ML20148K848
| ML20148K848 | |
| Person / Time | |
|---|---|
| Site: | 05000192 |
| Issue date: | 12/31/1987 |
| From: | Bauer T, Klein D TEXAS, UNIV. OF, AUSTIN, TX |
| To: | NRC |
| References | |
| NUDOCS 8804010022 | |
| Download: ML20148K848 (66) | |
Text
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. t NUCLEAR REACTOR LABORATORY TECHNICAL REPORT THE UNIVERSITY OF TEXAS COLLEGE OF ENGINEERING DEPARTMENT OF MECHANICAL ENGINEERING
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1987 ANNUAL REPOTiT fl 1* of
) The University of Texas,at Austin l Nuclear ?ngineering Teaching Laboratory Taylor Hall Room 104
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January 1, 1987 - December 31, 1987 i
D. E. Klein, Director 512/471-5136
. T. L. Bauer, Supervisor 5-512/471-5787
'a January 1988
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. . i 1987 TABLE OF CONTENTS List of Tab 1es................................... 3
- List of Figures.................................. 4 I. Introduction..................................... 5 II. Laboratory Administration........................ 9 A. Organization B. Personnel C. Cotuittees D. College Report III. Laboratory Development. . . . . . . . . . . . . . . . . . . . . . . . . . 14 A. Organization B. Nuclear Engineering Teaching Laboratory C. Nuclear Reactor Laboratory D. Neutron Activation Analysis Laboratory E. Nuclear Radiation Laboratory
- IV. Facility Operations Sunnary. . . . . . . . . . . . . . . . . . . . . 17 A. Operating Experience B. Reactor Shutdowns C. Reactor Utilization D. Reactor Maintenance E. Facility Changes F. Area Radiation Surveys G. Radioactive Effluents and Waste V. Laboratory Inspections.......................... 30 A. NRC Inspections B. TDH Inspections VI. Public Service Activities....................... 31 VII. Research Activities............................. 32 VIII. Publications from the Nuclear Engineering Teaching Program........................... 39 A. Ph.D. Dissertations B. Masters Thesis C. Reports and Papers 2
1987 List of Tables I.id211 lla. f.AfJL
- 1. Administration and Committees 11
- 2. Facility Personnel 12 3 University Courses 16
- 4. Reactor Safety System 18
- 5. Safety System Events 18
- 6. Performance Data 19
- 7. Annual Utilization Data 20
- 8. Summary of Personnel Radiation Exposures 25
- 9. Radiation Exposure Groups 25
- 10. Laboratory Radiation Levels 26
- 11. Laboratory Contamination Levels 26
- 12. Environmental Surveys 27 13 Monthly caseous Waste Discharge 28
- 14. Monthly Liquid Waste DischarSe 29 ;
- 15. Monthly Solid Waste Disposal 29
- 16. Research Funding 33 l
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1987 List of Figures Ficure h fagg i
- 1. Site Location of Nuclear EngineerinE Teaching Laboratory 7
- 2. Floor Plan of Nuclear Engineering Teaching Laboratory 8 3 Organization Chart of the Nuclear Engineering Teaching Laboratory 10
- 4. Annual Burnup versus Operation Year 22
- 5. Samples Irradiated versus Year 22 I
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1987 I. INTRODUCTION The Nuclear Engineering Teaching Laboratory (HETL) at The
- University of Texas at Austin prepares an annual report to provide information about program activities. Information in this report satisfies the requirements of the U.S. Nuclear Regulatory Commission (NRC) docket number 50-192 and the U.S. Department of Energy contract number At-(40-1)-3919. The report covers the period from January 1, 1987 to December 31, 1987 Activities of the NETL program are part of the College of Engineering Department of Mechanical Engineering. Development of the nuclear program by the university began in the years prior to 1960, with the location of most of the program activities in one of the original engineering buildings. Building space in Taylor Hall provides classroom, laboratory and office areas. The nuclear program was the only engineering program still functional by the year 1985 in the building that has become the location of the College of Natural Sciences Department of Computer Science. Building areas are also the location for parts of the University Computation Center and some other university groups.
- Most NETL program laboratory activities are at two locations in Taylor Hall. Floor plans of these two laboratory areas, a Nuclear Reactor Laboratory and an Activation Analysis Laboratory, are shown in Figures 1 and 2. The Nuclear Reactor Laboratory is the site of a TRIGA Mark I reactor that operates in steady-state and pulse modes. Power operation of the reactor is at 250 kilowatts steady-state and approximately 250 megawatts pulse. At the time of initial facility acceptance the power level was at 10 kilowatts. The Activation Analysis Laboratory provides gamma spectroscopy systems for analysis of neutron activation reactions. These reactions are products of irradiation experiments in reactor experiment facilities. Data acquisition and analysis is done with high efficiency, high resolution detectors.
Intrinsic purity germanium detectors provide radiation detection with automatic control and acquisition systems run by microce,mputers.
Other NETL program laboratory activities are at Jocations in the Engineering Science Building. This building provider a multipurpose facility for several engineering and science prograes. A Nuolear Radiation Laboratory provides an experiment facility for flux and energy j measurements of neutrons from fusion, fission, and other neutron ,
production reactions. Three sources available ars the D-T reaction from a Cockcroft-Walton type accelerator, spontaneous fission reaction from 3
the isotope californium-252 and the alpha-neutr'an reaction from plutonium-beryllium. Activities of the laboratory include detection, measurement and analysis, g i NETL program equipment and materials provide support for different types of facility activities. Supplemental equipment and radioactive materials includo a suboritical assembly, gamma irradiator, portable x-ray unit and various isotopic radiation sources. Equipment, instrumentation systems and detection devices for monitoring, 5
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l 1987 measurement and calibration of ionizing radiation are in routine use or available for special applications. Radioactive material inventories contain radioisotope sources for gamma rays, neutron emissions, x-ray !
excitation, and reference standards for several types of experimental programs. !
Development goals of the university and engineering have been the cause of a major change to the NETL program. Initiation of a, project to move hetivities of the NETL program to the Balcones Research Center (BRC) began in October 1983 and should continue into early March 1989.
The program move is in response to needs of the main campus for expansion of other educational programs, addition of research facilities, and the development of the research center into a major research site for science and engineering.
A Dismantling and Decoc:missioning, DDP, Plan (docket 50-192) for the Taylor Hall facility was submitted to the Nuclear Regulatory Commission (NRC) on May 3, 1985. An order to authorize the activities that will lead to the license terminat?.on was issued on March 9, 1987 Project plans indicate that the DDP activities will occur in the last quarter of 1988 and first quarter of 1989.
