ML20198P036
| ML20198P036 | |
| Person / Time | |
|---|---|
| Site: | 07000157 |
| Issue date: | 10/24/1997 |
| From: | TEXAS, UNIV. OF, AUSTIN, TX |
| To: | NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| Shared Package | |
| ML20198P011 | List: |
| References | |
| NUDOCS 9711060249 | |
| Download: ML20198P036 (54) | |
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APPLICATION FOR RENEWAL OF LICENSE SNM 180 SPECIAL NUCLEAR MATERIALS Submitted to i
Director, Omcc of Nuclear Materials Safety and Safeguards Fuel Cycle Safety Branch Division ofIndustrial and Medical Nuclear Safety l
U.S. Nuclear Regulatory Commission Washington, D.C. 20555 -
by i
Nuclear Engineering Teaching Laboratory J 1. Pickle Research Campus 10100 Bumet Raad, Building No.159 Austin, Texas 78758 October 1997 1
9711060249 971024 PDR ADOCK 07000157-:
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4 SUBMISSION FOR RENEWAL OF SPECIAI NUCLEAR MATERIAL LICENSE ~
70.22(a)(1)Name of Applicant:
Nuclear Engineering Teaching Laboratory Department of Mechanical Engineering The University of Texas at Austin J.J. Pickle Research Campus, Bldg. No.159 Austin, Texas 78712 Thomas L. Bauer, Assistant Director / Supervisor J.J. Pickle Research Campus, Bldg. No.159 U.S. Citizen Bernard W. Wehring, Director J.J. Pickle Research Campus, Bldg. No.159 U.S. Citizen J. Parker Lamb, Chairman, Mechanical Engineering l
ETC 5.214; ETC 7.150 U.S. Citizen Ben Streetman, Dean, College of Engineering EJC 10.310 U.S. Citizen Stephen Monti, Provost and Executive Vice President i
Main 201 U.S. Citizen 70.22(a)(2) Activity and location for which Special Nuclear Material License is requested:
The Nuclear Engineering Teaching Laboratory of the University of Texas at Austin uses Special Nuclear Material to supplement the training and instruction programs in the field of nuclear engineering. The items described in this application are used forjunior, senior and graduate level laboratory courses in the Nuclear Engineering Program of the Mechanical Engineering Department. The licensed materials are to be used in experiments in the Nuclear Engineering Laboratory facilities located at the University's J.J. Pickle ResearchCampus (formerly known as the Balcones Research Center).
o Laboratory facilities associated with the Nuclear Engineering Program include a research reactor with appropriate Nuclear Regulatory Commission license, NRC R-129, and a charged particle accelerator which operates under a Certificate of Registration from the Texas Department ofIlealth, Bureau of Radiation Control (License TDil LOO 485).
A diagram of the facility location and Door plan is included in Appendix A-1,3. The Nuclear Engineering Teaching I ahoratoy building designation is Building 159 at the J.J.
Pickle Research Campus (formerly known as the Balcones Research Center). The primary location for storage and operation of the assembly will be Room 1.104 and 1.102 of Building 159.
70.22 (a)(3) Requested duration oflicense is for 5 years.
70.22(a)(4) Description of Special Nuclear Material:
The Special Nuclear Material to be covered by this license is an extension of the previously granted license, SNM 180, dated Februay 27,1958, and later amendments.
Materials added by amendment in 1991 (8/1/91) have been rernoved to the R-129 li:ense.
1.
2"U Suberitical Reactor Assembly A. Description 1.
A homogeneous system is assembled of 2695.52 grams of UO 2 impregnated in high density polyethylene with a total weight of 18,788.1 l
grams. The UO, is enriched to 19.776% U-235, for a total U-235 composition of 469.74 grams, i
2.
The assembly consists of a cylindrical core with 10" diar..eter and 14" length assembled from 8 fuel disks into one unit. Axial and radial holes in the assembly may be filled with 36 smaller fuel disks of about 1" diameter.
The cylindrical core unit contains 465.03 grams of U-235 with ttie fuel plugs totaling 4.71 grcms of U-235. (One fuel plug is unaccounted for.)
3.
The fuel assembly operation is supplemented by 3 reflector assemblies. 3" polyethylene,6" polyethylene, and 10" graphite. An additional graphite block provides an external thermal sou:ce.
B.
Usage The suberitical assembly and the reflector media material are used with neutron sources to demonstrate the concepts of suberitical multiplication, thermal diffusion, fermi age. Hux measurement and other basic nuclear engineering principles. Both neutron detection systems and foil activation
I 4
techniques are applied in various expeiiments to monitor neutron flux levels and flux shape.
II.
Plutonium-Ileryllium Neutron Sources A.
Description 1.
hi-222 source contain 15.970 gms Pu scaled in a tantalum and stainless steel capsule with dimension of 1.02" O.D. x 1.46" high.
The Pu is 93.02325% enriched in (Pu-239 + Pu-241). The source has a total strength of 1.81 x 10' neutrons /second (12-3-61).
2.
M-798 source contains 31.960 gms of Pu scaled in a tantalum and stainless steel capsule with dimensions of 1.021" O.D. x 2.182" high. The Pu is 93.02325% enriched in (Pu-239 +
Pu-241). The source has a total strength of 3.83 x 10' neutrons /second (6-4-65) 3.
M499 source contains 79.940 gms of Pu sealed in a tantalum and stainless steel capsule with dimensions of 1.31" O.D.
x 2.72" high. The Pu is 91.02325% enriched in (Pu-239 + Pu 241),
making a total of 74.363 gms (Pu-239 + Pu 241). The source has a total strength of 8.82 x 10' neutrons /second (12-3-61).
11.
Usage The plutomum-beryllium neutron sources are used for neutron detector calibration, subcritical reactor multiplication source and neutron dose measurement experiments. Operation of the suberitical reactor assembly is accomplished by insertion of a neutron source into the radial or axial access hole or by positioning a source near the core assembly.
70.22(a)(6) Technical Qualifications of Applicant:
1, Administrative structure.
Staff qualifications for responsible utilization oflicensed special nuclear materials in the Nuclear Engineering Teaching Laboratory include the administration of a special nuclear material license, a nuclear reactor operating license, and a state radioactive materials license. The administrative structure consists of a Radiation Safety Committee, Radiation Safety Officer, Nu,: lear Reactor Committee, Laboratory Director, and Laboratoiy Assistant Director / Supervisor. Laberatory staff includes reactor operator, health physicist, and, as needed, research associates, technicians, administrative secretary and research assistants.
I
4 4
11.
Radiation Safety Committee The Radiation Safety Committee is established through the omce of the University President and contains 3 faculty and/or staff memberi from Science or Engineering Departments.
A.
Duties of the Radiation Safety Omccr A Radiation Safety Omccr acts as the delegated authority of the Radiation Safety Committee with responsibility to the University Safety Engineer.
Policies and practices set forth by the Radiation Safety Committee regarding the safe use of radioisotopes and sources of radiation on the University campus are implemented by the Radiation Safety Omcer.
The duties of the Radiation Safety Omcer are numerous but consist primarily of establishing, monitoring, and curtailing programs for the safe use of radioactive materials and radiation sources with respect to state or federal requirements. Some specific duties include periodic surveys and inspection, maintenance of radioisotope records and personnel exposures, disposal of radioactive wastes, periodic leak tests of sealed radiation sources, calibration of radiation detection instruments, help in the training of staff, aide in preparation of procedures, define proper radioactive material handling methods, and act as liaison for state and federal license responsibilities.
B.
Qualifications of Radiation Safety Omcer Qualifications of the Radiation Safety Omcer require a Bachelor's degree in engineering, physics or related field. Preferred e,ualifications require an advanced degree in health physics or radiological health or certification as a Safety Professional or Health Physicist. Experience required is three years work in radiation safety and/or radiological health plus a thorough working knowledge of Texas Regulations for Control of Radiation and supporting regulations issued by the United States Nuclear Regulatory Commission. Preferred experience includes knowledge of particle accelerators and nuclear reactors.
111.
Nuclear Reactor Committee A nuclear reactor committee responsible to the Dean of the College of Engineering with at least three nembers knowledgeable in the fields of nuclear safety shall review, evaluate, and approve standards associated with the operation the laboratory facility. Jurisdiction shall include all nuclear operations in the facility and general safety standards. The Radiation Safety Omcer is a member of the committee. Laboratory facility operation will be under the direct control of
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the Laboratory Director or a licensed Senior Operator designated by the
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Laboratory Director.
I A.
Duties of the Laboratory Supervisor 1
- Daily activities of the laboratory are directed by an NRC licensed senior
. operator whose responsibility is to direct the operation of the nuclear -
i reactor and other laboratory activities. The Senior Operator schedules and coordinates activities, assures the maintenance of appropriate license -
records and equipment calibrations, reviews experiments and procedures, i
supervises the use of radioactive materials and sources, supervises the activida of other laboratory personnel and supports teaching research functioes of the laboratory.
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B.
Qualifications of the Laboratory Supervisor
' Qualifications of the Reactor. Supervisor require a Bachelor's degree in engineering or science with three years experience in a related field.
Qualifications for a USNRC Senior Operator license is required. Preferred qualification is c. Master's or Ph.D. degree in a field of nuclear engineering or science with appropriate experience. Experience preferred is five years including two in a supervisor position. Knowledge of nuclear facility operation, radiation detection vams, data acquisition and analysis systems, electronic and mechalf of measuring equipment and utilization of computer equipment are requt.v <!1s.
n IV.
Laboratory Staff A.
Nuclear Technical Specialist (one or more positions)
Duties of a nuclear technical specialist include operation and maintenance of equipment, review of procedures and regulations, instruction and c
assistance of students or researcher, and assist in record maintenance and ieport preparations.
Qualifications require engmeenng or science degree or appropriate laboratory experience with radioactive materials and radiation detectors.
Pursuit of an NRC operator or senior reactor operator license is required.
1 Preferred experience includes advance knowledge of electronics, computer programming or other valuable laboratory discipline.
B.
Ilealth Physicist
4
' The purpose of the health physicist is to direct monitoring and training programs in order to protect the reactor and laboratory personnel from radiation hazards, and to assure compliance with federal, state, and UT Austin regulations. Additionally th: IIP a<! ministers the Laboratory's safety program and provides technical assistance to all personnel using ra<liation and radioacFve materials at the reactor facility.
Qualifications for this position are a Bachelor's degree in health physics, radiological health, nuclear engineering, or nuclear medicine. Preferred qualification is a Master's degree in health physics, radiological heelth, nuclear engineering, or nuclear medicine.
C.
Other Staff An administrative secretary aids in the prepara: ion of reports and documents. Other stafT, students or researchers, are employed as projects warrant. The minimum staffis considered to consist of a laboratory supervisor, nuclear techmcal specialist (technician), health physicia, and part-time technician. Additional technical support is also available from faculty members of the Mechanical Engineering Department employed to teach courses in the Nuclear Engineering Program.
D.
Appendix A-5 contains a block diagram of the administrative structure.
Specific data on key personnel is contained in Appendix A-6,8.
70.22(a)(7)
Facilities and Equipment for llandling Special Nuclear Material 1.
Areas of storage and use:
A.
All the special nuclear materials described in this license are stored in Building 159, Room 1.104, which contains a TRIGA nuclear reactor, j
Construction of the room consists of fireproof exterior walls, previsions for continuous radiation monitoring, and controlled access monitoring.
1.
Routine assembly, open. tion and storage of the subcritical core is in open areas of the reactor laboratory room. Core storage is in a 55 gallon barrel protected from exposure to combustible materials.
2.
The fuel pellets are assembled in the reactor laboratory or in adjacent controlled laboratory areas. Storage of the pellets is in a I
safe located in the reactor laboratory or with the cylindrical core.
l 3.
The plutonium-beryllium neutron sources are stored in a 16 foot deep storage well located in the reactor laboratory. Because of the i
value of the plutonium-beryllium neutron sources as calibration I
i standards, the sources may be transported in an appropriate shipping container to other laboratory facilities for temporary use.
B.
All materials are stored such that radiation levels at the container surfaces are less than 2 mr/hr.
C.
Appendix A-9 contains a diagram of the plutor.ium-beryllium neutron source shipping container.
11.
Shields, equipment and handling devices.
A.
The low specific activity of the non-operating suberitical core material allows for direct handling of materials. A polyethylenejacket protects the core assembly disk units against the small risk of radioactive contamination from the fuel pellet disks. Tweezers and small lead shields or other shield material are available to handle radioactive foils generated by neutron exposure in the suberitical assembly. Signs and rope are available to define radiation areas during assembly olcratio l
l B.
Routine handling of the plutonium-beryllium sources is accomplished with long handled tongs and long threaded rods. Shielding material such as l
paraftin, borated polyethylene, lead, concrete block, and shield casks are available to provide improved radiation safety in various neutron source applications.
Measurirg and monitoring devices l
A.
Personnel monitoring devices are required of all persons working in the laboratory with radiation sources. Film badges for laboratory personnel that are sensitive to gamma radiation (minimum measurable quantity
("M")of 10 mrem), energetic beta ("M" nf 40 mrem), fast neutron ("M" of L
20 mrem), and thermal neutron ("M" of :0 mrem), are piovided by l
Landauer. Direct-reading pocket dosimetus (ionization chambers) are available for dose n ca.;urements of gaman radiation (0-200 mrem). A l
TLD measurement system with several detectors (0.lmr/hr-100,000 R/hr) l are nko available for dose evaluations.
B.
Portable radiation monitors utilized in the facility shall have the capability to detect alpha, beia, gamma, and neutron radiation. Operational t
l parameters should include the ability to detect alpha above 4 MeV, beta l
above 100 kev, gamma and x n.Jiation above 7 kev, and neutrons over the energy range from 0.025 (thermal) to about 10 MeV. In addition, suflicient portable innruments shall be on hand to detect radiation fields at ranges of up to 50 IUhr for gamma and neutron radiation. Tbc Nuclear
Engineering Teaching Laboratory shall maintain these portable radiation detection instruments, or radiation detection instruments with equivalent performance characteristics (i.e., range, sensitivity, type of radiation detected) as follows: For alpha, beta, x-ray, and gamma radiation -
Victorcen Model 450B lon Chamber, Eberline Model RO-2A lon Chamber, Victorcen Model 190 Thyac V Survey Meter with ti.in-window, GM type probe (model 489-35): neutron detection and dose measurement
- Eberline PRS 2 and/or Eberline PNR-4 Lin-Log Neutron Remmeters.
C.
Specialized detection systems are available for analytical radiation measurements that are routinely required in a neutron activation analysis laboratory. The reactor room is continuously monitored by area radiation monitors with preset alarms (5 mr/hr) and a continuous air monitor with filter for particulate monitoring that also provides an audible alarm indication. A gamma spectroscopy system (HpGe) and alpha-beta windowless proportional counter plus other miscellaneous detectors and equipment represent substantial capability to analyze radioactive materials.
Iloth BF proportional counters and U-235 fission counters with associated 3
electronics are available to monitor and demonstrate operation of the suberitical assembly. Other detection systems, such as gaseous, scintillation or solid state detectors, allow students to count neutron activated foils.
IV.
Radioactive Waste Disposal A. Sources of radioactive waste material from the operation of the suberitical assembly are slightly contaminated from the polyethylene impregnated fuel pellets, activation products exposed in the assembly, and fission products generated by operation.
II.
Provisions exist through the Radiation Safety Office for the collection and disposal oflow level radioactive waste materials such as gloves, rags, and paper created by routine handling and maintenance of the assembly.
Disposal of materials to the sanitary sewer system are also monitored by the Radiation Safety Officer as allowed by state licenses. Subcritical 2
irradiations are at fluxes of-10"n/cm /see for a few minutes to hours. In general, foils or materials irradiated in the assembly are short half-life and reusable, and thus do not represent a waste material. Alternatively, said materials or foils may be stored until the radioactive hazard diminishes.
