring Reactor Supervisor / Assist. Dir. T.L. Bauer  !

Manager NAS(Research Scientist) F.Y. Iskander '

Manager NBP(Resee.rch Scientist) K. Unlu  ;

Manager o&M(Research 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 -

S t u de nt- AmminPants Graduate Level:

Jong-Youl Kim Hector Vega Carlos Rios-Martinez Harry Felsher i Undergraduate Level: I Ingmar Sterzing  !

William Gerber Michael Weber ,

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i 1994 Annual Report  ;

i Funding . NETL funding is provided by state appropriations, i 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 l funds to allow the facility to provide quality data acquisition I 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 l lists the current supplemental funds. i t

Y Table 2-6 1 Supplemental Funds l

Proiect Title Funding runding Amount Period Source ,

Reactor Sharing 9/30/92-9/29/94 doe S 5,000 Instrumentation  !

for the University  !

of Texas Reactor 9/30/92-9/29/95 doe 26,506 {

Study of Neutron  ;

Focusing at the .

Texas Cold Neutron i Source 4/15/92-4/14/95 doe 98,179 i

An Expert System ,

to Enhance ~

Software Reliability 9/30/91-6/31/95 NRC 99,998  ;

Analysis for Selenium 3/6/93-8/31/94 TPW 10,983  ;

Total 240,666 I

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1994 Annual Report  !

2. 2 Education and Training Activities  ;

Tours and special projects are available to promote public awareness of nuclear energy issues. Tours of the NETL facility are routine activities of NETL staff and students. A typical l

' tour is a general presentation for high school and civic i organizations. Other tours given special consideration are demonstrations for interest groups such as physics, chemistry ,

and science groups.

A total of 1278 visitors were given access to the facility during the reporting period. The total includes tour groups, -

official visitors, and facility maintenance personnel. Tours for 26 groups with an average 16 persons / group were taken through the facility during the reporting period.

P Table 2-7 Public Access i Tour Groups 425 Individuals 312 Workers M1 Total 1278 t

Two special group projects by area students were done by arrangement with NETL staff. One person conducted an individual project with NETL staff. Presentations by NETL staff, including demonstrations with laboratory equipment, were given to several i high school organizations. These presentations were done as part of school wide programs sponsored by the high schools.

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.- 1994 Annual R$ port

2. 3 Service and Commercial Activities 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 conditions of waters subjected to certain types of power plant or industrial effluent releases.

PROJECT: Determination of Toxic and Other Elements in Mexican Cigarettes SPONSOR: NETL The concentration of 27 elements was determined in 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 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 measured in the cigarette ash.

PROJECT: Detection and Determination of Impurities in Pd Microelectrode SPONSOR Department of Chemistry, University of Texas Several Pd microelectrodes were irradiated and the emitted gamma rays were examined for the possible identification of any impurities in the electrode.

PROJECT: Multielement determination in plants used in 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 2-7

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two goals. The first goal is to estimate the intake of toxic or

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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 l

the treatment of specific diseases.

PROJECT: Multielement Determination in Airborne Particulate SPONSOR NETL i

Airborne particulates from 30 locations in Zacatecas, j Mexico were collected. All samples were. analyzed to determine l

the concentration of toxic and other elements around the city. j The results will help'in mapping the concentration of each 'l element.- Concentration distributions may provide data to f f

identify the source of pollution.  !

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1994 Annual' Report 2.4 Research andDevelonmentProjects PROJECT: Neutron Depth Profiling j SPONSOR: NETL )

A neutron depth profiling (NDP) instrument has been i l

designed, constructed, and tested. The University of Texas (UT)  !

NDP instrument utilites thermal neutrons from the tangential beam port (BPf2) of the reactor. The NDP technique is not ~

normally available to the research community due to the limited number of appropriate neutron sources.

Neutron depth profiling is an isotope specific .

nondestructive technique used to measure the near-surface depth l distributions of several technologically important elements in various substrates. NDP is based on neutron induced reactions  ;

to determine concentration versus depth profiles. Because of the potential for materials research, particularly for semiconductor research, the UT-NDP facility has been developed  ;

and is available for scientific measurements.

l The UT-NDP facility consists of a collimated thermal l neutron beam, a target chamber, a beam catcher, and necessary  !

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

A target vacuum chamber for NDP was constructed from  :

40.6 cm diameter aluminum tubing. The chamber can accommodate l

several small samples or a single large sample with a diameter up to 30 cm. A rotating fixture with up-and-down motion may be  !

controlled without breaking the vacuum. The other degrees of j 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. J l

Depth profiles of various borophosphosilicate glass from i Intel Corporation have been measured. Measurements were J repeated at the National Institute of Standards and Technology i i

1 2-9

1994 Annual R; port -

(NIST) NDP facility using the same samples. The NETL results i showed good agreement with the NIST depth profiles.

Other possible applications of the UT-NDP facility include f the study of implanted boron in semiconductor material as a j function of wafer treatment; study of nitrogen in metals as it affects wear resistance, hardness, and corrosion; and study of j helium behavior in metals, and metallic, and amorphous alloys. l PROJECT: Gadolinium Neutron Capture Therapy Dosimetry l Measurements i SPONSOR: HETL and The University of Texas MD Anderson [

Cancer Center i i

Neutron capture therapy (NCT) is a technique which employs neutrons in conjunction with neutron-absorbing drugs to create  !

i localized radiation damage. It shows promise in the treatment f

of some malignant tumors of the human central nervous system.  !