Project authorization to move NETL program activities to the l Balcones Research Center (BRC) site was approved by The University of l Texas System Board of Regents on Ootober 13, 1983 A submittal for a l construction permit and an operation license was made to the Nuclear Regulatory Commission on November 9,1984. Subsequent to a site visit on January 22 thru 24 a license amendment was requested on February 27, and responses to NRC questions were prepared. The construction permit was issued June 4, 1985.
Preliminary architectural and engineering plans were approved by I The University of Texas System Board of Regents on August 8, 1985. I Final plara were approved on April 10, 1986 arJ the bid to a general contractor was awarded on December 4, 1986. CIT Construction Inc. of ,
Stafford, Texas, was specified as the general contractor and start of l construction was recorded on February 10, 1987 Facility completion is I scheduled for 16-18 months after start of construction. )
The Balcones Research Center iacility will provide laboratories for the TRIGA reactor, a neutron generator, radiation measurement systems, I preparation and processing of radioactive samples, and office space.
Although the facility will move the present TRIGA facility and other program activities into a single building at the Research Center, ,
several improvements to the reactor facility will extend facility capability. These include above ground shield structure for access to horizontal beam tubes, and an increase of power and pulse parameters.
Plans are to utilize the present fuel and cove some other components j from the old to the new facility. A few components such as control rod drives will be subject to rework procedures to assure appropriate functional operation. Many components such as reactor structure, instrumentation, and control system will be new components.
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'3 Figure 2 Floor Plan of Nuclear Engineering Teaching Laboratory 8
1987 II. LABORATORY ADMINISTRATION A. Organization
' The present organizational chart of the NETL program is presented in Figure 3 Budgeted NETL staff funding is provided for a Supervisor / Assistant Director, research associate, technician / operator, operator, and secretary. Budget support is divided into full time positions for supervisor, technician and research associate; half time for an operator; and quarter time for a secretary.
B. Personnel Personnel associated with the laboratory consist of NETL staff, faculty, students, and certain other university personnel. The personnel involved in the NETL program during the past year are sutunarized in Table I.
C. Standing Committees Two committees monitor the activities of the NETL programs. The
!Iuclear Reactor Committee functions through the College of Engineering and the Radiation Safety. Committee functions through the Office of the President.
- 1. Nuclear Ecactor Cotnittee The Nuclear Reactor Committee convened to review the activities related to facility operation during each quarter of the calender year.
Committee meeting dates were April 16, July 3, October 22 and January 16, 1988. The committee composition is shown in Table 2. Committee responsibilities are the reactor operation, associated facility activities and engineering programs.
- 2. Radiation Safety Committee The Radiation Safety Committee convened to review radiological safety practices at the university during each academic term. Committee cecting dates were April 8, 1987 and November 12, 1987. The committee composition is shown in Table 2. Committee responsibilities are the activities of university research programs that utilize radiation source materials.
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1987 Office, President University of Texas at Austin
!.adiation Safety Committee Executive Vice President and Provost 4
Dean College of Engineering Nuclear l Reactor !
Committee I l
Chairman Department of l Mechanical Engineering I i
Director )
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Operations e
Responsibility
. Communication - - -
FiEure 3 Organization Chart of the Nuclear EngineerinE Teaching Laboratory 10
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1987 Table 1
. Administration and Committees Administration The University of Texas System Board of Regents Chairman Jess Hay Vice Chairman R.B. Baldwin III Vice Chairman S.H. Ratliff Executive Secretary A.H. Dilly
!! ember (1987) !! ember (1989) Hember (1991)
J.S. Briscoe R.B. Baldwin III J.S. dianton B.B. Hilburn Jess Hay S.II. Ratliff T.B. Rhodes Mario Yzaguirre Bill Roden Chancellor Hans Mark The University of Texas at Austin President (app. 9/1/85) William H. Cunnin6 ham Executive Vice President and Provost (app. 9/1/85) Gerhard J. Fonken Dean of the College of Engineering Earnest F. Gloyna (rem: 8/31/87)
Herbert H. Woodson (app: 9/1/87)
Chairman of Department of Mechanical Engineering Grady H. Rylander (rem: S/31/87)
John R. Howell (app: 9/1/87)
Ifuelear Reactor ,Committqg Chairperson: H. L. Marcua (app: 9/1/77)
!! ember: N. E. Hertel (app: 4/1/79) tiember: D. E. Klein (app: 9/1/77)
Hembar: J. O. Ledbetter (app: 9/1/71)
!! ember: L. Rabenberg (app: 9/1/87)
Member, student: R. D. Manteufel (app: 9/1/85)
Ex officio member: T. L. Bauer (app: 6/1/78)
Ex officio member: H. W. Bryant (app: 11/1/73)
Ex officio member: E. F. Gloyna (app: 4/1/70, 8/31/87)
Ex officio member: H. H. Woodson (app: 9/1/87)
Ex officio member: H. G. Rylander (app: 9/1/76, 8/31/87)
Ex officio member: J. R. Howell (app: 9/1/87) e Radiation Safety _Commi ttee Chairperson: E. L. Sutton (app 9/1/84) 4 Hecber: K. J. Catkey (app: 9/1/83)
Hember: G. W. Hoffman (app: 9/1/84)
Member: D. E. Klein (app: 9/1/83) llembert S. A. Monti (app: 9/1/85)
!? ember: L. O. Morgan (app: 4/1/75)
Ex offi;1o member: H. W. Bryant (app: 11/1/73)
Ex officio member: W. H. Cunningham (app 9/1/85) 11
1987 Table 2 Personnel Facility Personnel Staff Director D.E. Klein Assistant Director / Supervisor T.L. Bauer Research Associate F.Y. Iskander Nuclear Technical Specialist M.G. Krause Technical Secretary D.L. Wood Laboratory Research Assistant R. Clements Laboratory Research Assistant L. Polohlopek Laboratory Research Assistant K. Israels Suceert Personnel Safety Personnel Safety Coordinator H.W. Bryant Radiation Safety Specialist L.W. Hamlin Researchers College of Engineering T.L. Bauer Nuclear Reactor Lab.
F.Y. Iskander Neutron Activation Lab. Research Associate N.E. Hertel Nuclear Radiation Lab. Assoc. Prof.
University Departments E.H.B. Sorenson Pha?macy Assoo. Prof.
J.H. Freeland Home Economics Assoc. Prof.