C.
Calculations indicate that the total fission product inventory of the assembly should not normally exceed several microcuries of fission product activity. Contained as an integral part of the assembly the activity is primarily a potential hazard to handling of the assembly and is rot
considered to be waste until the assembly is decommissioned.
(Calculationsin Appendix A-10).
70.22(a)(8) Safety Procedures to protect heu'th and minimize danger to life or property.
I.
Procedures are applied to establish safe conduct of activities with radioactive materials and radiction sources. The procedures in effect are to satisfy various requirements of federal USNRC licenses for special nuclear materials and state
'I DilBRC licenses for radioactive matericts. Procedures are reviewed by stafT, researchers and students. The r: actor supen*isor drafts procedures and aporoves changes. Substantive changes to procedures ax reviewed by the Nuclear Reactor Committee. The Procedu~:s are categorized into four basic functional groups; monitoring, calibration, operation, and einergency.
A.
Monitoring Procedures 1.
Access to laboratory areas is controlled by staff personnel.
2.
Film badges are required in the laboratory for staff when radiation sources are in use.
3.
Dosimeters are required for occasional visitors and unusual source handling conditions.
Status of special nuclear material is verified by periodic inventory (6 mo. cycle).
5.
Status of plutonium-beryllium is monitored by leak tests of source (6 mo. cycles).
B.
Operating Procedures 1.
Routine operation of the suberitical assembly shall consist of insertion of one af the plutonium beryllium sources (including fuel pellets and non-fissile foils) into the subcritical core assembly with any of the designed conditions for reflector or moderator components.
2.
Routine operation of the suberitical assembly will be authorized by the reactor supervisor.
3.
A survey of gamma and neutron radiation levels during operation will be made and an area radiation monitor with alarm will be continuously actis e or a monitor available at all times during operation.
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Cc Emergency Procedures 1.
Basic emergency procedures in effect for radiological emergencies in the Nuclear Engineering Teaching Laboratory are contained in '
Appendix A 12,16.-
2.~
Special precautions for material storage are required to minimize the potential for airborne radioactivity from exposure to fire hazards. Storage when not in use will be in a tightly closed 55 gallon barrel. The barrelis stored away from fiammable n aterials.
i The laboratory is constructe i of firewall construction. Leakage to the environment during normal operation is controlled by
- weatherstripping entrances and filtered exhausts.
- 11.
Trairing Program The priraary use of radiation sources and the suberitical assembly in the Nuclea l_
Engineering Teaching Laboratory is to support and extend the education of p
undergraduate and graduate students in basic concepts cf nuclear engineering. A i
portian of each student's education before performing experiments with radioactive materials will consist of material on radiation interactions, radiation L
hazards, dose measurements, and laboratory procedures. Experiments are performed with the supervision oflaboratory sbT Staff personnel are trained to i
handle materials by a combination of formal classroom education and laboratory training by other qualified stalT, depending on the nature of responsibility required.
111.
As Low as Reasonably Achievable E
The "as low as reasonably achievable" goal of a radiation safety progrem is supported by the procedures of the Radiation Safety Committee, Reactor Committee and Nuclear Engineering Teaching Laboratory. Many of the type of
_ experiments performed on a routine basis do not represent significant radiation -
doses. Less routine experiments may be required on occasion that represent more significant doses. Both occasional and periodic review of radiation doses of staff,
- students, and visitors is carried out by laboratory statTand the Radiation Safety Oflice. In general, radiation doses are in the minimal or near minimal category for_many routine experiments A review of significant deviations from expected values will be reviewed by the appropriate committee. Typica! values are L
- presented in Appendix. A-17.
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1 Appendix :A 1 - 3 SNM-180 l
License Application:
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Appendix A -4.
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License Application October 1997 i
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A41 Schematic of Assembly A4-2 Cover Page Lockheed Report A4-3 Assembly Configurations A4 4 Multiplication Values I
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0 VITA BERNARD W. WEHRING Education B.S.E. (Physics)
The Unkersity of Michigan 1959 B.S.E. (Math)
The Unkersity of Michigan 1959 M.S. Physics UnNorsity of luinois 1961-Ph.D. Nucl. En0r.
Uniersity of l'ainois 1P66 1
Ernploymenf 1959 (summer)
The Baboock and Wiioor Co., Atornic Energy Division 1960,1961 Isummer)
Autonetics, A Dkision of North American Aviation 1959 1962 Teachin0 Assislatt in Physics, University of lilinois i
1962 1963 Research Assistant in Nuclear En0 mering, Universlty of luinois 1966 1970 Assistant Professor of Nuclear Engineering, Unkersity of luinois 1970 1977 Associate Professor of Nuclear Engineering, UrMrsity oflilinois 1977 1984 Professor of Nuclear Engineering, University of luinois 1981 1982
- Revoking" Assistant Dean of Engineering, University of 'minois 1984 1989 Professor of Nuclear Engineering, North Carohna State University 1984 1989 Director, Nuclear Reactor Program, North Carolina State UnNorsity 1989-present Professor, Mocinical En0ineering, The University of Texas at Austin 1989 present Director, Nuclear Engineering Teaching Laboratory, The UnNorsity of Texas at Austin Society Mernbershio American Nuclear Society - Follow Member of ANS 5.2 Working Group and I
ANS Standan$s Commutee American PhysicalSociety Member Instuute of Electrical and Elodronics En0 neers - Member i
Honors Tau Beta Pi Atomic Energy Commissica Special Fellowship Syna XI American Men and Women of Science N's Who in Alons Best Paper Award, American Nuclear Society, Radiation Protodion and Shielding Division, June 1978 N's Who in Tecir,eicgy Today Physics and Related Disciplines intemational N's N in Energy and Nuclear Sciences Who's Who in Engineering Who's N in America i
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Other imoorthrs inicnnation One of Profesror Wehrt 's thesis studerts, G Dilorio, won the 1977 Mark Mes Award given by the American Ntdear y for outstanding graduate research h nuclear science and engineering. M nationwide competition, Dr. Dsorto's paper, HLAWATHA: A Fission-Fragmert Recoil Mass Spectrometer,* was )Lriged best original technical paper submitted for the award.
4 Professor Wehring's fission research was listed ard described h the two report series
- Progress in Fission Product Nuclear Data' which is published by the Nudear Data Section of the intemational Atomic Energy Agency (1977 83) ard the
- Actinide Newsletter" which is published by Oak Ridge National Laboratory (1981 83).
Rasaarch For Professor Wehring's doctoral research, he designed and buit a unique bert-crystal spectrometer for the rneasurement of characteristic x rays emitted in fission of U 235. This was the first measurement of x rays coincident with fission using a spectrometer capable of resolving Ka x rays of adjacent Z fission fragments.
As a member of the family W the Univpsity of Isinois, he initiated and guided multiparameter experimental studies of prompt and delayed x rays and gamma rays emitted by fission fragmerts.
Besides determining the amounts of particular types of radiation emitted by radioadke fission fragments, those measuremeras also gave information about the elements formed h fission, the types of transitions in excited fission fragments, and the nuclear strudure of neutron rich nuclei.
Ho provioed mahr guidance in measurements of beta rays from U-235 and Cf 252 fission fragments and was responsible for the unfolding technique and errpirical fitting scheme used in this research. Although the time dependent measurements on the sportaneous fission of Cf-252 are unique, the resuts of the measuremerts on thermal neutron fission of U 235 were more importart and were incorporated Ire fission reador decay heat standards.
Professor Wehring init'sted an experimental program to make direct physical measurements of the nuclide yields h thermal-neutron fission using the time of flight technique. A new fission-fragment recol mass spectrometer, HlAWATHA was conceived, designed, and constructed.
Operating on a unique principle, HlAWATHA achieved 0.5-amu mass resolution for both light and heavy fragments. The best mass resolution previously obtained for this type of experiment was 2.0 amu. An event by-event energy loss measurement was used to idertify fragmert atomic numbers. The developmert of this technhue required a study of fission-fragment slowing down more detailed than had previously been attempted.
He also hitiated raisearch at the University of luinois h the area of recou spedroscopy. By using pulse-shape discrimination on the output of an NE 213 organec scirginator, neutrons, measured by proton recoil, were sorted from gamma rays which were measured by Compton electron recoil.
A spectrometry system was developed and was used to measure energy spectra of nevirons and gamma raysleaking from homogeneous spheres containing neutron sources. The results were compared to calculated spedra as tests of mutigroup cross section sets for materials of irterest to rission and fusion reactor development.
Research started at the University of Ilinois and continued at North Carolina State University incluoed the development of the solid state nuclear track detector CR 39 for t se as a pradical fast-neutren dosimeter and also for use as a research tool h microdosimetric measurements.
Research started at North Carolina State University included the investigation of advanced alpha-particle detectors made of hcavy elements as allematkes to silecon surface-barrier detectors for the '1 oil neutralization technique
- of alpha-particle diagnostics in fusion reactors with high neutron backgrounds. CdTo and Hgl2 detectors were wnsidered and tested for radiation response and radiation damage charaderistics.
Vitar96-97 2
Professor Wehr6ng sieo :ionsborated with 3 faculty members W North Caronna State Universky on an emperimeraal demcostration of a decrease in tie high-heat-flux erosion of a inslottal surface e
due lo the presence of a strono parasol maOnetic field. This Magnetic Vapor Shieldm0 effect has appication to hi0h-power switchin0 devices, gun barrels, tal guns, and beam targets. Of the original members of the team, he was the only one who had experience in " pulse power,'
As director of the Nuclear En0ineering Teachin0 Laboratory at The Unkersky of Texas, Professor Wehrirg has established a plan for the ful utAzation of the capahanies of The Unkersty of Texas researcti reactor. Research actkties initiated under his supervision include neutron depth profiling, design and construction of a cold neutron source, design and construction of a unique i
convergirg neutron guide, cold neutron prompt gamma adkation analyst.. neutron radiography and tomography, and desion and construction of a reactor based slow postion beam facilty. He
)
has also formutJted preliminary designs for an utra cold neutron source, a neutron reflectrometer, and a neutron powder diffradometer stress analyzer.
The Texas Cold Neutron Source is one of four reactor ooid neutron sources h the U.S., the cold-neutron prompt gamma activation analysis system is one of two in the U.S., and the reactor based j
slow postron beam faciity when I becomes operational wM be one of two in the U.S. Professor Wehring has had cornplete technical responsibility for these researcti and development projects.
With sufficient operational staff, the Nuclear Ergineering Teachog Laboratory would become the premier university research reactor in the U.S. for cutting edge neutron research.
Professor Wehring has also participated in experiments using charged particle accelerators at ANL (tandem ard linac). ORNL (tardem), and LANL (Van de Graaff).
Dissertatbn Students Supervised The University of lilinois:
Bohn (Wyman)-
1968 TsouNanidis(Wyman) 1933 Long (Wyrnen)-
1969 Shapiro (Wyman)-
1970 S99 van -
1972 Lerche (Wyman)-
1972 Knief (Wyman)-
1972 Rouins (Wyman)-
1972 Withee (Wyman)-
1973 Johnson (Dorning) -
1975 Bucher in Physics -
1975 Lt>inrAl -
1976 Dilono -
1976 Ingersol(Doming)-
1977 Strlttmatter -
1978 Hertel-(Dorning)-
1979 S. Lee -
1983 The University of Texas at Austin:
Kim, Jong Youl,
- Neutron Focusing System for Texas Cold Neutron Source,' 1993 Vega Carrillo, Hector " Neutron Field Characterization in the Vcinity of a PET Cyclotron,' 1995 Rios-Martinez, Carlos,
- Prompt Gamma Activation Analysis using the Texas Cold Neutron Source,' 1995 Cheng, Kuo-Pen.
- Measurement and Calculation of Gamma Dose Localization in Gadolinium Neutron Capture Therapy,' 1996 Vita'96 97 3
l Other Experjapca i
Responsible for the development of the courses NE 351, Nuclear Engineering Laboratory, NE 4901, Nuclear instrumordation, and NE-490N, Nudear Data Analysis, Urhersey of lilinois.
Shared responsibilty for the development of the courses NE 347, introduction to Nuclear Engineering, NE-421, Interaction of Radiation with Matter NE 451, Nuclear Reador Laboratory, and NE-400F, Fission Physico, Urhersity of lilinois Consultart for Construction Engineering Research Laboratory, Cnampaign, lilinois,1970 71, Sabbctical Leave of Absence, Van de Graaff Laboratory, Oak Ridge National Laboratory.
Fau1973.
Extramural Teaching, Decatur, lilinois, Spring 1974.
S Contract with the Van de Graaff Laboratory, Oak Ridge National Laboratory,1975-77.
Faculty Research Appointment wili; Applied Physics DMsion, Argonne National Laboratory, 1975 77, Cross Section Evaluation Working Group subcommittee, Fission Produd and Decay Data, Brookhaven National Laboratory,1975-present.
Member of the Radiation Biophysics and Bioengineering in Oncology Training Program, University of Illinois,1977-84.
Consultant for Applied Physics Division, Argonne National Laboratory,19771979.
Consultant for Theoretical Division Los Alamos ScientWic Laboratory, 1977 79.
Outside User, Superconducting Heavy lon Linac, Argonne National Laboratory,1981 1904 Responsible for the development of the courses NE 202, Fundamental of Nuclear Energy, NE 520. Radiation and Reactor Fundamentals, and NE 521, Nuclear Laboratory Fundamentals, North Carolina State University.
Princioal invedimtor on Grards and ContrnMe NSF, ' Study of Fission Fragmert Photons Having Energies Below 200 kev,* 11 1-68 to 11 170 and 315-71 to 3-15 73, with M. E. Wyman, $165,700.
NSF, *Experimertal Study of Fission-Fragment Stopping Powers and A Direct Determination of the Nuclide Yields in Thermal Neutron Fission,' 6173 to 1130-74, $25,000.
NSF, " Study of Fission Fragment Photons and Electrons,'12-173 to 5-3176, with M. E. Wyman,
$81,200.
NSF,' Experimental Stt' dies of Fission Pagment Stopping Powers and Diet Nuclide Yield Measuren,ents," 4175 to 9 30 76 a*d 3177 to 8 3179, $134,300.
l Varian Cortact *Measuremerts and Calculations of Fast-Neutron and Secondary Gamma-Ray Leakage Energy Spectra From Bulk Media,*10-25 76 to 3 25-78, with J. J. Doming,
$3,000.
NSF,
- Data Acquisition System Ior Experimertal Rosearch," 9-177 to 2-28-79, $16,500.
NSF, " Data Acquisition System for Experimental Studies in Nucleonics,' 715 78 to 6 30-80,
$25,800.
Vita /96-97 4
.-r rr-u-m--
a-*
4 NSF,
- improvements in Nuclear Engineering Laboratory instruction,' 101 79 to 3 3142,
$17,500.
US DOE,'TFTR Alpha Extradion and Measuremert,* 1 143 to 12 344 and 2144 to 13145, with G. A. Gerden,462,000.
US-DOE, *TFTR Alpha Extradion and Measurernert Development and Testing of Advanced Alpha Detectors,* 2185 to 13146, $26,418.
Electrical Utilities, *Equtwnere Freon PWR Loop," 121645 to 12 3147, with J. R. Caves and P. J. Turinsky, $50,000 Virginia Power Company; $50,000 CaMina Power and Light Company, $50,000 Duke Power Company.
UJ DOD,
- Proof of Principle Experirnent for Magnetic Vapor Shield Mechanism,' Equptrert, FY 1986-87, wNh O. Auciello, O. Hankins, and J. Gilligen, $86,000.