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

agent due to its large thermal neutron absorption cross section for the (n, alpha) reaction. i Another material, gadolinium, has been considered as an NCT f agent. In comparison to boron, most of the energy from neutron capture in gadolinium is nonlocalized gamma radiation. Thus, l

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  !

dose distribution near the tumor is very important. Several l I

calculations have predicted this spatial variation, but it has ,

not been measured for Gadolinium Neutron Capture Therapy. A f research program was initiated at the NETL to measure the low- f LET dose distribution in a head phantom with and without a Gd  !

loaded tumor region. li Epithermal neutrons give better results than thermal  !

neutrons for the treatment of deep seated tumors. In order to f

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 ,

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1994 Annual R: port i

i dose delivered by the Gd. gamma rays. This problem does not  !

exist for the corresponding Boron Neutron Capture Therapy (BNCT)  !

experiment.  !

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

dose measurements, and to decrease the flux of MeV neutrons to f

better simulate proposed clinical neutron beams. Several  !

neutron filters, to be placed midway _in the beam port, were ,

constructed which contained lead to attenuate core gamma rays, aluminum to attenuate neutrons with energies above 30 kev, and ,

titanium to attenuate neutrons which leak through the aluminum ,

with energies between 10 and 30 kev. .

A cylindrical head phantom made of brain tissue equivalent j 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 f placed in depressions on the surfaces of some of the disks. The f

phantom was placed inside the beam port exit, 250 cm away from  !

the core. l The initial efforts at measuring gadolinium dose rates were- l l

not successful because the background gamma dose rate was too i high. Measurements and calculations indicate that the lead used I to attenuate the core gamma dose also attenuates the kev neutrons. Thus, the signal to noise was not significantly f

improved. Extensive design calculations have been done during l the past year for a new geometry for these measurements. The l new geometry involves a D20 sphere place at the exit of the beam [

port, and the head phantom placed at the D20 sphere  !

perpendicular to the exiting neutron beam. l B

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1 1994 Annual Report i

PROJECT: Texas Cold Neutron Source f SPONSOR: Advanced Technology Program and the State of i Texas ,

A cold neutron source has been designed, constructed, and l tested by NETL personnel. The Texas Cold Neutron Source (TCNS) j is located in one of the radial beam ports (:BP #3) and consists ,

of a cold source system and a neutron guide system. j The cold source system includes a cooled moderator, a heat  :

pipe, a cryogenic refrigerator, a vacuum jacket, and connecting l lines. Eighty ml of mesitylene moderator is maintained by the f

cold source system at ~36 K in a chamber within the reactor l

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

{

selected for the cold moderator because it has been shown to be .

an effective and safe cold moderator. The moderator chamber for  !

the mesitylene is a 7.5 cm diameter right-circular cylinder 2.0 t

cm thick. The neon heat pipe (properly called thermosyphon) is a 3-m long aluminum tube which is used for cooling the moderator .

t chamber. The heat pipe contains neon as the working fluid that [.

evaporates at the moderator chamber and condenses at the cold  !

head. I Cold neutrons coming from the moderator chamber are j transported by a 2-m-long neutron guide inside the beam port and j a 4-m-long neutron guide (two 2-m sections) outside the beam j port. Both the internal neutron guide and the external neutron f guide are curved with a radius of curvature equal to 300 m. To  !

block line-of-sight radiation streaming in the guides, the croF; sectional area of the guides is separated into three  !

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

The TCNS system provides a low background subthermal  :

I*

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 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  !

the National Institute of Standards and Technology. At least 2-12 l

. t 1994 Annual Report [

i four major centers for cold neutron research Exist in Europe, j with another two-in Japan. [

PROJECT: Study of Neutron Focusing at the Texas Cold f Neutron Source

[

SPONSOR: DOE i The design and construction of a neutron focusing system j for use with the Texas Cold Neutron Source (TCNS) were  !

i thoroughly investigated. The focusing system will be 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 expected at the end of the curved guide. One example l of such an experiment is Prompt Gamma Activation Analysis, a  !

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 j system. Different multielement converging guides were designed f and analyzed. Each consisted of a number of truncated f rectangular conical sections coated with Ni-C/Ti supermirrors. f A fou -element 80-cm-long converging guide was selected for use l with the TCNS. Ovonic Synthetic Materials of Michigan, a small [

company which is the only company in the US capable of doing Ni- j C/Ti coating for supermirrors, built the converging neutron l 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  !

provide a unique capability to address a wide variety of i analytical problems of importance in-science and technology.

t 2-13

1994 Annual Report PROJECT: Prompt Gamma Activation Analysis ,

SPONSOR: DOE and the State of Texas l

A Prompt Gamma Activation Analysis (PGAA) facility has been designed by NETL personnel. The UT-PGAA facility will utilize  ;

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

Source. The PGAA sample will be located at the focal point of f the converging guide focusing system. The use of a guided I focused cold-neutron beam will provide a higher capture reaction  ;

rate and a lower background at the sample-detector area as l compared to other facilities using filtered thermal neutron ,

beams.