Stt* dents Engineering University Graduate Assistants D. Hartley F. Beheardi D. Smith D. Durbin A. Patterson-Hine H. Lo R. Savage R. !!anteufel A. Heger Student Assistants R. Clements
. L. Polchlopek K. Israels 12
1987 D. Report to the College of Engineering Each year the Reactor Committee provides a report to the Dean of the College of Engineering describing activities of the committee and a review or assessment of the operation of specific portions of the NETL program concerning the reactor and other radiation producing equipment.
Harris Marcus, Reactor Committee Chairman, summarized the activities during this period saying:
There are two sets of minutes for this years quarterly neetings.
Docket 50-192 deals with the ongoing operation in Taylor Hall and Docket 50-602 deals with the construction of the new facility at Balcones Research Center. The specific items of interest are the following:
- 1. A major portion of the effort in the program was again associated with continuing the development of a new reactor facility at Balcones Research Center as well as for decommissioning arrangements of the existing facility. Plans have progressed in an orderly manner and have been coordinated with NRC personnel. A contract award for the new facility was made December 4, 1986. On
!! arch 9,1987 authorization for dismantling the Taylor Hall facility was received from the lluelear Regulatory Commission.
- 2. For another year the reactor remained operating efficiently while construction and destruction continued all around it. The level of reactor activity for the year was comparable to previous years. Recently, additional neutron activation studies have been initiated with an increase in reactor usage. This was accomplished
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in spite of the very heavy additional work load associated with the new facility and setting up the dismantling of the old reactor.
It is imperative that the personnel involved with the Nuclear Engineering Teaching Reactor be given full support during the construction phase to make sure that the construction problems are satisfactorily solved. In addition, the necessary resources for l dismantling must be made available, i I recommend the committee be reappointed for the coming year and :
that Lew Rabenberg (!!E) be added to the committee and Randy Manteufel be !
the student member. 1986-87 was again a busy and fruitful year for the l NETL. l l
Note: Bids for the facility at the Balcones Research Center were opened October 21, 1986 and award of the general contract was approved December 4, 1986. The University of Texas System Board of Regents entered into a contract with CIT Construction Inc. of Stafford, Texas. Total project cost for the proposed facility was I
$5,452,560. An additional $408,140 is being held in reserve for dismantling activities at the Taylor Hall facility. Authorized total cost is $5,860,700.
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1987 III. LABORATORY DEVELOPMENT A. Crganization
. Dr. Dale E. Klein continued as the Director and Dr. Thomas L. Bauer continued as Reactor Supervisor / Assistant Director during the past year.
The only changes made in the facility staff during the 1987 calendar year were in the area of part time student research assistants.
Kenneth Israels and Lester Polchlopek assisted in various laboratory activities during the summer with Mr. Polchlopek continuing in the Fall.
Bob Clements resigned in September to take employment elsewhere.
The Nuclear Reactor Committee remained unchanged with the exception of the appointment of one additional member. Nolan Hertel, a reactor conmittee member is on leave for the academic year 87-88. New personnel were appointed to the following university administrative positions:
Dean of the College of Enginecring, and Chairman of the Department of Mcchanical Engineering. Dr. H.H. Woodson has assumed the role of acting Dean of the College of Engineering. Dr. J.R. Howell has been appointed chairman of the Department of Mechanical Engineering.
B. Nuclear Engineering Teaching Laboratory The Nuclear Engineering Teaching Laboratory is part of the Nuclear Engineering Program at The University of Texss.
The Nuclear Engineering Teaching Laboratory's central feature is a Mark I TRIGA thermal fission reactor. Originally licensed by the Atonio Energy Commission to operate at 10 kw in 1963, the nuclear reactor and the associated laboratory equipment have been updated over the past years and the research capabilities of the Laboratory are now more diverse. In 1968, the facility license was amended to allow the THIGA reactor to operate at a steady state power level of 250 kw which increased experimental capabilities. ,
Other radiation producing devices maintained by the Laboratory are a 750 curie co-60 irradiator, vertical neutron beam tube, suberitical l assembly, industrial x-ray source, 14 HeV neutron generator, and several isotopio neutron sources. Different types of radiation detection devices provide the capacity to monitor or analyze the various radiation
- sources.
One of the functions of the nuclear reactor and its associated equipment has been to teach and demonstrate the fundamentals of reactor ,
operation. Another function has been the demonstration of specifio !
applications of nuclear technology. Several organized classes routinely utilize the reactor facility and a few others use the facility on an infrequent basis. Courses utilizing the reactor and associated facilities are listed in Table 3 Classes, organizations and groups are l provided tours or demonstrations of the reactor and its associated experimental facilities. Approximately 925 persons were admitted into the reactor facility during the past year.
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The use, operation, regulation and inspection of the Nuclear
. Engineering Teaching Laboratory is controlled by the United States l Nuclear Regulatory Commission, the Nuolear Reactor Committee of The University of Texas, the Director of the Nuclear Engineering Teaching
- Laboratory, the Radiation Safety Committee and the Texas Department of Health Division of Radiation Control.
C. Neutron Activation Analysis Laboratory I
The Neutron Activation Analysis Laboratory has provided nuclear i analytical support for individual projects ranging from student project support for classes to measurements for faculty research projects. l Student project support is in the areas of engineering, chemistry, j physics, geology, biology, zoology, and other areas. Research project j support includes elemental measurements for environmental and !
investigative research projects. Scientific articles based upon the results of sponsored and non sponsored research ty this laboratory have ,
been published or accepted for publication in several journals and I proceedings, and have been presented at conferences at the state, j national and international level. 4 Radiation reasurement systems available include gamma ray spectroscopy with two HpGe detectors coupled to a microcomputer !
- controlled acquisition and analysis system, Si(Li) detector and multichannel analyzer for X-ray measurements, alpha-beta proportional counter, scintillation detectors, neutron detectors and associated electronic modules to accomplish several typen of standard nuclear measurements. An important function of the laboratory is to support various research applications with the neutron activation analysis method or other techniques related to nuolear radiation measurensnts.
1 D. Nuclear Radiation Laboratory The Nuclear Radiation Laboratory la utilized by staff and students ;
of the Nuclear Engineering Program at The University of Texas at Austin. l The laboratory is located in an area of the Engineering Science !
Building. A 14 MeV Texas Nuclear neutron generator is the main feature l of the laboratory. Three californium-252 neutron sources are also i available for use. The facility, with installed shielding, provides an l area where students and staff can perform experiments utiliaing not only the high energy neutrons from the neutron generator but fission spectrum neutrons from Cf252. In addition to the neutron generator and the californium sources, other smaller radioactive sources are also used I within the confines of the Nuclear Radiation Laboratory.