US DOD,
- Control of Surfaos Melting and Ablation in ElectromaOnetic Launchers VIa the Magnetic Vapor Shield Mechanism,' 715-87 to 1014-89, with O. Auciello, O. Hankins, and J. Gilligan, $300,000.
Texas ATP. " Development of a Cold Neutron Source at The Unkersity of Texas Naclear Reactor,'
1190 to 12 2191, $207,000.
US DOE,
- Data System lor The Unkersity of Texas Reactor, Phase 1,11, and Ill",9190 to 8 3193,
$74,077.
US. DOE,' instrumentation for The University of Texas Reador,' 9193 to 8 3195, $26,506.
US NRC,'An Expert System to Enhance Software Reliability ' 9190 to 12 30 94, with T. L. Bauer, $99,998.
USOOE, " Study _of Neutron Focusing at the Texas Cold Neutron Soerce,' 415-92 to 414 95, with K. Unio, $201,449.
ANRCP (US DOE),
- 6195 to 8 3197, with N.M. Abdurrahman, $342,011.
Texas ATP, " Reactor Based Intense Positron Beam for Materials Characterization," 1 1-96 to 12-3197, K. Onl0, Pl, UT Austin and A. Koyman, Pl, UT Arlington, $427,920.
Vitn'96-97 5
.m.
4 1,
L Brideot B. W. WQ and M. E. Wyman, 'nme Delays in K X4y Emission During ThermalFissionof U 235, Appl. Phys.LesersI 181(1906).
2.
L Bridwet. M. E. Wyman, and B. W. W mring, Haf4.ives and YleMs of X Rays from Thermal Fission of U 235 and Pu 230,* Phys. Rev.1.(1,963 (1988).
3.
B. W. Wehrine and M. E. Wyman,' Sent Crystal rometer Measurement of the intenalties of X Rays Coincident with Fission of U 236,*
. Rev.11Z,1083 (1967).
4.
E. M. Bohn, B. W. Wehring, and M. E. Wyman, '9Asaeurement of X Rays as a Fundion of Maas in the Thermal Fission of U 236,* Appl. Phys. Lellers 12,199 (1908).
5.
B. W. Wehring and M. E. Wyman *A Bent Crystal Spectemeter lor the Weasurement of K X Rays Coincellent wth Fleelon," Nucl. Instr. Methods 11,149 (1988).
l
- 6.
B. W. Wehring, P. E. Rohan, N. L Shapiro, and M. E. Wyman, 'The Response of Double-ScintWator Fission Fragment Detodors to Cl 252 " Nucl. Instr Methods $1,330 (1988).
7.
A. B. Long, B. W. Wehring, and M. E. Wyman, " Procedure for Determining the Parameters
- from a FisslorFFra0 ment Energy Spectrum,' Rev. Sol. Inser. 38,1506 (1988).
j 8.
N. Tsoullanidis, 8. W. Wehring, and M. E. Wyman, 'The Use of an Analytical Response i
Function for Unfolding Beta Spedra," Nucl. Instr. Methods 22,98 (1969).
9.
A. B. Long, B. W. Wehring, and M. E. Wyman, ' Times of Emission of K X Rays from Cf 252 I
Fission Fra0ments of Known Mass,' Phys. Rev 181,1948 (1900).
10.
E. M. Bohn, B. W. Wehring, and M. E. Wyman, Prorryt K X Reys as a Function of Fragment Mass and Total Kinetic Energy in the Thermal Finaion of U-235,* Phys. Rev 138,1909 l
(1969).
11.
N. TsouNanidis, B. W. Wehring, and M. E. Wyman, 'nieasurerrents of Time Dependent f
Energy Spectra of Beta Rays from Uranium-235 Fission Fra0ments," Nucl. Sci. Eng. A3,42 (1971).
12.
N. L. Shapiro, B. W. Wehring, and M. E. Wyman, "Intemal-Conversion Electrons Emitted by Different Elements in the Fission of Cf 252,* Phys. Rev. C.1, 2464 (1971).
13.
R. A. Lerche, B. W. Wehring, and M. E. Wyman, " Effects of 00 Depost Thickness on 4
2 Fission-Fragment Double Kinetic Energy Measurements, Nuci. Instr. Methods.1A1, 287 (1972).
14, R. A. Lerche, B. W. Wehring, and M. E. Wyman, ' Timing Wak and Time Resolution Estimated by Least Squared Fitting,' Nuct inst. Methods 1A1,599 (1972).
.15.
R. A. Kniet, B. W. Wehring, and M. E. Wyman, " Study of Fragment Beta Decay in Spontaneous Fission of Cf 252,* Paper presented at the APS Meeting, At>uquerque, New Mexico, June 1972.
16.
B. W. Wehring and W. J. Sumvan, " Study of Surface Barrier Detodor Response Using
. FissiorFFragment Channeling,' Paper presented W the APS Meeting, Albuquerque, New Mexico, June 1972, 17.
R. A. Leiche, B. W. Wehring.'and M. E. Wyman, " Prompt Timing Response in X-Ray, Heavy lon Experiments UsinD Nel(T1) and Surface Barrier Detectors,* Nuot instr. Methods 102, 321 (1973).
Vita /96 97 6
v h
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18.
E. M. Bohn, R. A. Lerche, A. B. Long, and B. W. WoMng, ' Mass Resolutbn in Fission-Fragment Double-Kinetic-Energy Measuroments,' Nucl. Instr. Methods 31, 005 (1973).
19.-
- 8. W. Wehring, "Use of Particle Channelirg in TOF Fissbn Fra0mont Measurements,"
Trans. Am. Nud. Soc.1A,55 (1973).
1 20.
B. W. WeMrg, 'Ermitical Formulas lor Time Dopendent Beta Spectra for U 235 Fission
- J Trans. Am. Nud. Soc.18. 60 (1973).
21.
R. A. Lerche and B W. WoMag, *Effed of Thin Absorber on Fission Fragment Detector Energy Calibration," Nucl. Instr. Methods 111,137 (1974).
22.
R. A. Kniet B. W. Wehrin0, and M. E. Wyman. ' Measurements of Egallibrium and Time-Dependent Energy Spectra of Beta Rays from CalNomium252 Fission Fragments," Nucl.
Sci. Eng.12,47 (1974).
23.
W. J. Sulikan and B. W. WeMng,
- Study of the Use of Parte Channeling in Time of Flight Fission Fragment Mass Yield Measurements,' Nucl. Instr. k shode 11129 (1974).
24.
R. A. Lorc!se B. W. Wehrino, and M. E. Wyman, ' Times of Emissions of K X Rays from U-135 Fission Fragments of Known Mass,* J. Appl. Phys.,15,2327 (1974).
25.
R. H. Johnson, B. W. Wehring, and J. J. Domin0, 'NE 213 Neutron Spectrometry System for Measurements to 15 M1V,* Ni Aar Croma Saetions and Technobav. EdNed by R. A.
Schrad and C. D. Bowm,in, NBS Spec. Publ. 425, pp. 62 65, (U.S. Govemment Printing Cilice, Washington,1975).
26.
R. H. Johnson, J. J. Doming, and B. W. Wehrin0,
- Integral Test of Cross Sections Using Neutron Leakage Spectra from Spheres of iron, Niobium, Beryllium, and Polyethylene,
- Ni A= Crona Sections and Technobow? Edned by R. A. Schraak and C. D. Bowman, NBS Spec. Publ. 425, pp.100172, (U.S. Govemment Printing Office, Washington,1975).
27.
G. D. Ahon, J. A. Biggerstaff L Briowou. C. M. Jones, O. Kessel, P. D. Minor, C. D. Moak, and B. W. Wehring,' Absolute Charge State Yields of 20 MeV lions Scattered from Argon and Xenon,* Proc. 1975 Particle Accelerator Coni.-Acceleralor En0ineering and Technology, March 1214,1975, Wash., D.C., IEEE Trans. Nucl. Sci. NS 22. 1885 (1975).
28.
R. H. Johnson, B. W. Wehring, and J. J. Doming, " Smoothing in the FERDOR Method of Neutron Spectrum Unlolding,* Trans. Am. Nucl. Soc. 22,798 (1975).
29.
R. H. Johnson, B. W. Wehring, J. J. Domino, and D. T. Ingersou, 'CalWomium 252 Fast-Neutron Spectrum Measured to 15 MaV," Trans. Am. Nucl. Soc. 22,727 (1975).
30.
R. H. Johnson, J. J. Doming, and B. W. WeMng *Inlegral Tests of Neutron Cross Sections for iron Above 1.0 MeV,* Trans. Am. Nucl. Soc. 22,799 (1975).
31.
R. G Bucner and B. W. WeMng, ' Stopping Power of Nidel lor Fission Fragments-21 Dependence,* Trans. Am. Nucl. Soc. 22,151 (1975).
- 32. L B. E1rldwell, J. A, Biggerstaff, G. D. Allo;,, C. M. Jones, P. D. Miller, Q. Kessel, and B. W.,
Wehring.
- Multiple Electron Loca Cross Sections for 60 MeV l+10 n Single Collisions with i
Xenon, *BearnFoil Snecimaconv. Edted by L A. Sellin and D. J. Pegg, pp. 657 664, (Pienum Publ. Corp., New York,1976).
'53.
B. W. Wehring and R. G. Bucher, ' Stopping Power for lors of Intermedale Atomic Numbers
- Beam foi Spectroscopy. Ested by L A. Sellin and D. J. Pogo, pp. 679 686, (Plenum Publ. Corp., New York, (1976).
Vita /96-97 7
=
34.
R. H. Johnson and B. W. Wehring, "The FORIST Unfold %g Code,' Radiatlan Energy Spectra Unfolding. Proceedings of a Radiation Shielding information Corner Seminae.
Workshop, Oak Ridge National Laboratory, AprH ib13,1976, pp. 33 39 ORNURSIC 40 (1976).
35.
D. T. Ingerson, B. W. Wehring, and R. H. Johnson,
- Neutron Resporse Merts for Unlolding NE 213 Measurements to 21 MeV,* Radiation Enarav Snactra Unfolding. Proceedmg of a Radiation Shielding information Corter Seminar Workshop, Oak Ridge National Laboratory, April 1213,1976, pp. 47 53, ORNURSIC 40 (1976).
36.
D. T. Ingersoll, B. W. Wehring, and R. D. Starr,
- Gamma Ray Response of NE 213 Measured Between 2 and 11.5 MeV,* Badiation Enarav h*n Unf2JdlDG, Proceedings of a Radiation Shielding information Corner Seminar Workshop, Oak Ridge National Laboratory, AprH 1213,1976, pp. 55-64, ORNURCIC 40 (1976).
37.
R. B. Strittmatter and B. W. Wehring, ' Alpha-Particle Energy Straggling h Solids,' Trans.
Am. Nud. Soc. 22,120 (1976).
38.
D. T. Ingersoll, B. W. Wehring, and R. D. Starr,' Gamma Ray Response of NE 123 Measured Between 1 and 11.5 MeV,' Trans. Am. Nud. Soc. 22, 631 (1976).
39.
Gino Dilorio and B. W. Wehring,
- Performance of HlAWATHA, A Fission-Fragment Mass Spedrometer,' Trans. Am. Nucl. Soc. 22, 523 (1976).
40, R. B. Strittmatter and B. W. Wehring, ' Alpha Particle Energy Straggling in Solids
- Nucl. Instr.
Methods 125,173 (1976).
41, R. J. Lipinski and B. W. Wehring.
- Element Yields in Cf 252 Spontane>us Fission From Measured XRay Muttplicities," Proceedings of the Intemational Conference on the irteractions of Neutrons with Nuclel, Lowel, Massachusetts, July 6-9,1976, p.1416, CONF 76015 P2, Tech. Information Center, ERDA.
- 42. Gino Dilorlo and B. W. Wehring, " Fission-Fragment Mass-Yield Measurements Using HIAWATHA,* Proceedings of the Intemational Conference on the Itteractions of Neutrons with Nuclei, LoweN, Massachusetts, July 6-9,1976, p.1404, CONF 760715 P2, Tech.
Information Center ERDA.
43.
R. J. Lipinski and B. W. Wehring,
- Element Yields in Cf 252 Spontaneous Fission Determined from Measured X Ray Multiplicities.* Trans. Am. Nuct Soc. 2.4,460 (1970).
44.
Gino Dilorio and B. W. Wehring, " Direct Physical Measurement, of Mass Yields for 235 (nth.f),* Trans. Am. Nucl. Soc. 2L 459 (1976).
U 45.
D. T. IngersoN, B. W. Wehring, and J. J. Doming, " Integral Tests of Niobium Cross Sections through Simukaneous Measuremerts of Neutron and GamrreRay Leakage Spectra,
" Reactor Shieldina*, Edited by R. W. Roussin, L S. Abbott, and D. E. Bartine, pp. 841 848 (Science Press, Princeton,1977).
46.
R. J. Lipinski and B. W. Wehring. *Elemert Yields in Cf-252 Spontaneous Fission De' ermined from Measured X Ray Multiplicities,' Phys. Letters Afdl,326 (1977).
47.
R. B. Strittmatter, R a Bucher, and B. W. Wehring, " Atomic-Nurrber Dependence of Flssion Fragment Energy Loss: Evidence for Z1 Oscillations,' Phys. Rev. A 15,2230 (1977).
48, R. K Johreon, D. T, Ingersoll, B. W. Wehring, and J. J. Doming, 'NE 213 Neutron Spectrometry System for Measurements from 1.0 to 20 MeV,* Nud. Instr. Methods 115, 337 (1977).
Vita /96-97 8
4 49.
D. T. Ingemed and B. W. Wehrtne, t..# Pulse-Height Roeponse of an NE 213 Scintutation Detector,' Nucl. Inser. Methods 14Z%, 1 (1977).
50.
G. Dilosto and B. W. Wehring HlAWATHA, A Fission-Fra0 mort Recol Mass Spectomotor,*
Nucl. Instr. Methods 11Z, 487 (1977).
51.
R. B. Stratmanw and B. W. Wehring, "Dimet Physioel Measurement of Nuchde Yields for
~
235 (nth.f),* Trans. Am. Nucl. Soc.12,862 (1977).
U 52.
C. J. Withee, B. W. Wehring, and M. E. Wyman, 'Weasurement of intemal Conversion Cascadin0 in U 235 Fiselon Fragments,"J. Appl. Phys. AR, 4627 (1978).
j 53.
N. E. Hertel, 8. W. Wehring, and R. H. Johnson, 'Comperleon of VITAMIN C Master Lerary i
Renaion Coos Sections tor lon weh Munigmup Cease Sections Genwesed ty the vim Monte Carlo Code,* F..tlamun Nudaar Cmaq-Spalan PmcanningL Proceedings of a Radiation Shielding tr6.ution Corner Seminar Workshop, Oak Ridge National Laboratory, March 1416,1975, pp. 01 190. ORNURSIC 41 (1978).
i 54.
N. E. Hertel and B. W. Wehring *Photoneutron and Cf 252 Neutron Dose Corgartoons for Radiothernoy Shielding.' Trans. Am. Nucl. Soc.18, 620 (1978)..
I 55, N. E. Hertel, R. Mortogul, and B. W. Wehring, " Effectiveness of Tun 0 sten and Lead in the Atteru.ation of Photonautrons," Abstracts. Second inlemational Congress, World i
Federation of Nuclear Medicine and Biolugy, September 17 21, 1978, Washington, D. C.,
j
- p. 78, Sept. (1978).
56.
R. B. Strtitmatter and B. W. Wehrino, " Direct Measurement of Nucilde Yields in Thermah Neutron Fission Using HtAWATHA," ProceedinOs of an intomational Conferette on Neutron Physics and Nuclear Data for Reactors and Other Appiled Purposes, Harwet, U.K.,
September 25 29,1978, pp. 223 228, (OECD Nuclear Energy A0ency,1978).
57.