The UT-PGAA facility has been designed taking into account 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

~

background contribution for elements to be detected in the samples to be studied. b) The sample handling system was designed to be versatile to permit the study of a wide range of ,

i samples with quick and reproducible sample positioning with a minimum of material close to the samples.

A 25% efficient gamma-ray detector (GMX-25190-s ORTEC) in the DUET configuration with an offset-port dewar (30 liters) 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 other ,

components of the UT-PGAA system are under development.

The applications of the UT-PGAA will include: I 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, and semiconductor, iii) multielemental analysis of geological, [

archeological, and environmental samples for determination of major components such as Al, S, K, Ca, Ti, and Fe, and minor or t trace elements such as H, B,, V, Mn, Co, Cd, Nd, Sm, and Gd, and  !

iv) multielemental analysis of biological samples for the major  !

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i 1994 Annual Report i and minor elements H, C, N, Na, P, S, Cl, and K, and trace elements like B and Cd.

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1994 Annual Report  !

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2.5 SieniReantModiReations l No significant modifications have been made to the NETL 6

building, TRIGA reactor or experiment facilities. A summary of the types of modifications that did occur during the year f follows. A significant effort was in progress during the year l '

to test a cold neutron source for the reactor.

Buildmg. 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 i 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 l

of two or more control rods during automatic operation. i Erneriment Facilities. Standard experiment facilities for the i reactor are the center tube, pneumatic tube, rotary specimen  !

rack and beam ports. No significant modifications were made to f the original installation for any of the standard experiment  !

facilities.  !

The pneumatic tube (PNT), including support equipment is i not currently part of the installation. Installation of the i pneumatic system was a low priority during this year, although I planning and installation was in progress. The installation is  !

85% complete. An experiment authorization for the PNT is in  !

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

tests of the cold source at 250 Kw, 500 Kw, and 950 Kw are  !

2-16 ,

i 4 l 1994 Annual Report j complete. No unusual operating conditions that relate to safety of the experiment system have been found. A review of pressure and temperature dat'a from the TCNS is still in progress, f' however, to improve the understanding of the' power performance.

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2.6 Publications, Reports, andPapers .

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

students during the reporting period.

r Ph.D. Dissertations F

1. Carlos Rios-Martinez, " Prompt Gamma Activation Analysis using the Texas Cold Neutron Source," Ph.D. dissertation, The University of Texas at Austin, December 1994.

Publications i

Swnmaries:

1. K. On10 and B.W. Wehring, "Recent Accomplishments in Neutron Beam Projects at the University of Texas Research Reactor," Trans. Am. Nucl. Soc. 20, 135-136 (1994).

2. T.L. Bauer and B.W. Wehring, " Expert System Connected to  !

the University of Texas Research Reactor," Trans. Am. Nucl.  !

Soc. 2D, 138 (1994).

3. C. Rios-Martinez, K. On10, T.L. Bauer, and B.W. Wehring,  !

" Performance of Neon-Thermosyphon in the Texas Cold Neutron l Source," Trans. Am. Nucl. Soc. 21, 138-139 (1994). f

4. K. On10 and B.W. Wehring, " Applications for the University of Texas Neutron Depth Profiling Facility," Trans. Am. Nucl. Soc.

21, 163-164 (1994).

Paners.-

1. F.Y. Iskander, H.R. Vega-Carrillo, and A.E. Manzanares,  ;

" Determination of Mercury and Other Elements in La  :

Zacatecana Dam Sediment in Mexico," Sci. Total Environ.

113, 45-48 (1994).

2. B.W. Wehring, J.-Y. Kim, and K. Onlo, " Neutron Focusing System for the Texas Cold Neutron Source," Nucl. Instr. and Meth., Phys. Res. A 353, 137-140 (1994).

l

3. K. On10, C. Rios-Martinez, and B.W. Wehring, "The l University of Texas Cold Neutron Source," Nucl. Instr. and i Meth., Phys. Res. A 253, 397-401 (1994).

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1994 Annual Report

4. K. On10 and B.W. Wehring, " Neutron Depth Profiling at The University of Texas," Nucl. Instr. and Meth., Phys. Res. A 353, 402-405 (1994).

5. C. Rios-Martinez, K. Onlc, and B. W. Wehring, "Una Fuente de Neutrones Frios para Estudios de Materia Condensada,"

Investigacion Cientifica 1, 21-29 (1994).

6. K. On10 and B.N. Bayraktar, "The Quest for Energy: Nuclear Energy Outlook in Turkey," ENC'94 Transactions, Vol. II, 9-12 (1994).

7. H.R. Vega-Carrillo, "Calculo de los factores gamma para radioisotopos usados en Medicina Nuclear," Revista Espanola de Medicina Nuclear 13, 43-47 (1994).

8. H.R. Vega-Carrillo and A.E. Manzanares, " Radiation Treatment of Cancer," Revista Medica ISSSTE Zacatecas, 2 15-22 (1994).

9. F.Y. Iskander, " Measurements of 27 Elements in Garden and Lawn Fertilizers using Instrumental Neutron Activation Analysis," J. Radioanal. Nucl. Chem. 1HD, 25-26 (1994).

Presentations (speaker underlined)

1. S.C. Tovar, F.Y. Iskander and H.R Vega-Carrillo, "INAA of Some Rare Earth Elements in Fluorite," American Association of Physics Teachers 1994 Winter Meeting, San Diego, California, January 3-8, 1994.