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1987 Table 3 Courses Utilizing the Reactor and Associated Facilities I
Course Number Course Description Mechanisal Encineering Daoartment !
l HE 36tF Introductory Nuclear Laboretory - studies in radioactive decay, activation, detection and measurement.
IfE 361G Reactc? Operations - studiet in nuclear reactor parameters, instrumentation characteristics and regulation.
HE 377K Projcots in Mechar.ical Engineering - individual study and experiment projects for undergraduates.
tie 389R Nuclear Engineering Laborator) - studies for Craduate students in nuclear methods in measurement and analysis.
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HE S339R Special projects course for nuclear engineering laboratory studies as a summer course for foreign students.
HE 397 Current Studies in Engineering - specit.1 projects course for graduate study of selected topics.
Additional fgpynt in DI.htt Decartments GEO 388L Isotope Geology - graduate course CH 376K Advanced Analytical Chemistry - senior level course in instrumental e.nd analytical acthods.
CE 390L Environmental Analysis - graduate course in civil engineering PHR 370K Nuclear Pharmacy - senior level course in measurement and analyeis methods with nuclear pharmaceuticals.
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IV. Facility Operations Summary A. Operating Experience
. During the period no significant deviations from normal operating conditions were observed. Pulse reactor operation remained suspended.
Esta')l1shed operating procedures and other required procedures remained unchanged.
Licensed activities were performed by three persons with Senior Operator Permits, T.L. Bauer, H.O. Krause and R. Clements. Operating activities were in support of reactor operations, nuclear engineering, sample irradiations, research and education or demonstrations. No new experiments were proposed or approved. Excluding operation for demonstration, instruction, routine surveillance, or irotope production, the major experiment perform (d was neutron activation to support various research activities. Maintenance during the period consisted primarily of routine equipment repair and adjustments.
B. Reactor Shutdowns Reactor riutdowns (scrams) occurring during the reporting period are summarized in Table 4, categorized according to the typc of 2nitialing event. Safety system scrams are protective actions to shutdown the reactor that are caused by the proper operation of the safety system but are not the result of ar operator error or an intentional action of the operator. Operator error scrams are the result of judgetent errorr or procedural errors. Instrument and power failure scrams are protective acticns that result from loss of safety system function. Intentional scrams are operator initiated scrams such as tests. Manual action scrams ire classified either safety or intentional as d2termined by the !
cause of the manual scram action. Inadvertent scrams are all ]
unintentional shutdowns of the reactor by the protective action of the i safety system. Table 5 compares the number of inadvertent ahutdowns !
during this reporting period to previous reporting periods.
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1987 Table 4 ')
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Safety System 0 Operator Error i ]
Instrument Error 1 Power Failure O Subtotal 2 Intentional 6 Total 8 4
- . Table 5
- Safety System Events (inadvertent) 1971 13 1981 7 1972 6 1982 6 1963 10 1973 to 1983 6 1964 9 1974 4 1984 5 1965 3 1975 7 1985 2 1966 4 1976 5 1986 9 1967 3 1977 9 1987 2 1968 11 1978 11 1 1969 15 1979 12 1970 11 1980 7 l
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1987 rable 6 Performance Data 1987
- Reactor Operation Hours, Fuel Burn-up and Irradiated Samples Quarter Reactor Total Burn-up Samples Operation Fuel Irradiated (hours) (kwhrs) (number)
First 90.2 6169 192 Second 77.5 15349 442 Third 60.1 13066 418 Fourth 66.1 9202 342 Total 293 9 43786 1394 I
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(1) Reactor operation hours record the console key on time or the i time power is applied to the rod control system.
(2) One full power hour is 250 kilowatt-hours.
(3) Samples that are irradiated in the experimental facil! ties of the reactor such as the RSR, PNT or CT. I i
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1987 Table 7 Annual Utilization Data
. Igar Reactor Total Burn-up Samples j Operation Fuel Irradiated '
(hours) (kwhrs) (number) 1967 154.5 846 265 1968 342.6 28168 2449 l 1969 260.8 49935 18.52 1970 222.0 36477 1640 l 1971 262.5 53912 2990 1 1972 222.8 48389 1946 l 1973 318.6 45794 1347 l 1974 226.5 27641 778 !
1975 207 0 204,0 363 l
1976 135 7 11312 468 1977 139 3 7509 164 1978 171.9 26870 178 1979 311.6 72616 1568 1980 184.1 11760 150 1981 258.5 18165 330 ,
1982 247.6 16150 294 i 1983 260.2 24028 477 1 1984 179.6 24806 667 1985 139.9 18607 473 1986 183 1 18660 633 1987 293 9 43786 1394 l Total 4722 7 605931 20026 l
l Ncte (1) Data for 1967 includes all data recorded for previous operation )
1 at to kW from 1963-1967.
(2) Operation power of 250 kilowatts was initist4d in 1968. 1 I
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1987 C. Utilization Reactor utilization data for this reporting period is summar'. zed in Table 6. A summary of reactor utilization since initici criticality is
'a shown in Table 7 Bar graphs comparing annual burnup and quantities of samples irradiated since initial criticality are shown in Figures 4 and 5.
D. Maintenance During this reporting period maintenance consisted prirarily of routine recair and adjustment.
E. Facility Changes Operation of the reactor in the pulse mode reasins discontinued until the operation characteristics of the compensated cl.aaber as !
related to pul:1ng is established. This evaluation is not planned since current activities of the facility do not require pulsing and no pulsing is planned before moving to the new facility at BRC.
No other facility changes were made during this reporting period.
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1987 Burnup (7housands) 88<
60 h P< r I I 'T 77 f i 20 f -
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67 69 69 79 71 72 73 74 75 76 77 78 79 80 81 82 83 84 85 86 87 Annual Burnup versus Operation Year Figure 4 -
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_ :t U _, . 2 I f"3 E'1 l. M bb l'. i 67 68 69 79 71 72 73 74 75 76 77 78 79 89 81 82 03 14 05 06 07 Figure 5 Samples Irradiated versus Year 22
1987 F. Radiation Exposures A summary of radiation exposures during this reporting pr.riod to facility personnel, students, and visitors is shown In Table 8. The
. average exposure per individual and the greatest expcsure per individual for each group is summarized in Table 9. No exposures in excess of the limits of 10CFR20 occurred during this period.
G. Area Radiation Surveys An annual summary of the normal radiation levels measured in the laboratory is shown in Table 10. The results of routine surface and pool water contamination surveys are summarized in Table 11.
Environmental surveys performed outside the laboratory are summarized in Table 12.