D. T. Ingersou and B. W. Wehring, "Senskivity Ans Applied to an integ,ral Test of Niobium Cross Sections,' Ibaggv and Wh al dellMhr and Unomftalray Analynia.
ProceedinOs of a Radia' ion Shielding information Center Seminar Workshop, Ook Ridge National Laboratory, August 22 24,1978, pp.179189, ORNURSIC-42 (1979).
58.
N. E. Hertel, B. W. Wehring, and J. J. Doming, " Integral Tests cl ENDF/B IV High Energy l
Neutron Cross Section Data for Tungsten,:Trans. Am. Nucl. Soc 32,631 (1979).
59.
R. H. Johnson, K. R. Koch,, B. W. Wehring, and N. E. Hertel, "TLD Measutoments in an iron Sphere Containing a DT Source,* Trans. Am. Nucl. Soc. 32, 632 (197te).
60.
B. W. Wehring,06 M. Swtit, and D, Weidenfeld 'A MultichanneFAnalyzer/ Microcomputer System lor Nuclear Laboratory Instruaions," Trans. Am. Nucl. Soc. 33,107 (1979).
61.
B. W. Wehring, J. J. Domino, N. E. Hertel, D. T. InDersoE, and R. H. Johnson. ' Benchmark Shielding Problems Obtained from Integral Tests of Neutron Cross Sections,' Trans. Am.
Nucl. Soc. 33,666 (1979).
62.
G. M. SwWt, F. DolatshaN, F. H. Southworth, and B. W. Wehring. "Modeling the Neutronics of inertial ContinemerW Fusion Pellets," Trans. Am. Nucl. Soc. 33,' 33 (1979).
63.
R. B. Strttmauer and B. W. Wehririg, Tra0 ment Atomic-Number identWication Using a Gas t
lontzation Chamber in Fission Yield Measurements,' Nucl. Instr. Methods 1AA, 473 (1979).
i 64.
N. E. Hertel, R. H. Johnson. J. J. Doming, and B. W. Wehrino, " Measurements and Analyses of Neutron Transport Through Iron." Proc. Intemational CorWorence on Nuclear Cmes Sections for Technology, Knoxvnle, Tenn., October 22 26, 1979, N.B.S. Special Publication 594, pp. 563 576, (U. S. Government Printing Office, Washington, D.C.1980).
Vitar96-97 9
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- 85. n H. Johncon, B. W. W and J. J. Doming, smooshing h Neutron Spectrum Untolding try the FER Method," Nucl. Sol.
22,93 (1990).
,j 88.
N. E. Hertel and B. W. Wehring, ' Absolute MontortnD of DD and DT Neutron Fluences i
Using the Associated-Particle Technique," Nucl. Instr. Methods 121, 501 (1980).
87.
B. W. Wehrin0, Shengdar Lee, Gary Swift, and R Stratmatter, tight Fiagmert j
independent Yields try ThermakNeutron Fission og 233,' Trans. Am. Nucl. Soc.11,551 U
(1980).
t 88 Shengdar Lee and B. W. Wehrin0, "Model for Ealimating independerd Yleids of Fission l
Prochds," Trans. Am. Nuct Soc. 31, 55? (1980).
89.
B. W. WehrinO, S. Lee, and G. Swift, ilpht Fragment independent Yistds for Thermak Neutron Fission of U-233,* HlAWATHA Technical Memorandum No.1, 29 pgs. UILU-ENG-80 5312 (1980).
70.
R. Ac, Gt Gordin, J. Durham, B. Wehring, W. Styger, T. Emoto, and F. Venneri,
- Dense -
Plasma Focus Studies with Solld State Nuclea' Tract Detedors,' Buu. Am. Phys. Soc.,
Series 11,.11, No. 8, p. 982, Oct.1980.
71.
T E. Blue, J. S. Durham, J. J. Reyes, B. W. Wehring, and J. W. Blue, " Fuel Density Radius Diagnostic for inertial Confinement Fusion Experiments,* Proc. IEEE 9th Symposium on i
EngineerinD Problems of Fusion Researd, Chicago, innois, Odober 28 29,1981, Vol. E,.
1051 (1981).72. T. Ham, G. Swm, J. Durham, T. Emoto,- and B. Wehring, "He 3 Spectrometer Unfoldin0,* Progress Report,81 pp. UILU ENG 815319 (1981).
73.
T. E. Blue, J. J. Reyes, B. W. Wehring, J. W. Blue, and W. K. Roberts, " Dosimetry weh CR-39 in a Phantom irractated by a p(43) Be Neutron Beam," Proc. 88th Solentific Assemtdy and Annual Meetin0 of the Radiological Society of North America, Chicago, il, Dec.1982,.
paper 829 (1982).
74.
T. E. Blue, J. S. Durham, J. J. Reyes, B. W. Wehrin0, J. W. Blue, and W. K. Roberts,
" Dosimetry and Microdosimetry of High Energy Neutron Beams in TE Liquid Using CR 30 Plastic," Proc. Heath Physks Society Great LAes Chapters Spring Symposium,
Dearbom,
MI, AprN 28-29,1983, p. 29 (1983).
75.
T. E. Blue, J. J. Reyes, J. S. Durham. B. W. Wehring, J. W. Blue, and W. K. Roberts,
" Dosimetry with CR-39 in TE Liquid for Clinical Neutron Beams,' Trans. Am. Nucl. Soc. (.4, 484 (1983).
78.
D. Mueller, a Gordin, B. W. Wehring, T. Emoto, and T. Blue *A Passive Approach to Measulament of A5ha Particle Energies in TFTR,* Bul. Am. Phys. Soc. 24.
No.8,p.
1071, November 1983.
77.
T. Blue, T. Less, and B. Wehring, ' Enchantment of Absorbed Dose BNCT lor pe3) and Be(22) Fast Neutron Beam," First inter Americ.an Meeting of M Physics, Chicago, ll,
~ July 1519,1984, paper D4, (1984).
78.
D, remia. B. Wehring, and G. Gordin," Temperature Effeds on the Energy Loss and Neutral Fradion of Alpha Particles in Carbon Foils,' 9uN. Am. Phys. Soc. 21, No. 8, p.1310 (Oct.
- 1986.
79.
S. J. Bet 00s, B. W.Wehring. and T. E. Blue, ' image Analysis System for SSNTD Readout,"
Trans. Am. Nud. Soc..(2,387 (19C4).
80, a Gordin,- D, Mueter, and B. W, Wehring, " Charge Neutralization by Foils to Study Alpha Edge Flux Produced in Magnetic Fusion Reactors", Fusion Tech. I, 180 (1985).
VitW98 97 10 1
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.j 81 T. E. Blue C. S. Wepprocht, J. W. Blue W, K. Roberts, and B. W. Wehrine, Et^Ji in 1
Neuten Therapy by Automatic Reedout of CR 39 SSNTDS
- Trans. Am. Nuct. Soc. E,-
434 (1985).
82.
N. E. Hortel, R. H. Johnson, B. W. WeMng, and J. J. Domine, ' Transmission of Fast Neutrons through an iron Sphere," Fusion Tech.1. 345 (1988).
i 83.
T. E. Blue, B. W. WeMng, S. J. Brtges. C. S. Wepprocht, J. S. Durham, and J. W. Blue, J
' Dosimetry in Fast Neutron Therapy by Automatic Readout of CR 39,* Nucl. Instr. Methode in Phys. Research Sid, 589 (1988).
l 84.
H.K.C.
B. W. Wehrin0, K. Verghese, and R. P. Gardner, 'Worte Carlo Simuistion of Neutron :saponse for He 3 Spearomotors,"Trans. Am.Nuct. Soc.52,839 (1988).
)
85.
J. R. Caves, B. W. Wehring, J. M. Doster, and P. J. Turinsky, "PWR Thermal Hydraulles Training Faculty for Engineers and Operators,* Trans. Am. Nucl. Soc.12,17 (1988).
88.
G. D. M' iller and B. W. Wehring, "Universley Research Reactors: Key in0rodients for I
Success," Trans. Am. Nud. Soc.12,371 (1988).
~ 87.
B. W. Wehring and K. V. Mani, 'Two Source Method for Determining F,adiation Counting Dead Time," Trans. Am. Nucl. Soc. D, 59 (1988).
- 88. a D. Meer and B. W. Wehring, *Multpurpose Prompt Germa Fr.culty,' Trans. Arn Nucl.
Soc.13, 181 (1988).
89.
K. V Mani and B. W. Wehring, 'OM Counter Dead Time and The Two Source Method,'
Thirty Second Annual Meeting of the Health 18hyska Society, Sat Lake Cty, July 5 9, 1987.
90.
O. Hankins, O. Auciono, M. Bourham, J. Gigigan, and B. Wehring, "Construdion of a Proof-of Principle Device for Testing the MVS Mechanism", Buu. Am. Phys. Soc.11. 32, No. 9, 1943 (1987).
91.
N. R. Parkh. W. K. Chu, B. W. Wehring, and G. D. Miter, Doron 10 Distribution in Silicon, TISi, and SiO2 UsinD Neutron Depth Profiling,* Trans. Am. Nucl. Soc.15, 211 (1987).
2 92.
J. Gilligan, M. Bourham, O. Auciello, O. Hankins, and B. Wehring, ' Fundamental Studies to Reduce High Heat Fbx Erosion of Surfaces," Fifteenth IEEE Intemational Conference on Plasma Science, Seattle, June fet,1988, Conference Rocctd, IEEE CatalDO No.
88CH2559 3,115 (1988).
93.
J. S. Durham, T. E. Blue, B. W. WeMno, M. Ragheb, and J. W. Blue, 'Microdosimetry in Neutron Therapr by Automatic Readout of CR 39 SSNTDs," Trans. Am. Nud. Soc.18,9 (1988).
94.
K. V. Mani, a D. Meer, and B. W. Wehring, " Health Physics Operation at the NCSU PULSTAR Research Reador," Thirty Third Annual Meeting of the Health Physics Society, Boston, July 4 8,1988.
95.
J. S. Durham T. E. Bbe, B. W. Wehring, M. H. Ra0heb, and J. W. Blue, "Micmdosimetry in Fast. Neutron Therapy by Automatic Readout of CR 39 Solid State Nuclear Track Detodors," Nuct. Instr. Methods Fhys. Rosearch B38. 319 (1989).
96.
J. Gilligan, O. Auciono, M. Bourham, O. Hankins, B. WeMng, D. Hahn, R. Moharti, and J.
l Stock, " Theoretical and Experimental Studies of the Vapor Shielding Mechanism for Surf aces Subjected to High Heat Fluxes," Fusion Tech.15,522 (1989).
97, J. R. Caves,1 M. Doster, G. D. Miner, B. W. WeMn0, and P. J. Turinsky, "The NCSU Freon PWR Loop," Trans. Am. Nucl. Soc. 52,30 (1989).
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98.
O. Har6 ins, J. Galgen, B. Wehrin0, M. Bousham, and O. Auoisto, "Muniple Use Plasme l
Laboratory for Graduale Fuelon Education," Trans. Am. Nucl. Soc. Et, 108 (1999).
99.
B. W. Wehrin0, K. V. Mani, and S. J. Han, "Corwersion of Tra& Size Distreutions Obtained by CR.39 to Microdosimetric Spedra,' Thirty Fourth Annual Meeting of the Heath Physico Society, Albuquerque, June 25-29,1989.
100. M. Bourham, O. Har61ns. O. Auciello, J. Stock, B. Wehring, R. Mohanti, and J. Omgan, l
' Vapor Shielding and Erosion of Surfaces Exposed to a High Heat Load in an l
Elodrothermal Accelerator,' IEEE Trans. Plasma Sci.11, 386 (1909).
i 101. J. R. Caves, G. D. Maor, B. W. Wehrin0. and R. W. Coment, 'NCSU Pressurtred Water R maor Physical Simulator,' IEEE Trans. Nuot Sci. 38,1990, (1989).
i 102. W; D. Booth, R. Carrera, B. Wehring, T. Parish, and T. Elevant, " Neutron and Alpha Celection for a Fusion Ignaion Experiment," 1990 IEEE Conference on Plasma Sci., IEEE i
Catalog No. 90 CH 28571,110 (1990).
103. B. W. Wehring.
- Direct Physical Measurements of independent Fission Yields W a 1 MW I
Research Reactor,' Trans. Am. Nucl. Soc. $1,104 (1990).
104. R. C. Woodard, T L Bauer, and B. W. Wehring, " Methodology for Development of Health l
Physics Procedures at Research Readors kl A0reement States," Twenty Fourth Midyear Topical Meeting of the Health Physics Society, IrmWrwM of Nrare NCRP and ICRP _
l Guidance and Revised 10 CFR Pad 20. pp.46 54, North Carobne Chapter of the Heath Physics Society and U. S. Nuclear Regulatory Commission, NRC-04-359,1991.
i 105. T. Emoto, K. Onlo, T. Bauer, and B. Wehring," Texas Cold Neutron Source," Applications of Cold Neutron Spectroscopy in Chemistry, Biology, and Physics. A Workshop W the National Insttutue of Standards and Technology, Gaithersburg, MD, June 4 5,1991.
106. T. L Bauer and B. W. Wehrin0, " Digital Control for The University of Texas TRIGA
- Trans.
t Am. Nucl. Soc. M. 250 (1991).
107. N. E Hertel, R. C. Woodard, H. R. Vega Carrito, and B. W. Wehring. *Bonner Sphere
'1 0
252Cf Source," Trans. Am. Nucl. Soc. M,472 (1991).
Measurements of D2 -Moderated 108. B. W. Wehring and T. L. Bauer, " Status of the University of Texas Research Reactor Program,' Trans. Am. Nuct. Soc. As,242 (1991).
109. N. E. Hertel, H. R. Vega Carrillo, A. B. Preece, B. K. Nabelsel, B. W. Wehring, C. A. Shriver, C. E. Johannes, and P. A. Jerabek, " Neutron Spectra Measured in the Vicinity of a PET Cyclotron,' Health Physics Society Annual Meeting, Columbus, OH, June 2125,1992.
110. K. Onio, T. L. Bauer, and B. W. Wehring, " Development of Neutron Beam Projects at The University of Texas TRIGA Mark I Reactor,' Thirteenth U.S. TRIGA Users Conference, Comell University, khaca, New York, May 18 20, (1992).
111. K. Onl0, T. L. Bauer, and B. W. Wehrin0. " Safety Aspects of the Texas Cold Neutron Source,' Trans. Am. Nucl. Soc. 65.135 (1992).
112. K. Onl0, T. Emoto, T. L. Bauer, and B. W. Wehring.? Design Features of the Texas Cold Neutron Source," Trans Am. Nuci. Soc. A5,134 (1992).
1 i
^
113, B. W. Wehring, K. Oni0, and T. L. Bauer, "Researdi at The UniversthW TexaW A Mark I l
Reactor,"The Joint meeting of the Texas Section of the American Faysical Och Texas Section of the American Association of Physics Teachers and Soclaty of Ph,t 4 2,udent, Rice Universty, Houston, Texas,7-8 Nov 1992.
+
l' Vita /96-97
.12 L
L L
l 114. K. Oni0, C. Rios Martinez, and B. W. Wehring.
- Performance of Texas Cold Neutron Source," Trans. Am. Nud. Soc. R 160 (1992).
,I i
115. C. Rios Martinez, K. Oni0. and B. W. WeMng.
- Development of a Prorgt Gamma Activation Analysis Facey W the Texas Cold Neutron Source,".hladad Nudoar Mexicaca A.C.,
Tercer (e.;,.no Anual Memorias,159 (1992).
I 116. K. One and B. W. Wehring,
- Neutron Depth Profiling W the UrMrsky of Texas Research Reactor,' Trans. Am. Nucl. Soc. E 163 (1993).