2. H.R. Veaa-Carrillo, F.Y. Iskander, and A.E. Manzanares, "Multielement Measurement for Mexican Cigarette Tobacco,"

American Nuclear Society Western Regional Student Conference, Tucson, Arizona, March 24-27, 1994 (given an outstanding paper award)

3. K. Onln, C. Rios-Martinez, and B.W. Wehrino, " Prompt Gamma Activation Analysis with the Texas Cold Neutron Source,"

Third International Conference on Methods and Applications of Radioanalytical Chemistry, Kona, Hawaii, April 10-16, 1994.

4. R.O. Villareal, H.R. Vega-Carrillo, and F.Y. Iskander, "INAA of Standards of Cements," 1994 Joint Meeting of American Physical Society and American Association of Physics Teachers, Crystal City, Virginia, April 18-22, 1994.

5. R.E. Lopez, H.R. Vega-Carrillo, and F.Y. Iskander, " Search of Corrosive Elements in BOP.F Polymers," 1994 Joint Meeting of American Physical Society and American Association of Physics Teachers, Crystal City, Virginia, April 18-22, 1994.

2-19

I O

1994 Annual Report

6. B.W. Wehring, J.-Y. Kim, and K. Onlo, " Neutron Focusing System for the Texas Cold Neutron Source," 1994 Symposium on Radiation Measurements and Applications, Ann Arbor, Michigan, May 16-19, 1994.

7. K. On10, C. Rios-Martinez, and B.W. Wehring, "The University of Texas Cold Neutron Source," 1994 Symposium on Radiation Measurements and Applications, Ann Arbor, Michigan, May 16-19, 1994.

8. K. On10 and B.W. Wehring, " Neutron Depth Profiling at The )

^

University of Texas," 1994 Symposium on Radiation Measurements and Applications, Ann Arbor, Michigan, May 16-19, 1994.

9. B.W. Wehrino and K. On10, "The University of Texas Cold Neutron Source," International Seminar on Advanced Pulsed Neutron Sources: Physics of/at Advanced Pulsed Neutron Sources, PANS II, Dubna, Russia, June 14-16, 1994.

10. K. On10 and B.W. Wehring, "Recent Accomplishments in Neutron Beam Projects at the University of Texas Research  ;

Reactor," American Nuclear Society 1994 Annual Meeting, New Orleans, Louisisana, June 19-23, 1994.

11. T L. Bauer and B.W. Wehring, " Expert System Connected to the University of Texas Research Reactor," American Nuclear Society 1994 Annual Meeting, New Orleans, Louisisana, June 19-23, 1994.

12. K. On10, " Neutron Beam Research at the University of Texas Reactor," Hacettepe University, Ankara, Turkey, July 6, 1994.

13. K. On10, "Recent Developments and the Future of Boron / Gadolinium Neutron Capture Therapy," Turkish Atomic Energy Authority, Cekmece Nuclear Research and Training Center, Istanbul, Turkey, July 13, 1994.

14. A.E. Manzanares, H.R. Veca-Carrillo, and F.Y. Iskander,

" Elemental Concentration in Cigarette Wraping Paper and Tobacco," American Association of Physics Teachers 1994 Summer Meeting, University of Notre Dame, August 8-13, 1994.

15. K. On10 and B.N. Bayraktar, "The Quest for Energy: Nuclear ,

Energy Outlook in Turkey," ENC'94 International Nuclear Congress, Lyon, France, October 2-6, 1994 (selected one of the  ;

three best papers and invited for oral presentation before the '

full audience in the plenary session).

2-20

1994 Annual Report r

16. H.R. Veoa-Carrillo and J.Y. Kim, " Selecting the Initial .

Guess Spectrum in Neutron Sprectra Unfolding Process,"

American Association of Physics Teachers 1994 Fall Meeting, Austin, Texas, October 13-15, 1994.

17. C. Rios-Martinez, K. On10, T.L. Bauer, and B.W. Wehring,

" Performance of Neon-Thermosyphon in the Texas Cold Neutron ,

Source," American Nuclear Society 1994 Winter Meeting, Washington, DC, November 13-17, 1994.

18. K. OnlO and B.W. Wehring, " Applications for the University of. '

Texas Neutron Depth Profiling Facility," American Nuclear '

Society 1994 Winter Meeting, Washington, DC, November 13-17, 1994.

19. H.R. Veca-Carrillo, F.Y. Iskander, and A.E. Manzanares,  !

"Multielement Determination in Mexican Cigarettes Tobacco," I American Chemical Society 50th Southwest Regional Meeting, .

Fort Worth, Texas, November 13-16, 1994. l

20. F.Y. Iskander and M. Lyday, " Determination of Selective  !

Elements in Baseflow Water Samples using Instrumental j

~

Neutron Activation Analysis," American Chemical Society 50th Southwest Regional Meeting, Fort Worth, Texas, ,

November 13-16, 1994.

21. A.J. Teachout, "A Comparison of Neutron Detection Systems with Radioisotopic Neutron Sources," Health Physics Society Meeting, San Francisco, California, June 26-30, 1994.

22. A.J. Teachout, " Characterization of Neutron Spectra of Varian Clinacs Model 2100C and 2300C/D Medical Linear Accelerators," Health Physics Society Meeting, San  !