H. Radioactive Effluenta
- 1. Gaseous Wastes Gaseous discharge during the reporting perf.od is limited to leakage of AeAl from the reactor laboratory. The total estimated amount of radioactivity released was calculated based on experimental data.
. A summary of the calculated radioactive gaseous diccharges during the reporting perio t is presented in Table 13
- An eatimate of the release volume is calculated from the product of the monthly nutber of full power hours operated during the period and the effective air leakage rate. Although air leakesa from the laboratory is restricted, an effective air change rate of two per 3
hour (.36 m /sec) is assumed. The total activity released is calculated as the product of the volume released and the equilgbrium egncentration of Ar41 in the laboratory, measured at 4x10' pCi/cm The release point concentration is determined as the product of the equilibriumAr41concentrationintheIgboratory,theeffectiveair leakage rate, release point (0.14 sec/m ), and the actual full !
power hours operated divided by the total number of houre in the !
reporting period. The percent of the maximum permissible ,
concentration (MPC) is ghe relegse point concentration divided by the MFC for Ar41 (4x10~ pC1/cm ) in unrestricted areas.
- 2. Liquid Waste No liquid radioactive waste was discharged during the reporting j period. Efforts are made to tvoid liquid waste disposal by appropriate evaporation or absorption techniques for small volumes l and purification by resin treatment for large volumes.
3 Solid waste The activity and amounts of solid waste discharged during the reporting period are summarized in Table 14. All solid waste 23
l 1987 materials were packsged and shipped, along with radioactive waste generated in other departrents, by the Safety Office. Waste shipments are performed by Texas Nuclear, Austin, Texas.
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1967 Table 8 Sunmary of Personnel Raciation Exposuris Ranga gf Exposure in 1121 EMahar af Individuala Staff Students Visitors No measurable exposure 5 18 857 Heasurable exposure less than 0.1 3 4 68 0.1 - 0.25 0 0 0 0.25 - 0.5 0 0 0 0.5 - 0 75 0 0 0 O.75 - 1.0 0 0 0 Ta51e 9 i
- Radiation Exposure Groups 1
4 Exocaure man Individuni it at25 Groun Avarate ~ Greatent i Staff 13 50 Students < 10 20 i
Visitors < 10 < 10 i
i !
25
'l
-w -. ,
c2 1987 1
l Table 10 l Laboratory Radiation Levels Location Average (mR/hr) )[gigyg (mR/hr)
Control Console Area 7x10^-3 3x10^-2 10 ft, from core axis 6 f t. above pool Water System Area 2x10"-2 1x10*-1 l 12 ft. from core axis j 4 ft. above pool l Above Core 2x10*-1 3x10*-1 0 ft. from core axis 16 ft. above pool l
1 Table 11 Laboratory Contamination Levels I Location Averare Maximum Floors 19 dpm 162 dpm Sur faces 18 dpm 39 dpm 4
Pool Water 130 pCi/l 293 pCi/l l 26
-. . - . . - - - . . _ . .- - = . . _. . . . . _- . . . . , .
1987 Table 12 Environmental Surveys Location AY.ar.aga kh i 1 .01 mR/hr .01 mR/hr 2 .01 mR/hr .01 mR/hr 3 .02 mR/hr .03 mR/hr i 4 .01 mR/hr .01 mR/hr 5 .01 mR/hr .01 mR/hr 6 .01 mR/hr .01 mR/hr 7 14 pCi/l 63 pCi/l 4
a !
)
i r
1 l
1 1 l
k 4
e 1
l l
a i
1 1
27
8 e 1987 Table 13 H<'thly Gaseous Waste Discharge (AR00N-41)
MONTH EFPH VOLUME ACTIVITY REL. CONC. 5 MPC (HRS) (H'3) ( C1) ( Ci/CM*3) x10-12 1 7.86 10187 407 22 0.054 2 37 480 19 1 0.003 3 16.44 21306 852 45 0.114 4 11.88 15396 616 33 0.082 5 23 80 30845 1234 66 0.164 6 25.82 33328 1333 71 0.178 7 12.11 15698 628 33 0.084 8 24.05 31169 1247 66 0.166 9 16.10 20866 835 44 0.111 10 12.11 15693 628 33 0.084 11 12 74 16511 660 35 0.088 12 11 96 15499 620 33 0.083 Monthly caseous Waste Discharge (gas or particulate)
Hanth Isotope Total Point of Release Percent of Release Concentration Hasinua
( C1) (m*3) (pC1/m*3) (> 205)
Jan none Feb none Mar none Apr none l Pay none Jun none Jul none Aug none 2sp none Oct none Nov nont Dec none
. Total --
28
l 1987 i
Table 14 Monthly Liquid Waste Discharge Month Isotope Total Point of Release Percent of Release Concentration Maximus
( C1) (a*3) (pCi/a*3) (5)
Jan -
Feb -
Har - !
Apr - !
May -
Jun -
Jul -
Aug -
Sep -
Oct -
h'ov -
Dec -
1 l Table 15 Honthly Solid Waste Disposal Unnih Isotope Total Fora Remarks Release Chemical / Physical
( C1) (ft*3)
Jan -
Feb -
Mar -
3 3 Apr H 6853110 3 Targets & Paper From N. Generator Hsy -
Jun -
Jul -
Aug -
)
. Sep -
, Oct -
!!ov -
)
- Dec -
i 29
1987 V. Laboratory Inspections A. NRC Inspections No NRC inspections took place during the calender year for the R-92 Reactor Facility License.
No NRC inspections took place during the calender year for the SNM-180 special nuclear material license.
A license renewal for the SNM-180 license date May 19, 1987 extends the license to May 31, 1992.
B. TDH Inspection November 23-24, 1987 The inspection consisted of a review of activities and radioactive materials used at The University of Texas at Austin as authorized by TDH License.
e J
f I
I i
i
't 30 l
l
. . I 1987 VI. Public Service Activities Summer High School Science Teacher Symposium A.
The NETL staff organizes and supervises an annual two week symposium designed to familiarize high school science teachers with the theory cnd technology associated with energy resources today. Graduate I college course credit is given to all participants who successfully complete the course. The program is funded by various electric utility companies in Texas. Approximately thirty (30) teachers attend the symposium every year.
B. Lectures and Presentations On numerous occasions during 1987 the NETL staff talked to various organizations about subjects including but not limited to: "Nuclear Reactor Safety," "Nuclear Engineering and Society," "Research and Development cf Energy Resources," and "Energy and the Environment."