117. B. W. Wehring, K. One, J Y. Kim, and C. Rios-Martinez, ' Applications for the Texas Cold Neutron Source," Trans. Am. Nud. Soc. R 161 (1993).
118. J. Y. Kim. B. W. WeMng, and K. Onl0,
- Neutron Guide horlormance from Two-and Three-Dimensional Calculations," Trans. Am. Nucl. Soc. R 162 (1993).
119. GL k. Maer, N. E. Hertel, B. W. Wehring, and J. L. Horton, "Gado8nium Neutron Capture Therapy," Nud. Technology 102, 320 (1993).
120. K. Oni0, C. Rios Martinez, T. L. Bauer, and B. W. Wehring," Performance of the Texas Cold Neutron Source at Reactor Power,* Trans. Am. Nud. Soc. E 164 (1993).
121. B. W. Wehring, K. Onl0, K. P. Cheng, H. Vegatarrillo, J. Izewska, and J. Horton, ' Neutron Beam Filters for Gadolinium Capture Therapy Dosimetry Measurements at a TRIGA Reactor," Trans. Am. Nucl. Soc. E 163 (1993).
122. J. Y. Kim, B. W. Wehring, and K. Oni0,
- Converging Neutron Guide for Neutron Focusing at th6 Texas Cold Neutron Source," Trans. Am. Nud. Soc. R 166 (1993).
123. C. Rios-Martinez, K. Onl0, and B. W. Wehring,"ThermohWraulic and Neutronic Performance of the Texas Cold Neutron Source," Sociedad Nuclear Mexicana, IV.
Congreso Anual Memorias, Vol 1,148 (1993).
124. K. OnD and B. W. Wehring. *Recert Accomplishments in Neutron Beam Projects at the Universty of Texas Research Reador,* Trans. Am. Nud. Soc. 21135 (1994).
125. T. L. Bauer and B. W. Wehring, " Expert Systerns Connected to the University of Texas Research Reactor," Trans. Am. Nucl. Soc. 2.0,.38 (1994).
126. B. W. Wehring and K. Onl0, "The University of Texas Cold Neutron Source," Proceedings of intemational Seminar on Advanced Pulsed Neutron Sources: Physics ol/at Advanced Pulsed Neutron Sources, PANS 11, Dubna, Russia, June 1416,1995.
127. B. W. Wehring, J Y Kim, and K. Onl0, " Neutron Focusing System for the Texas Cold Neutron Source,* Nud. Instr, and Meth...i Phys. Res. A353.137 (1994).
128. K. OnD and B. W. Wehring.
- Neutron Depth Profiling W The University of Texas," Nucl.
Instr and Meth. In Phys. Res. A152,402 (1994).
129. K. On0, C. Rios-Martinez, and B. W. Wehring, "The University of Texas Cold Neutron Source," Nucl. Instr. and Meth, in Phys. Res. A352. 397 (1994).
130. C. Rios Martinez, K. Onl0, T. L. Bauer, and B. W. Wehring. " Performance of Neon-Thermosyphon in the Texas Cold Neutron Source," Trans. Am. Nud. Soc. 21,138 (1994).
131. K. Onl0 and B. W. Wehring. " Applications for the University of Texas Neutron Depth Profiling Facility," Trans Am. Nucl. Soc. 21,163 (1994).
132. K. Onic. C. Rios Martinez, and B. W. Wehring, " Prompt Ganma Activation Analysis wth the Texas Cold Neutron Source,* J. Radioanal. Nucl. Chem.192,145 (1995).
o Vitat96 97 13
133 B. W. W
, C. Rios4Aaniner, and K. Onio, " Cold-Neutron Gerrms Actkation Analysis F al the Universey of Texas at Austin,' Trans. Am. Nud.
22, 112 (1996).
<l I
134. H. R. VegaCarreo, N.E. Hestol, A. J. Teachout, and B. W. WeMng.
- Paired Thermoluminescord Dosimeter Technique in Bonner Sphere Spectometry,' Trans. Am.
Nucl. Soc. 22,356 (1995).
135. N. M. Abdurrahman and B. W. Wetring " Neutron laa0 no System lor Neutron Tomography, i
R&ds $,y, and Beam DiagnostLs," Trans. Am. Nucl. Soc. 22,154 (1995).
v 136. K. P. Cheng, K. Onl0, A. J. Teachout. N. M. Abdurrahman, and B. W. Wehring.
- Gadolinium Neutron Capture Therapy Dosimetry Measurements,' Trans. Am. Nucl. Soc. Z2,30 (1995).
137. B. W. WeMng and Y. N. Pokotileveld, of Utracold Neutrons and a TRIGA Pulse-A Marria0s Made in Heaven," Trans. Am. Nud.
22,153 (1995).
136. C. Rios Martinez. K. Onio, T. L Bauer, and B. W. Wehring,
- Operational Features of the 1
Cold Neuten Pr:
Garrms Activation Analysis Faculty at The Urdversity of Texas at Austin," Sociedad at Mexicana, VI. Con 0reso Anual Memorias Vol 1,333 (1995).
139. H. R. VegaCarrtlo, B. W. Wehring, and A. J. Teachout, "New Neutron Sources for Calibration Purposes," Sociedad Nuclear Mexicana, VI Congreso intomacional Anual, 218, (1995).
MO. A. J. Teachout, T. L Bauer, K. Onio, and B. W. Wehring, "A Case Study in Control of Access to Radiation Beams: Neutron Depth Profiling at the Nucisar Engineering Teaching Laboratory. The University of Texas at Austin," Accepted, American Nuclear Society Radiation Protection and Shielding Topical Meeting, April 21,1996, Cape Cod, MA.
141. K Onl0, and B. W. Wehring, "Nudear Analytical Techniques wth Neutron Beams at the UnNossity of Texas at Austin," Trans. Am. Nuct Soc. 21109 (1996).
142. B. W. Wehring, K. Onl0, A. R. Koymen, and A. H. Weiss, " Reactor. Based Slow Positron Beams.* Trans. Am. Nucl. Soc.2A,110 (1996).
143. Y. GL Jo, N.M. Abdurrahman, and B. W. Wehrino "Desi n of a Neutron Radiography 0
ColEmator System in a Through Beam Port at the TRIGA Roador," Trans. Am. Nucl. Soc. 21 113 (1996).
144, J. Y. Kim, K. Onio, and B. W. WeMng, " Neutron Focusing System for Neutron Capture Experiments," Accepted, The 5th Asian Sypmposium on Research Roadors (ASRR V),
May 29-31,1996. Toajon Korea.
145. B. W. Wehring K. P. Chen0, and K. Onio, "L.ow1ET Dose Calculations and Measuremerts for Gadolinium Neutron Capture Therapy,* Presented in 3rd Topical meeting on industrial Radiation and Radioisotope Measurements and Applications, IRRMA 1>6, October 6 9, 1996, Raleigh, NC.
146. B. W. Wehring, and K. Onl0, " Applications of Cold-Neutron Prompt Gamma ActivPlion Analysis at the Universky of Texac Reador," invted paper,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 lootopes,1997.
147. K. Onio, M. Saglam, B. W. Wehrin0, T. Z..Hossain, E. Custodio, and J. K. LoweN,
" Nondestructive Determination of Boron Doses h Semicondudor Malertals usin0 Neutron Depth Profiling," lEEE Proceedings, )0 Inlemational Conference on lon implantation Technology, Vol. 1,575 (1977).
146. K. 0n10, and B. W. Wehring.
- Neutron Depth Profiling Applications W The Universky of Texas Research Reactor," J. Radioanal Nuct Chem. Ul.273 (1997).
Vitar96-97 14
+- -
i i
I e
Resume Thomas L. Bauer i
Education:
i B.S. Physics, The University of Texas. 1971 M.S. Nuclear Engineering, The University of Texas 1974 Ph.D. Nuclear Engineering, The University of Texas -1978 Employment 1971-1978 Teaching. Assistant, Graduate Research Assistantr The University of Texas at Austin 1978-1980 Assistant Professor, Mechanical Engineering The University of. Texas at Austin 1980-1981 Research Engineer, Nuclear. Engineering Teaching Lab i
- The University of Texas at Austin 1981-present Assistant. Director / Reactor Supervisor, NETL The University of Texas at Austin Society Memberships and Committeep
'American Nuclear Society (Member) 1 Test Research and Training Reactor (Executive Committee)
- Stationary Neutron Radiography Source (Alt. Member ETA Review)
Engineer in Training. (Instructor, waves & nucleonics)
Research:
Dr. Bauer has contributed substantial effort to the planning and construction of The University of Texas Nuclear' Engineering Teaching Laboratory.
One interest is to develop outstanding
. programs in the application of nuclear technological methods and the research and development of new methods.
Among these general technologies are applications of a research reactor, detection and measurement of radiation, use of instrumental neutron activation alaalysis and neutron radiography and th3 application of digital control systems for research reactors.
- Selected Publications:
1.
N. M Abdurrahman, B. W. Wehring, T. L. Bauer, Y. G. Jo,
" Development of Nsutron Imaging. System for Real Time Neutron Radiography and Neutron Computed Tomography at The University of Texas Triga Reactor," Proc. of 5th Horld Conference on Neutron Radiography,. Berlin, 1996.
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 University of Texas at Austin,"
American Nuclear Society Proceedings 1996. Topical Meeting, Radiation Protection and Shielding, Vol.2:888- (1996).
J 9
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.Page 2 - Resume f
3.
H.R. Vega-Carrillo, A.J. Teachout, and T.L. Bauer, " Water-l extended Polyester Based Neutron Shielding Calculation,"
Sociedad Nuclear Mexicana, VI Congreso Internacional Anual, j
September 17-20, 1995.
4.
C. Rios-Martinez, K. On10, T.L. Bauer, and B.W. Wehring,
" Performance of Neon-Thermosyphon in the Texas Cold Neutron i
Source," Trans. Am. Nucl. Soc.21,- 138-139 (1994).
5.
T.L. Dauer and E.W. Wehring, " Expert _ System Connected to the University of Texas Research Reacter," Trans. Am. Nucl. Soc.
2Q, 138 (1994).
l 9
h l~
149. K. Ordo, C. Rice Martiner, and B. W. WeMng, " Prompt Osmma Activation Ande ts using a Focused Cold Neutron Beam," Irwhed prper,9th inlemadonal Syrgoalum on Capture Gamme Ray Spectroscopy and Reisled Toplos, Budapest Hungary,612 October,1998, in l
press as Conference Proceeding.
150. N. E. Hertel, H. R. VegaCarvito 8. W. Wehring. _A. J. Teachout, and P. A Jerabek, l
Heutron Fioed Charactertration la the Vicinty of a PET Cyclotron,' Proceedings of the 13th Mdyear Topical Meetin0 of the Heath Physios Society: Heath Physics of Radletion Generating Machines, January 5 0,1997, San Jose, CA, pp. 44189.
151. T, Z. Hossain, K. Onio, C. Rios-Martiner, B. W. Wehrin0, and J. K. Lowe5, Hydrogen Measurements in Semiconductor Thin Fhs usinD Prompt Gamma Activation Analysis, Fourth intomational Workshop on the Measurs.nont, Charactortsation an i Modeling of Unra-Shallow Doping Proftes in Semiconductors, Apr8 6-9,1997, Researct, Triangle Park, North Carouna, USA.
152. C. Rios-Martiner, K. Onl0, and B. W. WeMng, " Performance of the University of Texas Cold-Neutron Prorgt Gamme Adivation Analysis Faoluty,' Fourth intomational Conference i
on Methods and Appucations of Radoanatical Chemistry, Apri 6 11, 1997, Kallua-Kona, l
HewsN, USA (to be published J. Radioanal. Nucl. Chem.)
t
- 153. K. Onlo, B. W. WeMn0, T. Z. Hossain, and J. K. Lowou, ' Concentration and Depth Measurements of Poron in Semiconductor Malertels using Neutron Depth Profiling," The Electrochemical Society,191st Meeting, Diagnostics Techniques for Semiconductor Materials and Devices Symposium, May 4 9,1997, Montreal, Quebec, Canada.
154. K. Onl0, S. G0ktepeN, B. W. Wehring, A. R. K6ymen, F. M. Jacobsen, and A. H. Weiss,
" Design Fea'ures of the Texas irtense Postron Source," Trans. Am. Nucl. Soc. ZA 115 (1997).
155. S. GoldepeH, K. Onl0, T. L Bauer, and B. W. WeMng, ' Analysis of TRIGA Mark 1 Research Reactor Through Beam Port with MCNP,* Trans. Am. Nucl. Soc.lA 113 (1997).
156. B. W. WeMng, C. Rich-Mar,!rv.ez, K. Onlo, "Testin0 of the Universky of Texas Prompt Gamme Activation Analysi Facuty,'Trans. Am. Nud. Soc.ZA.118 (1997).
157. M. A. Elsawl, N. M. Abdurrahman, B. W. Wehring, and A. L Howerl, "Use of Graphite for Sbwin0 Down-Time Spectrometry," Trans. Am. Nucl. Soc.ZA,139 (1997).
158. A 1. Howart, N. M. Abdurrahman, and B. W. WeMng. T,ompact New Technology Neutron Generators for Nondestructive Assay of Nuclear Malertals Using Slowing-Downtime Spectrometry," Trans. Am. Nucl. Soc. 28,143 (1997).
159. F. M. Jacobsen, A. Koymen, A. H. Weiss, S. Ovonc, E. Srinivasan, S. Goklopol, K. Onio, B.
W. WeMng,'An intense Postron Beam Using a '.arge Area 6tu Source," (in press) Nel.
Instr and Meth,in Phys. Res. (1977).
160. K. Onlo, B. W - Wehring, T, Z. Hossain, J. K. Lowel, T,oncentsation and Depth Measurements of Boron in Semiconductor Malertals using Neutron Depth Profilin 0,* (in press), Diagnostics Techniques for Semiconductor Materials and Devices, SPIE, (1997).
Vta/96 97 15 P
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i Anna M. Johnson Teachout i
Education M.S.
Radiological Health Physics, San Jose State University, San Jose, Califomia, 1994.
B.S.
Physics, Norfolk State University, Norfolk, Virginia,1990. Gcaduated summa cum laude.
Employment History 1993-1997 Reactor Health Physicist. Nuclear Engineering Teaching Laboratory, the University of Texas at Austin.
1992-1993 Visiting Scientist. Varian Associates, Inc. Oncology Manufacturing Division, and the Stanford Linear Accelerator Center (SLAC), Palo Alto, Califomia.
Research work on neutron spectroscopy emp!oying three separate methods to quantify the neutron spectra, average energy, and r eutron dose equivalent for all Varian medical accelerators.' The methods employed were the Bubble Detector Spectrometer (BDS), the multisphere spectrometer with LIF TLDs, and flux integrators and an Anderson-Braun remmeter with activation foils. The data obtained from these separate methods was analyzed by means of spectral stripping, the use of unfolding algorithms (BUNKl/SPU",T), and the methods of AAPM 19 and NCRP 79.
1989-1990 Research Associate. The Continuous Electron Beam Accelerator Facility (CEBAF, now Thomas Jefferson National Laboratory), Newport News, Virginia.
Radiation shielding calculations for the focal place detector (FPD) crea in experimental hall A. Computer modeling of the parameters of the shielding problem, i.e., the spectra of particles reaching the FPD area and shielding materials characteristics, by means of FLUKA, GEANT, and EGS computer codes. My work assessed the weight, volume, and cost of the larger part of the shielding requirements of the FPD region of either spectrometer arm in hall A.
1987 1988 Military Aviation Consultant. Anders Williams Technologies, Inc., Norfolk, Virginia. Advised on both academic and field training aspects of military aviation training as well as which particular aspects of flight training could be improved or reinforced through tha use of Interactive Video D! splay (IVD) technology.