Francisco, California, June 26-30, 1994, i

I i

l l

l 2-21

. 1994 Annual R: port l 3.0 FACILITY OPERATING SUMMARIES 3.1 operating Experience The UT-TRIGA reactor.at the J.J. Pickle Research Campus i became operational during 1992. Total operating times did not

[

change much from the first to second year of operation although l the energy production increased almost a factor of two. The i total burnup after two years of operation is 7.0 MW-days. A f

total of 65.2 MW-hours were generated in the third year of operation. The reactor was critical for approximately 155 hours0.00179 days <br />0.0431 hours <br />2.562831e-4 weeks <br />5.89775e-5 months <br />.

A summary of the burnup history is shown in Figure 3-1. ,

f Burnup History j MW Hrs [

120 i

100 ,

80 l 60 +

+ .

. . j 40 + +  ;

20 + + +  !

l 0 . . .

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

3.2 Reactor Shutdowns l

The reactor safety system classifies protective action  ;

trips as one of three types, a limiting safety system (LSSS) l' 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 f

3-1 classify the types of protective actions recorded.  !

r 3-1 1

-~, ,

i

• 1994 Annual Rsport I i

Table 3-1 i Protect 1're Action Definitions f Protective Action Descriotion .l 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 j detection) system. t l

Examples:

pool water level i detector high voltage l external circuit trips ,

Condition for Software action detects inoperable  :

operation conditions within a program function of LCo - (digital the instrunent control and safety l detection) system. i i

Examples:

watchdog timers program database errors l Manual Switch operator emergency shutdown (protective action) i Manual Switch Operator routine shutdown i (intentional i operation) l t

1 Scrams are further categorized according to the technical f specification requirement given in Table 3-2. External scrams l which provide protection for experiment systems are system l operable conditions. l i

The total number of safety system protective actions during 1994 was four. Of the four total protective action shutdowns l t

two were actions of a safety system setting, and two were  ;

I actions of a system operable condition (see Table 3-3).

f 3-2 i

.s 1994 Annual R* port ,

i Table 3-2  !

Instrumentation, Control and Safety System l Protective Action Events (1)  !

Technical Specification Requirement Ita HQ j SCRAM Tyne Safety System Setpoint (LSSS) 2 0 System operable Condition (LCo)  !

?

Analog detection (hardware) 2 0 Digital detection (software) 0 0  !

Manual Switch  !

Protective action 0 0 l Intentional operation (2)- _ _ L Total Safety System Events 4 0 (1) Tests of the SCRAM circuits are not recorded (2) Intentional ScRANS (non protective action) are not recorded l A review is always done to determine if routine corrective actions are sufficient to prevent the recurrence of a particular reactor safety system shutdown.  !

Table 3-3 [

Summary of Safety System Protective Actions ,

1 Trin Action Ntimbe r o f occurrencen Safety System Setpoint 2 l System operable Condition 2  ;

6 Total 4 h

v 3-3

G

_,: 1994 Annual R port  ;

o i Previous SCRAM History Number of SCRAMS i

16  !

i 14 12 f i

10 l

+

8 [

6 * * .

+ +  !

4 * *

• 2 - + =

i 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999  !

Year Figure 3-2 Summary of All SCRAM Events .

i i

3.3 Utilization l Primary utilization of the reactor during the year was by l l

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. One significant research project was development of a cold neutron l

source for the radial beam port. Development testing of the

{

TCNS continued throughout the year. The basic testing phase of j the TCNS was complete in 1994, although work continues to- l improve full power performance and develop the beam guides. j A summary of the reactor utilization for 1994 is presented l in Table 3-4 with the monthly distribution.shown in Figure 3-3.

Table 3-5 summarizes the sample irradiations and experiments.

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

i 3-4 I

_ _ _ _ _ _ - - - -j

1994 Annual Report [

l i

Table 3-4 Summary of 1994 UT-TRIGA Operation

{

t Q1 ,Q2 Q3 Q4 Total  :

1. of " Kev On" Hours operator #1 18.0 32.2 26.4 31.7 108.3  :

Operator #2 12.2 0.0 0.0 0.0 12.2 f i

testing / maintenance 18.8 1.2 12.8 1.7 34.5 Total hours 49.0 33.4 39.0 33.4 155.0  !

l MW-Hours Enerav Operator #1 11.4 17.5 13.1 22.3 64.3 i

operator #2 0.0 0.0 0.0 0.0 0.0  !

testing / maintenance <0.1 <0.1 0.5 0.4 0.9 l s

Total 11.4 17.5 13.6 22.7 65.2 1

i I

Monthly Burnup Kw Hrs ,

i 16000 I

14000

• 12000 +

10000 +

1 8000 *

• 6000 * * *

• 4000 + + + + = = =

• 2000 * * * * * * * * * *

• o . . . . . . . . . . .

JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC Figure 3-3 operating Data 1994 3-5

1994 Annual Report 'I i

I i

i Table 3-5 l Summary of Utilization 1994 t UT-TRIGA Experiments 01 02 -Q3 Q4 Total  !

No. of Samnlan p

.. I In-core 66 244 238 235 783 t Ex-core 4 2 1 6 13 {

i No. of Funer4 m nt s -!

Type A 5 11 5 13' 34  ;

Type B 4 4' 5 4 17  ;

Other 0 0 1 0 1  !