C. Reactor Facility Tours
< During 1987, 925 persons visited the laboratory. The largest group visiting the laboratory were persons attending the Texas Energy Science Symposium. Numerous high school students also toured the facility during an event called The World of Engineering, designed to recruit students into the field of Engineering. Students from several local
. hiEh schools and students from several non engineering related college courses visited the facility. Numerous college engineering related classes and several student engineering organizations also toured the facility. Safety personnel such as Austin Fire Department, UT Police Department, UT Safety Office and the Texas Department of Health also visited the facility to remain familiar with the laboratory and emergency response procedures unique to the facility.
D. Fuel Transfer Cask Loan A three element transfer cask was obtained as part of the fuel element acquisition from the Northrup Cc poration. The donated cask is i designed for standard elements of TRIGA fuel and is to be available for l loan to other university reactor programs. A container to ship the i empty cask is also available. Charges for the cask use will apply only l to shipment costs.
31
1987 VII. Research Activities The staff and users of the Nuclear Engineering Teaching Laboratory perform research, as both sponsored and non sponsored projects, in several different areas. Equipment and personnel are provided by the laboratory to supplement the research effort.) of facility users, that include students, faculty and others. The following section lists research projects active during the calendar year. 11ajor research funding or grants are presented in Table 16 for users of the facility.
A. Fuel Assistance Sponsor U.S. Department of Energy Personnel: Dale Klein, NETL Thomas L. Bauer, NETL
Description:
The U.S. Department of Energy has provided research support by providing reactor fuel cycle assistance for the currently operating reactor core at The University of Texas at Austin TRIGA reactor.
B. Summer Science Teachers Symposium
. Sponsor Electric Utility Companies of Texas Personnel: Dale Klein, NETL The Electric Utility Companies of Texas have sponsored Summer High School Science Teachers Symposium, a program designed to familiarize these teachers with the theory and technology of energy sources.
C. Texas Energy Science Symposium Sponsor Texas Atomic Energy Research Foundation Personnel Dale Klein, NETL Orlan Ihms, Texas Utilities Electric Company The Texas Atomic Energy Foundation has sponsored a symposium for outstanding high school science students for over 25 years. The program is intended to encouraSe students to pursue careers in the sciences or
. engineering. Yearly attendance for the 4 day symposium consists of about 250 students and 150 high school science teachers.
32
1987 Table 16 Research Funding
, Department of Energy Fuel Assistance Program ------
llew tiuclear Engineering Teaching Laboratory (includes D&D for existing facility) 5,860,700 Electric Power and the Environment 20,000 6/87 - 8/87 Texas Energy Science Symposium 6/87-8/87 22,000 National Science Foundation 141,626 9/85 - 8/87
~
l Sandia !!ational Laboratories 90,000 .
l 2/85 - 9/87 Sandia National Laboratories 131,000 :
4/87 - 1/90 j Texas Parks and Wildlife Department 25,400 !
8/31/87 1
l Texas Parks and Wildlife Department 23,000 Subtotal 453,026 TOTAL 6,313,726 I 1
l l
l
? \
4 i
33 1
- - - - .. . .. _ _ . - =- ,
)
1987 i
I Heat Transfer and Friction Factor Analysis for Artificially ;
Roughened Surfaces
- 1 Sponsor: Conter for Energy Studies National Science Foundation University Research Institute Personnel Dale Klein, HETL J. Parker Lamb, Hech. Enc.
Mike Krause, NETL l Michael Michael, Mech. Eng.
Description:
l The proposed research is to determine the heat transfer and friction characteristics for surfaces with discrete roughness geometry. Two major aspects are to be examined in that this is*both an experimental and an unalytical invest.igation. Values of R(h+) and 0(h+) in the !
universal velocity and temperature profiles will be examined. New experimental techniques have been developed at The University of Texas at Austin to measure local heat transfer values surrounding discrete roughness elements. A test assembly to examine artificially roughened surfaces is being designed. In addition, a new analytical method has also been developed to determine R(h+) and 0(h+) values without making detailed velocity and temperature profile measurements. Analytical predictions will be made utilizing fundamental parameters in boundary
'ayer theory coupled with the latest information on rough surfaces using integral techniques. Results from the experimental ~ and analytical methods will be compared in order to gain insight as to the dominant mechanian involved for the use of discrete rough surfaces. This research has fundamental application for heat transfer augmentation.
l Pressure Drop and Heat Transfer Measuraments of Liquid Metal !
Flowing in a Packed Bed Under the Influence of a Magnetic F3 eld l l
Sponsor Center for Fusion Engineering j Texas Atomic Energy Research Foundation Personnel: Dale Kleine NETL Jon McWhirter 1 George Avlonitis, Hech. Eng. l Mike Crawford, Mech. Eng.
Description:
The flow of electrically conducting fluids through porous media in the presence of a magnetic field has recently begun to generate significant
, interest due to potential applications for fusion reactors. This study is designed to examine the pressure drop and heat transfer from a liquid metal (NaK) flowing through a packed bed of stainless steel spheres under the influence of a transverse magnetic field. Results of this investication should have direct applications on the deci;n of fusion 34 l
1987 breeder blankets usinc liquid uotal flowing around sphores of fertilo patorial.
Thermal Analysis of Nuclear Shipping Containers Sponsor: Sandia National Laboratories Personnel: Randy Manteufel Dale E. Klein
Description:
The thermal analysis of shipping containers to be used in the transport of spent nuclear fuel is an important safety issue. Sandia National Laboratories has been involved in safety issues for the transport of nuclear material for many years. The University of Texas at Austin (NETL) has been invcived in the specific issues of thermal analysis of these containers for several years. The current project is e intended to benchmark a thermal analysis computer code (C/TRAN) and pre and post processing software PATRAN-0 using four standard model prtblems. Comparicons will be made with other applicable codes cur rently available at Ut (including IIEATING 5). Sensitivity studies will be performed to further evaluate Q/TRAN's suitability for thermal analysis. Enhancements, if any, that will increase the current capabilities of the software will be suggested and developeo if
, feasible.
i Application of CODRA for shipping Cask Analysis l Sponsor: Sandia National Laboratories Personnel: Randy Hanteufel, Hechanical Engineerinc Dale Klein, NETL Lescription:
A thermal hydraulic computer code, COBRA, has been applied for both I steady state and transient analysis. Previous research at The !
University of Texas at Au* tin involved the modification of the COBRA l code and created a new version COBRA *GCFR AP/UT. The current research is directed towards modifying COBRA 80CFR 4P/UT so that it may be applied to transient conditions for shipping cask analysis. One speciirio i modification will be to develop a more sophisticated model for analyzing radiation heat transport. Results using this code will be compared with the results from Q-TRAN and HEATING-6 where possible. In addition, j reconcendations will be made regarding COBRA's use for dry storage analyses.