1982 1987 Rotary Wing Aviator / Officer. United States Army. Managed a staff of eight.
Responsible for all personnel matters (manpower forecasting, financial records, promotions, transfers, employee ratings, general and military correspondence) for an aviation brigade of 900+ personnel. Prepared and presented oral and written briefings on operational status for senior management. Additional duties included provision of weapons, and computer, nuclear, biological, and chemical safety and security. I also flew 800+ accident / incident free flight hours during
' this time period.
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1980 -1982 Deputy Administrator. Community Developmerit Block Grant Program, City of Lumberton, Mississippi. Prepared application for and implementation of a $2.9 milhon dollar HUD Small Cities Community Development Block Grant to rehabilitate a target area in a municipality of 4,000 people. Activities included rehab of four structures, construction of 18 new residential dwellings,2.3 miles of road improvements, construction of a neighborhood park, and extension of city water and sewer services to the target area.
Professional Memberships Health Physict Society South Texas Chapter Hoalth Physics Society American Physical Society Forum on Physics and Society New York Academy of Sciences Bt.h Kappa Chi Honor Society Alpha Kappa Mu Honor Society Professional Activities President-elect of the South Texas Chapter Health Physics Society.
Sci 6nce Teachers' Workshops Coordinator and Fundraising Committee Chair for the South Texas Chapter Health Physics Society.
Selected by the Americal Physical Society to participate in their Industrial Summer intern Program,1991.
Elected "Most Outstanding Physics Major,1990" by the faculty of Norfolk State University.
Featured in the National Dean's List, 1988-1990.
Federal Aviation Administration (FAA) certificated commercial pilot,1975.
Security Clearance - Secret (issued by U.S. Army Central Clearance Authority)
Publications Neutron Field Cha'acterization in the Vicinity of A PET Cyclotron, N.E. Hertel, H.R. Vega-Carrillo, A.J. Teachout, P. Jerabek, B.W. Wehring, Proceedings of the 13"' Midyear Topical Meeting of the Health Physics Society: Health Physics of Radiation Generating Machines, January 5-8,1997, San Jose, CA, pp. 461-69.
A Case Study in Control of Access to Radiation Beams: Neutron Depth Profiling at the Nuclear Engineering Teaching Laboratory, The University of Texas at Austin, A.J. Teachout, T.L. Bauer, K. Unl0, B.W. Wehring, Proceedings of the American Nuclear Society 1996 Topical Meeting, Volume 2 No. Falmouth, MA, pp. 888-93.
Paired Thermoluminescent Dosimeter Technique in Bonner Sphere Spectrometry, H.R. Vega-Carrillo, N.E. Hertel, A.J. Teach:ut, B.W. Wehring, Transactions Am. Nucl. Soc. D,356 (1995).
A Comparison of Neutron Detection Systems with Radioisotopic Neutron Sources in Preparation for Characterization of the Neutron Spectra of Varian Model 2103 and 2300 i
l
Clinacs@, A.J. Teachout, M.M. Elsalim, J.H. Kleck, P.A.J. Englert, J.C. Liu, V. Vylet Characterization of the Neutron Environment Around Varian Clinacs@ Model 2100C and 2300C/D Medical Linear Accelerators, M.M. Elsalim, A.J. Teachout, P.A.J. Englert, J.H. Kleck, J.C. Liu, V. Vylet Gadolinium Neutron Capture Therapy Dosimetry Measurements, X.P. Cheng, K. Onl0, A.J.
Teachout, N.M. Abdurrahman, B.W. Wehring, Transactions Am. Nucl. N. Z3,30 (1995).
y Water-Extended Polyester Based Neutron Shielding Calculations, H.6 / g.a-Carrillo, A.J.
Teachout, T.L. Bauer A Comparative Study of the UTA4 and the MYS4 Bonner Sphere Response Matrices, H.R.
Vega-Carrillo, A.J. Teachout, B.W. Wehring New Neutron Sources for Calibration Purposes, H.R. Vega-Carrillo, A.J. Teachout, B.W.
Wehring, Sociedad Nuclear Mexicana, VI. Congreso Anual Memorias, VolI,33 (1995).
d-Appendix A - 9 SNM-180 License Application October 1997 1
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e Appendix A - 10,11 SNM-180 License Application October 1997 A10 - Estimare of Fission Product Activity Al1 - Disposal Requirements
4 Fission Product Buildup in Suberitical Assembly Experimental measurements with a neutron source of 0
1.6 x 10 n/sec generate a neutron density approximately but conservatively represented by n(x) = a(sin bx)/x in both axial and radial dimensions.
The constants are
~3 2
~1 determined to be a = 50 x 10 n/cm, and b =.18 cm The total fission rate in the assembly is then determined f
by
[f n(r) V dr where V is the thermal neutron velocity 5
2.2 x 10 cm/sec.
The total fissions /sec are calculated 4
to be 9.65 x 10.
With an energy release of 185 MeV/ fission 4
the power of the assembiv will be (9.65 x 10 fission /sec) x
~13
-6 (185 MeV/ fission) x (1.60 x 10 watts /Mev) equals 2.86 x 10 6
watts.
A source strength of 8.82 x 10 n/see would generate
-6 15.8 x:10 watts.
The smaller source represents about 90 watts-sec of power / year of continuous operation.
A more realistic estimate is 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> / year or about 5.71 watts-secs with the larger source.
From 1960 till 1985 100 hr/yr oparation with the larger neutron source results in (25 yr) x 4
(3.15 x 10 sec/yr) x (1.15 x 10-5) x (9.65 x 10 fissions /sec) x 6
6 12 (8. 8 2 x - 10 n/sec) / (1.6 x 10 n/sec) is 4.80 x 10 fissions.
Assuming that af ter 100 days the fission products beta decay
-8 12 at a rate of 10 decays per ' fission then (4.8 x 10 fissions) x (10'O decays / fission) x (3.7 x 10 decays /p-curie) is less 4
than 1.5 u curies of activity.
A-10 A 10 i
SNM License (SNM 180 Decommissioning Requirements Materials on the license are PuSe neutron sources and a subcritical Three of the license materials are assembly of 20% uranium 235 enrichment.
plutonium beryllium sealed sources that are exempt from the regulation requirements.
The disposal requirements for these sources will most likely require a return to the Department of Energy to allow recovery of the materials prior to ultimate disposal.
Only the uranium 235 and any byproduct material of the suberitical The followin6 assembly's operation require consideration for decommissioning.
calculation indicates that the material requires a fund of $750,000!
These decommissioning requirements of 10CFR part 70 represent unacceptable conditions for this SNM 180 license materials.
10' factor 10CFR 70.25(a) decision limit 10CFR 20 appendix C uranium 235
.01 pcurie 10' x.01x10*'
.001 curie 10** curie / gram 40CFR 173.434 item 20 10CFR 70 license material 470 grams 470 grams x 10** curie / gram..0047 curie
.0047 curie
.001 curie - 4.7 times decision level The physical form of the subcritical assembly material is uranium dioxide License conditions set by uniformly dispersed in a matrix of polyethylene.
the assembly be ex6 mined for " leakage" of alpha activity by NMSS require that Yet the as;embly does not the same criterion as a sealed PuBe neutron source.
The result of meet any other criteria for consideration as a sealed source.
this type of testing would also set a limit on the amount of potential byproduct material contamination.
Any beta contamination that occurs during use of the assembly materials would be either taken care of subsequent to each use of the assembly or discovery by radiation program surveys.
The only contamination will be the assembly, possibly materials that are in contact with the assembly, and experiment materials that are part of the assembly The quantity of b product material is not considered a factor in f
applications.
the decommissioning since the cost of disposal will be set by the volume, waste classification and total curies.
The issue of byproduct material within the assembly has no effect on the Direct disposal of this assembly would be the minimum charge for conclusion.
one barrel (55 gallon) with no surcharge for activity, and ignores the recovery is unknown.
value of the 470 grams of uranium 235 isotope for which the market However, requirements for the recovery of uranica 235 as for plutonium 239 in scaled sources may also prevent direct disposal.
Total decommissioning costs for use of the suberitical assembly depend on the radioactive waste site disposal charges and transportation charges to the September 14, 1990 A 11
Page 2 disposal site.. An additional cost will be the radiation survey for' alpha, or beta contamination in'the immediate area of the materials'use, an area of g
84 e.
The cost of disposal,- transporg, and survey is then arbitrarily set at
$10,000., The cost is figured at $20/m area cleanup, disposal cost of 6200 $/a of waste, and a 201 allowance for transportation costs.
The estimated amount of a fund for decommissioning the SNM-180 license activities represents 0.0021 of the annual operating budget of The University of Texas at Austin, i
total cleanup 84m'
$20/a*
$1680 Dt.posal charge
$6200/a,
$1280 (1996 $'s, 1 55 gal, barrel)
Transportation
$ 256 (20I of disposal)
Contingency (escalation)
$6784
$10000 License SNM 180 Materials Decommissioning Requirements material grama isotone 1 grama comment 1 curie PuBe source plutonium 16 239 15 sealed (exempt) 2 curie PuBe source plutonium 32 239 30.
sealed (exempt) 5 curie PuSe source plutonium 80 239 74 sealed (exempt)
Subericical assembly uranium 23)5 235 20 470 unsealed September 14, 1990 A 11
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Appendix A 12 - 16 e
- SNM-180
- License' Application October 1997 v
Al2 '- Emergency Response Procedure -
. A 13' - SAR, i - xii
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Number
. Title Rev. 1-PLAN-E Emergency Response Date 6/90 NUCLEAR ENGINEERING TEACHING 1ABORATORY PROCEDURE PLAN E - REV 1 D(ERGENCY RESPONSE Approvals:
M 4 te9. ag t Hea:lth Physidist' Date SL 1, %
+hc./1I Reactor Supervisor Date M W. N &
7-9-91 Director, NETL V
Date f
-l-W f ' ; h*z? [ G'.& -
/]- V - V f Chairpers.on,. Re' actor Committee Date j
1$'
1ll$') A l Chafrperpn, Datd Radiation Safety Committee l'
List of Pages:
123456 l
I At tac!unents :
A Emergency Classifications B
Equipment and Supplies C
Drill Exercise i
BALCONES RESEARCH CENTER THE UNIVERSITY OF TEXAS AT AUSTIN OllG) N A Pas 1-6 R 1 0tro M & l.
1& f f-
Number Title Rev. 1 PLAN E Emergency Response Date 6/90 Step Action and Response Comment or Correction I.
PURPOSE To provide for classification of emer6ency conditions and describe the general actions to be taken for each Emergency Classification Category.
11.
DISCUSSION This procedure provides the general Buidelines for classification and actions to be taken in the event of an emergency condition.
The guidance provided in this procedure is very general as each emergency is an unpredictable and 3.sque event.
The specific actions taken are left to the personnel in charge based on their assessment of the event and the c i rcums ta nc e s.
III. REFERENCES A.
UT TRICA Mark II Emergency Plar.
B.
NCRP Report #65 IV.
CONTENTS lita fAEt Classification 2
Non-reactor specific event 3
Notification of Unusual event 4
Evacuation Procedure 5
V.
PROCEDURE A.
Classification 1.
Use the information in Attachment A, Emergency Classification to classify the event as a a.
Non Reactor Specific Event b.
Notification of Unusual Event 2.
Place the call for assistance, and start the notification process (see procedure PLAN 0).
-3.
Follow the procedures of section B or C.
If evacuation is necessary follow the procedures of section D.
ORIGl\\'AL rare _2_ of _6_
1
!4f Number-Title-Rcy, l' h
PLAN-E--
. Emergency Response Date 6/90 r
Step
. Action and Response-
. Comment or Correction B. : Acticns for' Non Reactor Specific 'Fvent:
1
- Evacuation of the building _would not normally 'oe a requirement'of-this classification of-event.
-1, The reactor shall be immediately shutdown.if the event o*
emergency has the_ potential to worsen such that the reactor, pool, room, experiments or instrumentation and control system are threatened.
2.
Render immediate assistance to any victim.
~
3.
Secure radioactive materials-as necessary.
4.
Notify all persons in the immediate areas.
5.
Identify the responsible person to be designated' emergency director.
6, r.equest assistance fros' appropriate emergency response organizations.
(Refer to Emergency Call List),
7.
Verify notification of University Safety Office.
Notify-NETL Director.
8.
Initiate actions that mitigate the emergency situation.
9, Take actions ~necessary to t'erminate emergency condition.
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O Number Title Rev. 1 PLAN E-Emergency Response Date 6/90 Step.
Action and Response Comment or Correction C.
Actions for Noti.fication of Unusual Event:
Evacuation of the building or an area is generally a requirement of this classification of event.
1.
Terminate reactor operation by shutdown or scram switch as appropriate to the conditionr.
2.
Notify and evacuate all persons in the immediate vicinity.
3.
Specify the responsible emergency director by verbal acknowledgement.
a.
Assistant Director b.
Supervisory Reactor Operator c.
Director or management 4
Notify appropriate emergency response organizations.
(Refer to Emergency Call List).
5.
Secure appropriate emergency equipment.
Locate appropriate emergency supplies.
(Refer to Emergency Equipment and Supplies List).
6.
Initiate actions to e.1 gate the emergency.
7.
loentify need for emergency support.
8.
Notify university safety - ' security personnel.
9.
Provide security r.nd access control.
10.
Assess radiation levels and releases.
11.
Implement controls to limit personnel exposures appropriately. Establish controls of radioactive material contamination.
12.
Evacuate personnel on adjacent site areas if necessary.
Notify NRC, Reb on IV. Notify TDH Bureau of Radiation 13.
i Control authority.
(Refer to Emergency Call List).
14 Maintain personnel eccess, physical security, and radiological monitoring until event is terminated.
15.
Take actions necessary to terminate emergency condition.
16.
Review facility status and develop recovery procedures.
OR!G!NAL 6
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I
_____---__--_-_____.___________m
Number Title Rev. 1 P LAN. E Emergency Response Date 6/90 Step Action and Response Comment or Correction D.
Area Evacuation 1.
Proceed to the emergency assembly area. An alternate area may be designated if the assembly area is not considered
$1fe, a) Assembly area is the health physics room (2.106).
For localized emergencies that do not threaten building systems or multiple building areas.
b) An alternate area is the equipment access driveway, several meters from the building or if this area is downwind the emergency director shall locate another site upwind of the building and verbally notify all evacuees.
c) Account for all persons in the facility. A person should monitor the whereabouts of facility personnel at both the main and service exits to the building.
d) Determine the person specified as emergency director. Assign a person to provide public information.
e) NETL Emergency Director should wear a hard hst and or fluorescent vest with NETL Emergency director designation.
f) NETL Emergency Director should communicate with HP or staff personnel by relay via response personnel communication equipment or a runner.
2.
Control spread of radioactive contamination by a)
Immediate measurement of activity on hands and
- feet, b) Removal of contaminated clothing and wash of skin surfaces.
c)
Identification of potential problem areas.
d) Control of access to hazard areas.
3.
Remove readily accessible portable radiation survey instruments to be available for emergency activities.
Issue pocket dosimeters to emergency personnel entering potential radiation areas.
4.
Persons transported from the area for medical treatment shall be free of contamination or escorted by a knowledgeable person with radioactivity measurement equipment.
5.
Avoid areas with potential safety hazards.
OR!GINAL P se s of _6_
~_
-. ~..
... ~ - -. -..
Number Title Rev. 1-PLAN-E
_ Emergency Response-Date 6/90
'N Step Action and Response Comment or Correction E.
Er.ergency Plan Preparedness 1.
Emergency locker radiacs Emergency locker radiacs should be response checked monthly a.
.but shall not exceed three months.
- b.
Emergency locker radiacs shall,.be calibrated every six months but shall not exceed 1 year.
2.
Eme rgency - Locke r Inventory a.