Total 9 15 11 17 52  ;

l t

i r

i Number of Sample Irradiations l No. of '

I Samples 500 l

400 j 300 200

• l 100 + + - * * * * + + l

. . . . . . . . . l 0 = * - - . - . = .

JAN FEB MAR APR MAY JUN JUL AUG. SEP OCT NOV DEC )!

Figure 3-4 Operating Data 1994 l i

d I

3-6 ]

. -. ___ . __ - _ . . _ _ _ __ _ _ _ 0

s 1994 Annual Report 3.4 Maintenance Maintenance in 1994 was routine. Maintenance work included repairs and included modifications to' equipment. Replacements were made to several digital components of the reactor control system. All changes were made to meet or exceed original manufacturer's specifications. No significant. safety considerations were detected during the maintenance activities.

A design flaw in the argon-41 monitoring system was found.

The flaw, which was in the argon-41 count circuit was the source of random errors in the radioactivity measurements. Analysis of previous measurements indicated that counting circuit failures did not create a significant error in count totals. A replacement counting system will replace the argon-41 count module until a new design for the defect part is available.

3.5 Facility Changes one significant experiment authorization begun during 1993 continued throughout 1994. The experiment authorization was for the installation, test and operation of the Texas Cold Neutron Source. No unreviewed safety question was found during the review of the Safety Analysis Report for the Texas Cold Neutron Source. Several tests of the system were done during 1994 to determine the heat removal capabilites of the system.

Tests during 1994 determined the effect of nuclear heating on the TCNS heat removal capability. Changes, all minor, were made to improve the system. At the end of the year the TCNS could operate approximately 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> at full power. Tests at 500 kilowatts indicated no limit to the operating time at that power level. Analysis of the data from experiments at 250, 500 and 950 kilowatts are consistent with the design conditions. Work on the neutron-wave guide system will complete the TCNS testing during the 1995 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 3-7

c' 4

1994 Annual Report l shift the energy of thermal neutrons available at the reactor to >

subthermal neutrons at an experiment. The process is done by f

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 I heat pipe are contained in a vacuum system insulation from thermal heat sources. j The safety problems associated with commonly used  :

moderators such as hydrogen, deuterium or methane are eliminated j by using mesitylene, 1,3,5-trimethylbenzene, as a moderator.

The H2, D2, and methane are gaseous at room temperature, and l

possible sudden temperature changes may lead to a dangerous  !

L pressure buildup in the moderator chamber. Mesitylene is a l 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 ir in the moderator chamber and mesitylene have been evaluated.

l Possible ozone generation in vacuum chamber, radioactivity of f 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 f I

loss of vacuum. It was concluded that even with worst-case scenarios will not create a safety issue related to damage to i I

the reactor components or reactor core. Analysis demonstrated l

no credible accident involving the Texas Cold Neutron Source could cause damage to the reactor beam tube or to the reactor f core or cause releases of radioactivity in excess of the limits in 10 CFR 20.  ;

r I

t 3-8

. - . _ _ _ _ _._D

r e

1994 Annual Report ,

i 3.6 Laboratory Inspections Inspections of laboratory operations are conducted by l i

university and. licensing agency personnel. Among the functions  !

of the Radiation Safety Committee and Nuclear Reactor Committee was the review of inspections by university personnel. These l committees convened at the times listed in Table 3-6.  :

t Table 3-6 ,

Comnittee Meetings l l

Radlation Safety Cnmittee Spring Term April 29, 1994 Fall Term october 4, 1994 l

[

Nuclear ReAgt o r Cn-4 t t ee .

First Quarter January 27, 1994 Second Quarter April 7, 1994  ;

Third Quarter July 19, 1994 Fourth Quarter october 6, 1994 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 i the times presented in Table 3-7. ,

Table 3-7 l Dates of License Inspections  ;

r licenne Dates [

R-129  ;

SNM-180 March 23, 1994 LO O485 (4 8) September 26-30, 1994 )

t i

I

?

f 3-9

)

. i a  !

1994 Annual Report l 3.7 Radiation Exposures ,

Radiation exposures for personnel, building work areas and areas in the vicinity of the building are shown in the following tables. Table 3-8 lists NETL personnel dose exposure data for i the calendar year. Table 3-9 is a list of the Radiation  !

Protection Requirements and Frequencies. Figure 3-5 locates the building internal and external dosimetry sites. Numbers identify the immediate vicinity radiation measurement sites l exterior to the building. These sites do not indicate any measurable dose from work within the NETL building. Table 3-10 and Table 3-11 list doses recorded in facility work areas and i the immediate area adjacent to the building.

i Table 3-8  !

Annual Summary of Personnel Radiation Doses Received Within the NETL Reactor Facility [

Averace Annual DoseIII Personnel Students Visitors (PIC) i Whole Body,DDE i M M(2) <1 f Extremitles,SDE l 70 2 (3) N/A [

Lens of eye,LDE  !

M 2 N/A i f

Greatest Individual Dose Personnel Students Visitors (PIC) '

Whole Body,DDE [

M 10 5 .

Extremities,SDE M 10 N/A f Lens of eye,LDE  !

80 10 N/A f f

Total Person-mrem for Groun t Personnel Students Visitors

{.

Whole Body,DDE M 10 13 t Extremities,SDE  !