35
k I
1987 i
- Transportation Analysis of Spent Fuel & High Level Wastes Sponsor
- Nuclear Engineering Teaching Laboratory Personnel Danny Smith, NETL
- , Dale Klein, EETL Thomas L. Bauer, NETL
Descriptions The current methodology (i.e., overall plan for analysis which .
intecrates discrete computer codes and other computational elements) for
- analysis of high-level waste and spent fuel transportation is not -
1 directed toward minimizing radiation exposure but rather is an attempt to demonstrate minimum coepliance with statutory and reCulatory requirements. The current models (i.e., algorithms and computer codes) l j exhibit deficiencies and the thesis to be examined for this work is that !
more representative and credible models can be developed for radioactive l e waste transportation analyses and those models can be integrated into a l
)
cethodology that allows selection of routes resulting in miniaua l radiation exposure. This work will also examine options for :
cost-effective enhancement of transportation operations with the intent J of minimizit.g public and occupational exposure to radiation as well as I
exposure to radiation and non-radiation transportation risks (recognizinE that elimination of risk is neither possible nor necessary but that achievepont of exposures as low as reasonably achievable, ALARA, is prudent).
Neutron Transport Studies: Neutron Multiplication by l Beryllium I Srinsor: National Science Foundation !
1 Personnel: Molan E. Hertel, Center for Fusion Engineering 1
Description:
The uem of beryllium as a neutron multiplier is central to the j, current fusion breeder design. Recent measurements of beryllium neutron j multiplication and reevalutions of beryllium nuclear data indicate that ;
a the multiplying performance of beryllium previously has been l j overestimated, possibly by as much as 255. If beryllius's performance i i as a neutron multiplier has indeed been overestimated even by as much as '
- 105, the direction of the fusion breeder I;rogram in the United States
, might well change. It is tantamount to the current fusion breeder j concepts that the issue of beryllium neutron multiplication be resolved.
l Therefore, an experiment using a spherical shell of beryllium is being
'. proposed.
i
]
The beryllium experiment has been designed to measure i multiplication resulting from DT, DD, Pube, and 252Cf neutron sources i l beinE placed in a spherical shell. By doinE so the sensitivity of the l cultiplication to spectral shape can be observed. In addition, the use ,
36 1 l
- .- . - - - . _ _ - , _ _ - _ _ - _ . . . . . - - - , . . . . , . . . . _ . - L
1967 of these four sources helps to simulate the effect of neutron source degradation in a fusion reactor. The neutron multiplication will be obtained directly from summing weighted Bonner ball measurements of the neutron leakage. The neutron multiplication obtained in this manner will provide a number which tests the capability of the current beryllium nuclear data to calculate total neutron multiplication.
Measurement of Nutrional and Other Elements in Bread Sponsor: Nuclear Engineering Teaching Laboratory Food Research Center, University of Idaho Personnel F.Y. Iskander K.R. Davis
Description:
Egyptian bread samples were collected from several locations across the country. Cereal and other ccaponents used for bread making depend on location (city, village or nomad). The objective of the study is to determine the concen' ration of nutritional elements in the different bread samples and to study a possible correlation between the iron content of bread and cases of iron deficient anemia.
Comparison Between Imported and Locally Manufactured Baby Food in Nigeria Sponsor: Nuclear Engineering Teaching Laboratory Dept. of Chemistry, University of IPE, Nigeria l Personnel: F.Y. Iskander 0.I. Asubiojo l
j
Description:
The concentration of nutritional, probably nutritional and toxic trace elements in baby food locally produced in Nigeria were compared to imported brands. Based on the total element content no significant difference was observed between local and imported baby foods. However, I l
mineral bio-availability from the different brands may vary.
New Method for the Determination of Iodine Value by Instrumental Neutron Activation Analysis
, Sponsor: Nuclear Engineering Teaching Laboratory Personnel: F.Y. Iskander !
I
Description:
1 !
HessurinC the degree of unsaturation for oils and fats, as expressed by 37 ,
1987 iodine value (I.V.), is an important step in the production of shortenings and margarine fats. Measuring I.V. is also nf great importance to detect adulteration of vegetable oilt with highly saturated animal fats and mineral oils. Early methods for the
- determination of I.V. depend on mixing a halogenating agent with the nil sample for a certain period of time, then titrating the residual unreacted halogenating agent. Most of these methods require preparation of special reagents, large sample size, and handling of corrosive or toxic chemicals. In addition, a long time (up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />) is required to prepare fresh reagents before starting the analysis.
A new microanalytical method has developed to measure the 1.V. of oils and fats. Bromine vapor was used to saturate the ethylenic double bond in the oil samples. The quantity of Br reacted was determined ty instrumental neutron activation analysis (INAA). The analysis of 50 samples was completed in 75-100 ninutes (compared to several days by other methods).
Determination of Selenium. A quality assurance project to evaluate the minimum detection limit.
Sponsor: Department of Parks and Wildlife, State of
. Texas Personnel T. L. Dauer F.Y. Iskander
Description:
The Department of Parks and Wildlife for the State of Texas is interest.ed in deterraning the concentration of selenium, in fish, in several lakes across the state. To evaluate the quality of enalysis, the department requestec the participant laboratory to analyze a number of biological matertal for selenium content. No significant variation was obset ved between the results reported from !!ETL and tbs certified values (except for one sample). Results of the analysis were intended to provide quality assurance irformation to the department on the cohuurement methods performed by several laboratories.
Selenium and Other Metals in Fis.1 Tissues Sponsor: Department of Paris and Wildlife, State of Texar
- Persornel: T.L. Bauer F.Y. Iskander
Description:
Tissue from nusole and liver of fish samples from several TeLas lakes are analyzed for acieral elements known to be toxic. Elementa of interest are relanium, arsenic, scacury and zinc. This measurement is part of an environmental program for the State to examine the canditions of waters subject to certain types of power plant or fndustrial effluent releases, 36
t VIII. Publications From the Euclear Enrineerina Tamehans Laboratorv Ph,D. Dissertations
- 1. R.D. O' Dell, "The Angular Thornal Neutron Spectrum in the Vicinity of the Interface Eetween Two Media", Ph.D. Dissertation, The University of Texas at Austin,186 pp., January 1965.
- 2. B.E. Thompson, Sr., "Cryogenic Neutron Spectra !!easurements ,
Across a Discontinuity in Temperature and Properties", Ph.D.