The Emergency Locker shall be inventoried every six months but shall not exceed 1 year.
b.
Supplies removed from the inventory should be replaced promptly.
3.
Emergency Plan Training / Drills Emergency plan training shall be held annually for NETL a.
-permanent staff, that includes a drill.
On site drills should coordinate through UTPD and che Safety
- Office, b.
A full-scope drill shall be conducted biennially to include the response of offsite emergency groups.
Off site drills should be coordinated through UTPD and the Safety Office for the scheduling of all activities of Austin City Fire Department and Emergency Medical Services. This
~
includes involvement of the City of Austin Office of Emergency Management.
4 Letters of agreement with the City of Austin AFD, EMS and Brackenridge Hospital shall be updated each two years.
Unit Title Home Phone #
City of Austin Director Office of Emergency S. Collier 370-2608 Management City of Austin Chief AFD B. Roberts 477-5784
' City of Austin Training Coordinator EMS D. Cruel-469-2050 UT Director Safety Office D. Decker 471-3511 UT Chief UT Police Dept.
D. Cannon 471 4441
' NETL Director.
B. Wehring 471-5787 NETL Emergency Director T. Bauer 471-5787 NETL Health Physicist R. Woodard-471-5787 OR!GINAL 6
r =- 6 * --
j
+
Rev. 1 l
Number
' Title PLAN E Emergency _ Response.--
Date'6/90-
'[
Emergency Classification classify Emergency conditions'as follows:
Condition-Qualification 1
I, Non-Reactor Soecific Emernency Individual; inj ury Assistance necessary Natural disaster.
Nearby *,' threatening or impending Fire in operations boundary Lasting 15 minutes or less Hazardous localized condition Personnel contamination
.or material spill II.
Notification of Unysual Event Severe natural phenomenon Damage to building reactor systems or facility utilities Sustained. fire in facility Threat to reactor systems or radioactive materials Civ11' disturbance or bomb threat Threat of physical damage Threat or breach of Discovery of forced entry physical security or SNM the'-
Reactor coolant leakage Out of cperati irus boundary Reactor coolant loss Exceeds makeup capability Single fuel element failure Relea'se of radionuclides into' operations area Multiple. fuel element failure Release of' radionuclides into operations area Measured dose rate
> 20 mr/hr at operations boundary from unknown source Measured or projected whole
> 15 millirem in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at site
-body dose boundary Measured particulate activity
> 10MPC within operation boundary on fixed filter air sample Measured 'or projected effluents.
> 10MPC (24 hr avg) unrestricted areas at site boundary i
O TGINAl_
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Number-Title Rev. 1 PLAN E Emergency-Response Date 6/90 Emergency Eautoment t
Emergency _ Lights:-
portable flashlight in control _ room ac and'de= emergency lighting in hallways, stairwells, and reactor bay Efra Extinguishers:
Sprinklers in lab and office areas dry-stand pipe in stairwells 72f halon_ system in control room 15f halon portable.
10# CO2 Portable (8) 6f dry chemical _ portable (8)
Radiation Monitors:
Eberline RO 2A lon Chamber 0 50 R/hr (PORTABLE)
Bicron Micro Rem Scintillator 0 2000 sSv/hr Bicron Frisk Tech 0-500,000 cpm Scintillator Probe (a B)
PRS 2/NRD BF ' Counter 0 5 R/hr 3
Victoreen 440 Ion Chamber 0 300 mree/br Radiation Monitora:
Eberline 6 channel CM 0,1 10,000 mr/hr (FIXEO)'_
CA Model Ar 1000 C seous Air 9
Monitor 0 10 cpm Emergency Supolies Reference Materials:
Control Materials:
Emergency Procedures 5 Radiation Area Emergency Notification List 5 High Radiation Area University Radiation dafety Manual 5 Radioactive Material Triga Safety Analysia Report 5 Airborne Radioactivity Area
!!ealth Physics Handbook i roll Radioactive Material tape 10CFR20/NCRP65
- 20 ft magenta and yellow rope Eirst Aid Kil:
Protective Clothine:
gause, bandalds 8 pair coveralls iodine, antiseptic 8 pair gloves eyewash, absorbent cotton 8 pair shoe covers adhesive tape, scissors, swabs, 8 filter respirators,(k mask) tongue depressor, eyedropper, 1 full mask respirator, filters ammonia inhalants Cleanun Materials:
Radiation Detection:
10 large plastic bags 2-7 sensitive radiation detec -
1 roll lab mat absorbent paper tors with_ batteries 1 pkg ordinary paper towels i
4 7 sensitive pocket dosimeters 1 bottle decontamination soap l pocket dosimeter charging /
reading unit with battery OR!GiNAL 1
r se 1 or --
.... - ~
e Number-Title Rev. 1 PLAN E.
Emergency Response
'Date 6/90 Drill Exercise Emergency: Event Type:
Exercise Date:,_/__/__
-Release of radioactive gas High radiation area or airborne particulate.
Civil disturbance or Fire or chemical reaction Radioactive material spill and contamination
.ecurity. breach Fuel element failure Natural disaster-Loss of pool coolant.
Persornel injury-Event Scenario:
Area effected by the event Specify the source of the released material
-Specify the-magnitude of radioactive release involved Brief description of event:
Response Evaluation:
Condition properly identified?
yes no Assessment actions taken:
Responsibility identified?
yes no Director Corrective actions taken:
Notify support organizations:
yes no-organization Protective actions-taken:
' Termination of event specified?
yes no Performance Comments:
ORIGINAL t
r==-
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TRIGA Reactor Facility Nuclear Engineering Teaching Laboratory The University of Texas at Austin SAFETY ANALYSIS REPORT Submitted May 1991 Revision 1.01 Revision Dates Chapter 1 5/91 Chapter 7 5/91 Chapter 2
-5/91 Chapter b 5/91 Chapter 3 5/91 Chapter 9 5/91 Chapter 4 5/91 Chapter 10 5/91 Chapter 5 5/91 Chapter 11 5/91 Chapter 6 5/91
-Page Replacements - October 1991 2 25, 7-5, 22, 23, 27, 28, 4-69, 8-1, 7, 10, 11, 16, 18, 22, 5-12, 14, 9-11, 9-15 6-13, 15, 10-2, 6, 9, 10, 31
SAR 5/91 Table of Contents-Safety Analysis Report The University of Texas TRIGA
_Seetion Ep_gg 1.
Introduction and Summary..................................... 1 1 1.1 Principal Design Criteria 11 1.2 Design Highli hts 11 b
1.3 Conclusions 13 References 15 2.
Site Description...................................
...... 2-1 2.1 General Location and Area 2-1 2.2 Population and Employment 2-6 2.3 Climatology 2 10 2.4 Geology 2-13 2.5 Seismology 2-19 2.6 Hydrology 2-19 2.7 Historical 2-23 References 2-28 3.
Facility Design - Structures, Systems and Components......... 3 1 3.1 General Conditions 3-1 3.2 Architectural and Structural Engineering 3-4 3.3 Space Allocat' ion 37 3.4 Reactor Bay and Operation Control 3-7 3.5 Support Facilities 3-13 3.5.1 Health Physics Laboratory 3 13 3.5.2 Sample Handlint.aboratory 3 13 3.5.3 Effluent Control 3-13 3.6 Design Evaluation 3-15 References 3-16 4.
TRIGA Reactor......................................
... 4-1 4.1 Design Bases 4-1 4.1.1 Reactor Fuel Temperature 41 4.1.1.1 Fuel and Clad Temperature 4-7 4.1.1.2 Finite Diffusion Rate 4-21 4.1.1.3 Summary 4-25 1
l SAR 5/91 c
Section g
4.1.2 Prompt Negative Temperature Coefficient 4 26 4.1.2.1 Codes Used for Calculations 4 28 4.1.2.2 ZrH Model 4 28 4.1.2.3 Calculations 4 31 4.1.3 Steady State Reactor Power 4-32 4.1.3.1 Entrance Loss 4 34 4.1.3.2 Exit Loss 4-36
'9 4.1.3.3 Loss Through Portion of Channel Adjacent to f
Lower Reflector 4 36 4.1.3.4 Loss Through Portion of Channel Adjacent to Upper Reflector 4 36 4.1.3.5 Loss Through Each Increment of the Channel Adjacent to the Fueled Portion 4 37 of the Elements 4.1.3.6 Acceleration Term 4-37 4.1.3.7 Friction Term 4 40 4.1.3.8 Gravity Term 4-41 4.1.3.9 Nomenclature 4-45 4.2 Nuclear Design and Evaluation 4 47 4.2.1 Reactivity Effects 4-47 4.2.2 Evaluation of Nuclear Design 4-51 4.3 Thermal and Hydraulic Design 4 52 4.3.1 Design Bases 4-52 4.3.2 Thermal and Hydraulic Design Evaluation 4-54 4.4 Mechanical Design and Evaluation 4-54 4.4.1 General Description 4-54 4.4.2 Reflector Assembly 4 57 4.4.3 Crid Plates 4 57 4.4.4 Safety Plate 4 59 4.4.5 Fuel-Moderator Elements 4 59 4.4.5.1 Instrument Fuel Elements 4 61 4.4.5.2 Evaluation of fuel Element Design 4-62 4.4.6 Neutron Source and Holder 4 64 4.4.7 Craphite Dummy Elements 4 64 4.4.8 Control System Design 4-64 4.4.8.1 Control Road Drive Assemblies 4 67 4.4.8.2 Regulating Rod and Stepping Motor Drive 4 67 4.4.8.3 Transient Road Drive Assembly 4 69 4.4.8.4 Evaluation of Control Rod System 4-72 4.5 Safety Settings in Relation to Safety Limits 4-73 References 4-74 5.
Reactor Coolant System....................
.... 5-1 5.1 Design Bases 5-1 5.1.1 Reactor Core Heat Removal 5-1 5.1.2 Reactor Pool Heat Removal 5-2 5.1.3 Heat Exchanger Design Bases 5-2 5.1.4 Water Purification Bases 5-6 11
=_.- - _
SAR 5/91'
]
Section -
h
}
5.2-System Design-5 6-5.2.1 Coolant System 56 5.2.2 Purification System 5-10; 5 2.3 Water System'1nstrumentation 5.
'5.3 Water System Design Evaluation 5 12
-References 5 15 6.
Ins trumentation and Control Sys tem........................... 6-1 6.1 Design Bases 6 1:
6.1'1 NM 1000 Neutron Channel 65 6.1.2 NP 1000 Power Safety Channel 6 6=
6.1.3 Reactor Control Console 6-6 6.1.4 Reactor Operating Modes 68 6.1.5 Reactor Scram and Shutdown System 6-13 6.1.6 Logic Functions 6-14 6,1.7 Mechanical Hardware 6 16' 6.2 Design Evaluation 6 17 References 6-18 7.
Design Features and Auxiliary Systems........................ 7-1 7.1 Design Bases 7-1 7.2 Design Features 7 1-7.2.1 Reactor Pool and Shield Structure 7-2 7.2.2 Reactor Bay Ventilation Design 72 7.2.3 Fuel Materials 7-10 7.2.4 Safety Feature Evaluation 7-10 7.3 Auxiliary Systems 7-11 7.'3.1 Life Safety and Fire Protection 7 11 7.3.2 Passive Fire Protection Elements 7-11
'7.3." Active Fire Protection Elements 7-12 7.3.4 HVAC System 7-13 7.3.5 Communicati and Security 7-13 7.3.6 Compressed Air and Deionized Water 7-14 7.3.7 Utilities 7 14 7.3.8 Hazard Liquid Waste 7-14 7.4 Confinement Design Evaluation 7-15 7.4.1 Release of Nitrogen-16 and Argon 41 7-15
-7.4.1.1 Nitrogen 16 Activity in Reactor Room 7 15 7.4.1.2 Release of Argon 41 from Reactor Pool Water
- 7 19 4.1.3 Activation of. Air in the Experimental Facilities 7-25 7.4.2 Evaluation of Argon 41 Release.
7-27 References 7-29 111 s
1
SAR 5/91 e
Section Eggg 8.
Experiment and Irradiation Facilities.........
.8 1 8.1 Standard Experiment Facilities 8-1 8.1.1 Central Thimble 8-1 8.1.2 Rotary Specimen Rack 81 8.1.3 Pneumatic Specimen Tube 8-1 8.1.4 Beam Tube Facilities 84 8.1.4.1 Tangential Beam Ports 8-4 8.1.4.2 Radial Beam Ports 84 t
8.1.4.3 Beam Tube Plugs 8-4 8.1.5 Evaluation of Materials in Experiment Facilities 8-7 8.1.5.1 Double Encapsulation 87 8.1.5.2 Explosive Materials 88 8.1.5.3 Fueled Experiments 8-10 8.1.5.4 Airborne Experiment Releases 8 11 8.2 Special Experimental Facilities 8-12 g
8.2.1 Reactor Core Facilities 8 12 8.2.1.1 Three Element Feature 8-12 8.2.1.2 Six Element Feature 8-12 8.2.2 Camma Irradiation Facility 8-13 8.2.2.1 Hazard to the Pool Water System 8-13 8.2.2.2 Hazard to Laboratory Personnel 8-17 8 2.2.3 Point Source Shielding Calculations 8-17 8.3 Othe. Experiment Facilities 8-20 8.3.1 Suberitical Reactor and Moderators 8 20 8.3.2 14 MeV 1;eutron Generator 8-20 References 8-22 9,
Radioactive Materials and Radiation Measurement..
.... 9 1 9.1 Radioactive Materials Control 9-1 9,1,1 Reactor Fuel 91 9.1.2 Reactor Components 91 9.1.3 Experiment Facilities 9-4 9.1.4 Activated Samples 9-4 9.1.5 Radioactive Waste 9-4 9.1.6 Other Materials 9-4 9.2 Radiation Monitoring 95 9.2.1 Minimum Procedures 95 9.2.2 Monitoring Techniques 9-6 9.2.3 Management Surveillance 9-6 9.2.4 Frequency and Accuracy 9-6 9.3 Instrumentation 9-7 9.3.1 Fixed Area Monitors 9-7 9.3.". Airborne Radioactivity Monitors 9-7 9.~ 3 Survey and Laboratory Instrumentation 9-8 9.3.6 Liquid Effluent Sampling 98 9.3.5 Range and Spectral Response 9-9 9.3.6 Calibrations 9-9 iv
.,y 4
.s
-SAR 5/91 T
Se'e tion.
Ea&A-9.4 Records-9-9~
t
_ 9.5 Evaluation of Monitoring _ System-
-9 10 9 5.1 Particulate Air Monitor 9 10 a
9.5.2 Argon 41 Monitor _
9-15 9.5.3 Area Radiation Monitors 9 18 9.5.4 Monitor Availability _ Conditions-9 19 Re fe rence s -
-9 21 10.
Conduc t o f ope ra t i ons...................................... 10 1 10.1 Facility Administration 10 1 10.1.1 Organization 10 1 10.1.1.1 Structure.
10 1
.10.1.1.2 Executive Vice President and Provost 10 1 10.1.1.3 Vice: President for Business Affairs 10 1 10.1.1.4 Director of Nuclear Engineering Teaching Laboratory 10 1 10.1.1.5 N.: clear Reactor Committee 10 3 10.1.1.6 Radiation Safety Officer 10 3 10.1.1.7 Radiation Safety Committee 10 3 10.1.1.8 Reactor Supervisor 10 3-10.1.1.9 Health ~ Physicist 10 4 10.1.1.10 Professional-and Classified Staff 10 4 10.1.2 Qualifications 10 4 10.1.2.1 Job Descriptions 10 4 10.1.2.2 Facility Director-10 5 10.1.2.3 Reactor Supervisor 10 5 10.1.2.4 Health Physicist 10 5 10.1.1.5 Professional and Classified Staff 10 5 10.1.3 Reactor Operations 10 5 10.1.3.1 Staffing 10 6 10.1.3.2 Procedures 10 6 10.1.3.3 Experiments 10 7 10.1.4 Actions and Reports 10 10.1.4.1 Operating Reports 10 7 10.1.4.2 Safety Limit Violation l'
8 0
10.1.4.3 Release of Radioactivity 10-8 10.1.4.4 Other' Reportable Occurrences 10 9 10.1.4.5 other Reports 10 9 10.1.5 Records 10 -10.1.5.1 Lifetime Records-10-10 10.1.5.2 Five Year Period 10-10 10.1.5.3 Training cycle 10 10 10.2 Operator Requalification
.10 11 10.2.1 Introduction 10 10.2.2 Operator License Status 10 11 10.2.3'Requalification Program Bases 10 11 v
. = -.