M 10 N/A  !

Lens of eye,LDE  !

140 10 N/A l

3-10 ,

l

a 1994 Annual Report  ;

Notes to Table 3-8 ,

(1) Dose is in arem. 1 (2) "M" indicates that each of the beta-ganana or neutron dosimeters during the reporting period was less than the vendor's minimum measurable quantity of 10 mrom for x- and gamma rays, 4 mrom for energetic betas, 20 mrem for fast neutrons, and 10 mrom for thermal neutrons.  :

(3) "N/A" indicates that there was no extremity monitoring conducted i or required for the group. 1 (4) DDE applies to external whole-body exposure and is the dose equivalent at a tissue depth of 1 cm (1000 mg/cm 23, (5) SDE applies to skin or extremity external exposure, and is the dose equivalent at a tissue depth of 0.007 cm (7 mg/cm 23, (6) LDE applies to the external exposure of the eye lens and is taken as the dose equivalent at a tissue depth 0.03 cm (300 mg/cm 23, (7) PICS are pocket loniration chambers issued to persons who enter radioactive materials / restricted areas for periods of short duration, i.e., a few hours -

annually. It is suspected that most of the doses recorded on the visitor PIC issue cards were due to incorrect reading of the PIC or improperly  !

completing the PIC issue card (six cards listed doses received, out of a total of 210 cards) . t 5

f 6

6 h

k l

j i

3-11

1 1

• 1 1994 Annual Report Table 3-9 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.

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

Monthly Gamma survey of exterior walls and roof.

Neutron survey of exterior walls and roof.

Swipe survey of roof.

Exchange personnel dosimeters and interior area menitoring dosimeters.

Review dosimetry reports.

Response check emergency locker portable radiation measuring equipment.

Review Radiation Work Permits.

Response check of the argon monitor.

Response check hand and foot monitor.

Conduct background checks of low background alpha / bet counting system.

Collect and analyze TRIGA primary water.

As Process and record solid wasted and liquid effluent Required discharges.

Prepare and record radioactive material shipments.

Survey and record incoming radioactive materials.

Perform and record special radiation survey.

Issue radiation work permits and provide health phys:

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 HV plateaus at detection efficiencies on the low background alpha / beta counting system.

Semi- Inventory emergency locker.

Annual Calibrate portable radiation monitoring instruments.

Calibrate contir.uous air monitor, argon monitor, and area radiation monitors.

Leak test and inventory sealed sources.

Annual Conduct ALARA Committee meeting.

Conduct personnel refresher training.

Calibrate emergency locker portable radiation detect:

equipment 3-12

r , . . .

1994 Annual Report ,

ACCESS ROAD l L J PARKitG s

. 1 t

• 2 i e

e .

'. m L

5 PARK!PG 4 1 Sidewalk M TL facility fremt entranee 2 Reactor hay enterior wall, east 3 maaetor boy enterior maii, west 4 MTL power transformer 5 urTL servios door  ;

6 METL roof stack -

I

• Indiostas location of dosimetry within the building  !

SERVICE DRIVE i

l t

Figure 3-5 Environmental TLD Locations l

)

l i

l I

i l

l l

.3-13

e.'  ;

1994 Annuni Rsport -!

Table 3-10 Total Dose Equivalent Recorded on  ;

TLD Environmental Monitors Around the NETL Reactor Facility '

Location in Reactor Facility Mnn4 tor Total I

n g (1)

Sidewalk, NETL facility front entrance 00156 M(2)  ;

NETL power transformer 00157 M j NETL Roof stack 00158 M Reactor bay exterior wall, east 00159 30 Reactor bay exterior wall, west 00160 M NETL service door 00161 150(3) '

I (1) Dose is in mrom. i

) (2) "M" indicates that each of the dosimeters during the period was below vendor's minimum measurable quantity of 10 mrom for x- and ,

gamma rays, 40 mrom for energetic botas. The total recorded dose  !

equivalent values do not include natural background contribution l and reflect the summation of the results of four quarterly TLD dosimeters for each location.

(3) Measurement does not agree with other data. )

3 I

l I

3-14

i e

• e- 1994 Annual Report ,

i Table 3-11 Total Dose Equivalent Recorded on Area Dosimeters Located Within the ,

NETL Reactor Facility i

Location in Reactor Pacility Monitor Total Dome (1) i In Aa.x _n ,

Reactor Bay, North Wall 00167 20(2) g Reactor Bay, East Wall 00168 M M .

Reactor Bay, West Wall 00169 30 M l Water Treatment Room 00170 1090 M i Reactor Pool Area, Roof 00171 10 M Shield Area, Room 1.102 00172 40 M Sample Processing, Room 3.102 00173 10 N/AI3) }

Gamma Spectroscopy Lab, 3.112 00174 M N/A i Radiation Experiment Lab, 3.106 00175 M N/

Reception Area, 2.102 00176 10 N/A

)

(1) Dose is in mrom. I (2) "M" indicates that each of the dosimeters during the period was l below vendor's minimum measurable quantity of 10 mrom for x- and gamma rays, 40 mrom for energetic betas, 20 mrem for fast neutrons, ,

and 10 mrom for thermal neutrons. The total recorded dose j equivalent values do not inclade natural background contribution i and reflect the summation of the results of 12 monthly beta, x- l and gamma ray or neutron dosimeters for each location. These dose  ;

equivalent values do not represent radiation exposure through and i exterior wall directly into an unrestricted area.

(3) "N/A" indicates that there was no neutron monitoring at that location. f f

I v

t i

l 6

i l

i 3-15

't i

,,, 1994 Annual Report  ;

3.8 Radiation Surveys Radiation surveys of NETL work areas are shown in Table '

s 3-12. Surveys with portable instruments and measurements of l

radioactive contamination are routine. Supplemental  !

measurements are also made any time unusual conditions occur. j Values in the table represent the result of routine I I

measurements. Environmental monitoring at sample sites exterior  :

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

Table 3-12 [

Annual Summary of Radiation Levels and Contamination Levels Within the i Reactor Area and NETL Facility f

i Accessible Location Whole Body Contamination f Radiation Levels Levels i (mrem /hr)(1) (dpm/100cm 2)

Average Maximum Average Maximum TRIGA Reactor Facility f Reactor Bay North 0.55 1.5 3.4 36.8 I Reactor Bay south 0.012 0.185 MDA(2) MDA(2) }

Reactor Bay East 0.02 0.035 Mog(2) gog(2) l Reactor Bay West 0.095 0,18 gog(2) gog (2) i Reactor Pool Deck 0.012 0.02 9.7 17?6.3(3) [

(third floor)  ;

NETL Facility NAA Sample Processing 0.03 0.5 3.5 23.1(3) j (Rm 3.102 ,

NAA Sample Counting 0.03 1.1 2.9 36 j (Rm 3.112)

Health Physics 0.01 0.025 MDA Mog(2) ]

Laboratory Neutron Generator 0.13 0.6 7.3 22.7 }

(Rm 1.102) j Waste Storage r (Rm 1.108) {

l f

f f

(1) Measurements made with a Bicron Microrem portable survey meter. l (2) MDA for the G-5000 low level alpha-beta radiation counting system is 2.49 dpm/100 cm 2 j beta. *

(3) The contamination shown for this location assumes 100% smearing efficiency, and was  !

immediately removed. As result, the average contamination level at this location l during the reporting period was, for all practical purposes, <500 dpm per 100 cm 2, j I

l l

3-16 l

1 i

• i

< 1994 Annual R3 port j i

i 3.9 Radioactive Effluents, Radioactive Waste l

Radioactive effluent releases to the air, to the sanitary l r

sewer and disposals of radioactive materials are shown on the l following pages. Argon-41, with a half-life of 109 minutes is j the only airborne radionuclide emitted by the facility. A -

summary of the Argon-41 releases are shown in Table 3-13.

t t

Table 3-13 f Monthly Summary of Argon-41 Effluent Releases (II  ;

Date of Discharge Total Quantity of Average Fraction of (Month, 1994) Argon-41 Release Concentration at Technical  !

(microCuries) Point of Release Specifications (2) j (microcurie /cm33 (g) f January 0.00E+00 0.000 February 56500 3.38E-08 0.28 l March 47300 2.83E-08 0.24 April 41200 2.47E-08 0.20 l l

May 143000 8.57E-08 0.71  ;

June 153000 9.16E-08 0.76  ;

July 69000 4.13E-08 0,34 August 75600 4.53E-08 0.38 September 98100 5.87E-08 0.49 October 48600 2.91E-08 0.24 l l

November 201000 1.20E-07 1.00 +

December 61100 3.66E-08 0.30  ;

ANNUAL VALUE 994000 4.96E-08 0.41 l (1) Point of release is the roof exhaust stack. Concentration includes dilution factor of [

0.2 for mixing with snain exhaust.

(2) Technical Specification limit is 2.00E-6 microcurie /cm 3, j l

r 3-17 j 1

+

.- 1994 Annual R*. port f

Table 3-14 Monthly Summary of Liquid Effluent Releases to the Sanitary Sewer From the NETL Reactor Facility Date of Release Total Quantity Discharge Volume of Radioactivity (Month, 1994) (m3 ) (Curies) i 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 i November No Releases December No Releases Table 3-15 Monthly Summary of Solid Waste Transfers for Disposal Date of Release Total Quantity Discharge Volume of Radioactivity (Month, 1994) (m3 ) (Curies)

January No Releases February No Releases March No Releases April 0.21 6.36E-09 May No Releases June No Releases July 0.11 4.33E-07 August 0.11 3.24E-08 September No Releases October 0.11 1.07E-06 l November No Releases December No Releases l

3-18 l

/..y 1994 Annual R! port Releases to the sanitary sewer are done from waste hold up tanks at irregular intervals. To date no releases have been made.

Radioactive waste disposal of solids are shown in Table 3-15. The inventory of material in Table 3-15 represents the disposal of decontamination waste from Taylor Hall and experiment waste from Building 159. The total activity sent to disposal was 1.5 microcuries. Radioactive materials were tank cleanup waste from Taylor Hall, NAA sample waste from Building 159 and miscellaneous gloves, paper and other disposable materials. Tank cleanup waste from Taylor Hall included resin and filters with small amounts of the isotopes of Co60 and Cs137 NAA samples wastes from Building 159 contained the isotopes of Co60, Zu65, Ba133, Sb122, Na22, K40, CoS7, Ag 110m and Te125, All material was sent to the university safety office for disposal as low level waste.

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