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- .1 SAR 5/91
.v.
Seetion f.agt -
10.2.4 Requalification Program
'10-11 10.2.5 Schedule 10 12.
10.2.6 List-of subjects 10 12 10.2.7 On the Job Training 10 12 10.2.7.1 List of Annual Training Tasks 10-12 10.2.7.2 List of Training Tasks; system malfunctions 10-13 10.2.7.3 On the Job Training Checks 10-13 10.2.8 Evaluation 10 14 10.2.9 Records 10-14 10.3 Radiological Protection Program 10 15 10.3.1 Management and Policy 10-15 10.3.2 Responsibilities 10 15 10.3.3 Organizational Access 10-15 10.3.4 Equipment and Supplies 10-16 10.3.5 Training and Safety 10-16 10.4 Fire Protection Program 10-17 10.4.1 Facility Fire Protection Elements 10 17 10.4.2 Facility Fire Protection Control 10-18 10.4.3 Fire Safety Assurance 10-18 10.5 Security and Emergency Plans 10-18 10.6 Quality Assurance Program 10-19 j
10.6.1 Introduction 10-19 10.6.1.1 Purpose 10 21 10.6.1.2 Responsibility 10-21 10.6.1.3 organization 10 21 10.6.1.4 Documentation 10 23 10.6.2 Quality Assurance Controls 10-23 10.6.2.1 Design Controls 10-23 10.6.2.2 Procurement Controls 10-23 10.6.2.3 Document Control 10-25 10.6.2.4 Material Control 10-25 10.6.2.5 Process Control 10-25 10.6.3 Inspection and Corrective Actions 10-25 10.6.3.1 Inspection Program 10-25 10.6.3.2 Test Program 10-26 10.6.3.3 Measuring and Test Equipment 10-26 10.6.3.4 Non Conforming Material and Parts 10-26 10.6.3.5 Corrective Action 10 26
.1.6.3.6 Experimental Equipment 10-27 0
10.6.3.7 Replacements, Modifications, or Changes 10 27 10.6.4 Records and Audits 10-27 10.6.4.1 Quality Assurance Records 10-27 10.6.4.2 Audits 10-27 b'
vi y
~
o SAR-5/91-
- o.
d v
'Seerion gag,g 10.7 Startup Program
-10 29
.10.7.1 Storage of Fuel and Acquisition of Components-10-30 10.7.2 Tests of Systems Before Core Loading 10 30 10.7.3 Core Load for Initia1' Criticality '
10-30 10.7.4 Tests Subsequent to Core Criticality 10-30 10.7.5 Acceptance _for Operation _
10 31 References10-321 11.
Safety Analysis............................................ 11 1 11.1 Reactivity Accident 11 1 11.1.1 Summary 11-1 11.1.2 Analysis Lof 2.8% Insertion at 1 kW 11 2
- 11.1.3_ Analysis of 2.8t-Insertion at 880 kW 11 8
.11.2 Loss of Reactor Coolant 11 11 11.2.1 Stamary-11-11 11.2.2_ Fuel _ Temperature and clad Integrity 11 11.2.3 After-Heat Removal Following. Coolant Loss 11-18 11.2.4 Radiation Levels 11 22 11.3 Fission Product Release 11-26 11.3.1 Fission Product Inventory 11-26
--11.3.2 Fission Product Release Fractions 11-26 11.3.3 Downwind Dose Calculation' 11 28 11.3.4 Downwind Doses 11-30 l
l References 11-32 i-l i
l l-i
'vii
SAR 5/91 4
c.
List of Figures Figure Egag 21 State of Texas Counties 2-2 2-2 Travis County 23 2-3 City of Austin 24 2-4 Balcones Research Center 2-5 25 Travis County 1980 Census Tract Boundaries 2-8 26 City of Austin Census Tract Boundaries 29 2-7 Austin Climatology Data 2-11 28 Austin Wind Rose Data 2-12 29 Texas Tornado Frequencies 2-16 2-10 Texas Hurricane Paths 2 17 2-11 Local Funnel Cloud Sitings 2-18 2-12 Balcones Fault Zone-2 20 2-13 Texas Earthqu.ke Data 2-21 2 14 Local Water Aquifers 2 22 2 15a Research Center Area 1960 2-25 2-15b Balcones Research Center 1960 2-26 2-16 Balcones Research Center 1990 2-27 31 NETL Site Plan for Balcones Research Center 3-2 32 Elevation Plans 3-5 3-3 Building Section Plans 36 34 First Level Floor Plan 3-8 3-5 Second Level Floor Plan 3-9 3-6 Third Level Floor Plan 3-10 3-7 Fourth Level Floor Plan 3-11 38 Reactor Bay Area 3-14 4-1 Phase Diagram of the Zirconium-Hydrogen System 4-3 42 Equilibrium Hydrogen Pressure Versus Temperature for Zirconium Hydrogen 4-5 43 Strength of Type 304 Stainless Steel as a Function of Temperature 4-6 4-4 Strength and Applied Stress as a Funtion of Temperature, Equilibrium Hydrogen Dissociation Pressure 4-8 4-5 Radial Power Distribution in the U-ZrH Fuel Element 4-10 46 Axial Power Distribution in the U-ZrH Fuel Element
-4 11 47 Subcooled Boiling Heat Transfer for Water 4-12 48 Clad Temperature at Midpoint of Well Bonded Fuel Element 4-13 4-9 Fuel Body Temperatures at Midplane of Well-Bonded Fuel Element After a Pulse 4-14 4-10 Surface Heat Flux at Midplane of Uell Bonded Fuel Element After'a Pulse 4 15 4 11 Surface Heat Flux for Standard Non-Gapped (h p-500) Fuel Element After a Pulse 4-17 SuhfaceHeatFluxforStandardNon-Gapped 4-12 (hgap-375) Fuel Element Af ter a Pulse 4 18 4-13 Surface Heat Flux for Standard Non Gapped (hEsp-250) Fuel Element After a Pulse 4-19 vili
-=
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- SAR 5/91' e
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.4 14-Surface Heat Flux at Midpoint Versus Time for Standard Non Capped Fuel Element After a Pulse
- 4 20 4-15 Transport Cross Section for Hydrogen in ZrH and Average Neutron Spectra in Fuel Element 4-27 4 16 A Comparison of Neutron Spectra Between Experiments and Several Hydrogen Models 4 29 4-17..Effect of Temperature Variation on Zirconium Hydride Neutron Spectra 4 30 4 18 Prompt Negativt Temperature Coefficient Versus Average Fuel Temperature for TRICA 4 33
'4-19 Ceneral Fuel Element Configuration fer Single Coolant Channel in the TRIGA 4-35 4 20 Experimentally Determined Vapor Volumes for Subcooled Boiling in a Narrow Vertical Annulus 4-38 4 21 Cross Plot of Figure 4 20 Used in Calculations 4-39 4-22 Plot.for which DNB Ratio is 1.0 of Maximum Heat-Flux Versus coolant Temperature 4-44 4-23 Estimated Reactivity Loss Versus Power 4-49 4-24 Estimated Maximum B Ring and Average Core Temperature Versus Power 4-50 4 25 Reactor, Reflector, and Shielding 4-55 4 26 TRIGA MARK II Reactor 4-56
- 4-27 Core Arrangement 4-58 4 TRIGA Stainless Steel Clad Fuel Element with End Fittings 4 60 4 29 Instrumented Fuel Element 4-63 4 30 Fuel Followed Control Rod 4-66 4 31 Rack and Pinion Control Rod Drive 4-68 4-37 Adjustable Transient Rod 4-70 4-33 Transient Rod Operational Schematic 4-71 5-1 Coolant System Layout 5-7 52 Purification System Layout 58 53 Water System Instrumentation 5 11
'61 Control System Block Diagram 6-3 6-2 Neutron Channel Operating Ranges 6-4 63 Layout of the Reactor Control Console 6-7 6-4 Console Control Panels 6-9 6-5 Video Display Data 6 10.
6-6 Rod Control Panel 6-11 6-7 Logic Diagram for Control System 6-15 7-1 Reactor Shield Structure 7-3 7-2 Isodose Curves for Shield Structure 7-4 27 3 Reactor Bay Air Ventilation System 76 74 Reactor Bay Auxiliary Exhaust System 77 7-5 Schematic of Ventilation Systems 7-9 e
ix i
l
e SAR L/91 e-UL'att hit 81 Rotary Specimen Facility 82 82 Pneumatic Transfer Facility 83 83 8-am Tube Configuration 85 84 Camma Irradiator 8 14 8-5 Special Experiment C.quipment B 21 91 Radioactive Material Use and Storage, Areas 92 92 Radioactive Material Effluent Control Systems 93 93 Activity Accumulation on Particulate Filter 9 13 10 1 Administration 10 2 10 2 Quality Assurance Organization 10 22 l
11 1 Calculated Pulse Shape Energy, and Temperature 11 3 11 2 ruel Temperature Distribution Before and After Pulse 11 12 11 3 Tuel Temperature and Power Density for Element Cooling Times 11 13 11 4 U Zrit (1,6) Strength and Stress versus Temperature 11 14 11 5 Coo'aing Times After Reactor Shutdown to Limit Maximum Fuel Temperature Versus Power Density 11 16 x
SAR 5/91 f
e
.e List of Tables Table fa&t 11 Principal Design Parameters 12 i
21 Travis County 1980 Population Density Distribution 27 22 1982 Meteorological Data for Austin, Texas 2 14 2+3 Historical Meteorological Data for Au.stin, Texas 2 15 2e4 Cround Water !.ctivity ~
2 23 25 Tank Studge Samples
.2 24 l
-41
-Physical Properties of Delta Phasa U.ZrH 42
-l 42 Hydraulic Flow Parameters 4 32 I
43 Typical TRICA Core Nuc' car Parameters 4 47 l
4 4-
-Estimated Control Rod Net Worth 4 48 45 Estimated Fuel Element Reactiviry Vorth Compared with Water as a Function oL Position in Core 4 48 46 Expected Reactivity. Effects Associated with Experimental Facilitans 4 51 47 Comparison of Reactivity Insertion Effects 4 52 48 1000 kW(t) TRICA Heat Transfer and Hydraulic Parameters 4 53 49 Thermocouple Specifications 4 61 4 10 Summary of Fuel Element Specifications 4 62 t
4 11 Summary of Control Rod Design Parameters 4 65 4 12 TRICA Safety Settings 4 73 51 Reactor Coolant System Design Summary 59 52 Heat Exchanger: Heat Transfer and Hydraulic ?arameters 5 13 i
71 Saturated Argon Concentration in Water 7 20 72 Volumes and Thermal Fluxes of Facilities 7 26 81 Material Strengths 88 82 container Diameter to Thickness Ratio 89 83 Calculated isotope Release Values 8 10 84 Microshield Data 8 16 91 Significant Fission Products:
Contribution to Total Activity, Percent 9 12 92 Beta Emitting, Caseous Radionuclider of Interest 9 16 i
10 1-Q. List for 1MW UT TRICA 10 20 10 2-Responsibilities and Key Personnel 10 22 10 3' Format for Safety. Related QA Checks 10 24
.10 4. Quality Assurance Program Audit Procedures 10 28 i
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SAR 5/91 I
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11 1 ' Reactivity Transient input Parameters 11 4 r
11 2-Reactivity Transient input Parameters 11 9 11 3 Calculated Radiation Doie Rates for Loss of Shield Water
- 11 22 i
11 4 Noble Gas and Halogens in the Reactor 11 27
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11'.5 Assumed Breathing Ratert 11 30-l 11 6 Average Comma Ray Energy and Internal Dose Effectivity for Each Fission Product Isotope 11-30 11 7 Domes from Fission Product Releases 11-31 i
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Title:
Subcritical Assembly
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7/6/87 i
Perconnol TRIGA facility supervisor; Supervisory senior operator; or knowledccable faculty J
Cowponents:
Aerojet !!uclear A0li j
Subcritical Core Assembly Reflector, lioderator Couponents Suppleaonts:
Plutonium-Beryllium lleutron Sources 11nufacturer Documentation Experiment Requests Prercquisites: I:nowledge or experience with neutron suboritical multiplication, S!!!i-18011aterial License Instructions:
1.
Check for personal dosimeters.
Filu bad;c dosimeters shall be used by each person that will handle the suboritical assecbly or the plutoniuu-beryllium sources.
Pocket ionization chambers or TLD's should be used to suppleuent personnel conitoring for persons in the experiment area if a neutron source is in the suboritical assembly.
2.
Obtain portable radiation monitoring equipuent.
A thin window G!! tube should be available for measurement of Gamma radiation fields and detection of activation activities in experipent foils. A neutron detector should be available to conparo neutron count rates of the assembly for the conditions of noutron source multiplication and no neutron source multiplication.
3 Identify the person responsible for movement of the coro assembly or neutron sources.
Experiments with the core and neutron source combination shall be under the direct supervision of the TRIGA facility supervisor, a faculty-nember with the appropriate knowledge and experience, or a licensed reactor operator with specific traininc or instruction.
4 Post the experiment area or maintain visual observation of the i
nrca during an experiment.
EXP - 1
J. L's.rorary accenn sign and barrier or auditle alara are to crovlue the nocctsary warning of ra(ittion trea or hich raciation
.t n a, if cpplicaL>1e.
5.
Contral storaco, t. oves..cr.ts and riodifict.tions by explicit approval of tie Tit!CA facility supervisor or a cupervisory senior operator.
Cuberitical coro Lose:.bly shall includa the core, storage container, reficotor systens, fuc1 elenent disks and three plutoniuc.-berylliu.a cources.
6.
Mondio irradiated bare foils with tweezers to lossen al:1n enla ures. I',andle polyethelone tuv1 couponents with plastic
- 1tv s to cvoid skin contanination. Handle neutron cources with ton, to.iaintain diatence fron source.
Control irradiated foils an radiot.ctive raterial. Dispose of handling or cleenin; itecs an rtdio:iotive waste.
7.
Verify the calibration of portablo radiation nonitors prior to ht;ndlin; the core assetbly or neutron sourcec.
Ctandard procedures for portable conitor calibration shall be thcac of the TTt10A reactor facility or equivalent.
(!!ot to exceed ciCht nonth intervals for any condition.)
3 Cor. fir _ the Icah tcat of the uranium impre nated polyethylene and the neutron sources prior to any c::perinent.
ftcndtr6 procedures for the activity.essurcuent shall be those of tho.7tdiation Safety Office or equivalent.
(!!ot to exceed sin i.onth intervale prior to any use.)
i e
CXP - 2
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i Appendix A 17 SNM-180 License App.'ication October 1997 A17 - Dose Measurements
(
POSITION RADIATION SOURCE 1
2 3
4 METER TYPE BARE 3 " POLY 6" POLY GRAPHITE l'M-797 S
O O
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lSU-14TW Il S+y limr/ hr 6 mr/ hr 3 m r/hr limr/ h r SU-14 T W l
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120/cm sec 45/cm sec FOILS NONE 4
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