Dissertatior., The University of Texas at Austin,149 pp., January 1965.
3 M.G. Stevenson, "Investigations on the Macroscopic Nodal Approach to Space-dependent Nuclear Reactor Kinetics", Ph.D. Dissertation, The Univercity of Texas at Austin, 203 pp., Au5ust 1968.
- 4. P.J. Rodriguez, "Time and Energy Dependent Neutron D!stribution in a Pulsed llultiplying Medium", Ph.D. Dissertation, The
- University of Texas at Austin, 205 pp., January 1969.
- 5. F. A. Rodriguez-Gonzalez, "Application of Neutron Activation Analysis to the Study of Interstitial Solid Solution of Oxygen in Niobium and in Niobium-Titanium Alloys", Ph.D. Dissertation, The [
University of Texas at Austin, 131 pp., August 1970. <
,, 6. G.D. Atkinson, Jr., "Nondestructive Uranium Assay by Delayed Gamma Ray Analysis Following Californium- 252 Neutron InterroEation", Ph.D. Dissertation, The University of Texas at Austin, 183 pr., August 1971.
7 G.D. Douc'.iey, "The Optimization of Nuclear Systems", Ph.D.
Dissertation, The University of Texas at Austin, 231 pp., August '
i 1971.
- 8. J.B. Whitworth, "The Development and Application of a Syst?natic Approacr. to Elecental Analysis in Forensic Investigations", Ph.D.
I Dissertation, The University of Texas at Austin, ??3 pp.,
i Pecenter 1971. '
.. J. Frein, "Theoretical and Experimental Evaluation of Nuclear Lata and Calculation Techniques for Fusion Reactor Blanket Desiga", Ph.D. Dissertation, The University of Texas at Austin, 210 pp., Deceuber 1972.
- 10. D.C. Anderson, "Fission Product Mass-Yield Measurements from Incertediate Energy Neutron Fission of Plutonium-239 ar,d
. Plutonium-241", Ph.D. Dissertation, The University of Texas at Austin, 125 pp., December 1972.
j 11 J, R. Deen, "l:eacurement of Fission Product Yields from Thorium-232 in a califoi nium-252 Fission Neutron Spectrun a, Ph.D.
Dissertation, The University of Texas at Austin,141 pp., May 1973 39
- 12. T.A. Parish, "Meutronio and Phutonic Analyses of Simulated Fusion Reactor Blankets Containing Thorium and Natural Uranium", Ph.D.
Dissertati ons The University of Texas at Austin, 329 pp., January 1974.
13 J.H. Vanston, Jr., "Use of the Partitive Analytical Forecasting (PAF) Techelque for Analysis of the Effcets of Various Funding and Adginistrative Strat6Sies on Nuclear Fusion .'ower Plant Developnent", Ph.D. Dissertatior, The University of Texas at Austiri, 459 pp., Jahuary 1974,
- 14. E.H.B. Soransen, "Thermal Effects on the Biological Magnification of Arsenic in Green Sunfish,19pouis Cyanellus", Ph.D.
Dissertation The Vaiversity of Taxas at Austin, 233 pp., May 1974.
- 15. S.P. Nichols, "Application of tbs Partitive Analytical ForecastinE (PAF) Technique to the United States Controlled Thermonuclese Research Effort," Ph.D. Dissertation,liechanical En61 neering (l'uclear Engineering) Department, The University of Texas at Austin, December 1975
- 16. C.T. Rombough "The Total Energy Investment in Nuclear Power
. Plants", Ph.D. Dissertation, The University of Texas at Austin, January 1975.
. 17 J.L. MacDonald, "Investigation of Pattern Recognition Techniques for t?.e Identification of Splitting Surfaces in !!onte Carlo Partic15 Transport Calculations", Ph.D. Dissertation, The University of Texas at Austin, August 1975.
- 10. S. A. IkJge, "Determination of Friction Factors and Heat Transfer Coefficients for Flow Past Artificially Roughened Surfaces",
Ph.D. Dissertation, Mechanical Engineering (Huclear Engineering)
Department, The University of Texas at Austin, December 1979.
19 Y. Yang, "Heat Transfer Through A Randomly Packed Bed of Spheres by t.he Monte Carlo Method", Ph.D. Dissertation, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, December 1981.
- 20. H.M. Razzaque, "Finite Element Analysis of Combined Mode Heat Transfer Including Radiation in Gray Participating Media" Ph.D.
Dissertation, Hechanical Engineering (Nuclear Engineering)
Department, The University of Texas at Austin, May 1982.
- 21. G.F. Polansky, "A Finite Element Analysis of Incompressible Laminar and Turbulent Flow with Heat Transfer past Irregular
- Surfaces", Ph.D. Dissertation, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, May 1983 40
I
- 22. T.L. Sanders, "Magnetohydraulic Flow Through a Packed Bed of Electrically Conducting Spheres", Ph.D. Dissertation, Mechanical ,
- Engiraering (Nuclear Engineering) Department, The University of ;
Texas at Austin, May 1985.
23 R.D. Smith, "Routing and Scheduling of Radioactive Material !
Shipments", Ph.D. Dissertation, Mechanical Engineering Department, The University of Texas at Austin, August 1987
!! asters Thesis
- 1. K.L. Gilbert, "Neutron Flux Mapping of a Suboritical Reactor Core with a Polyethylene Reflector", Masters Thesis, Physics (Nuclear EnCineering) Department, The University of Texas at Austin, 61 pp., June 1961.
- 2. T.T. Doss, "Neutron Density Distribution in an Unreflected Suberitical Reactor Core" Masters Thesis, Physics (Nuclear Engineering) Department, The University of Texas at Austin, 63 pp., June 1961.
3 J.M. Norwood, "The Point Source Transport Solution for the Position and Velocity Dependent Neutron Distribution in a Spherical Body of Non-Multiplying Material", Masters Thesis, Physics (Nuclear Engineerin6) Department, The University of Texas at Austin, 75 pp. June 1962.
- 4. R.W. Reed, "Effect of a Cadmium Control Rod on the Neutron Density in a Subcritical Reactor", Masters Thesis, Physics (Nuolear Engineering) Department, The University of Texas at Austin, 85 pp., August 1962.
- 5. P. Derananda, aNeutron Flux Distribution of a Suboritical Reactor Core with a Graphite Reflector", Masters Thesis, Physics (Nuclear Engineering) Department, The University of Texas at Austin, 40 pp., January 1962.
- 6. T.A. Fredericks, "Thermal Neutron Flux Distribution Due to a Plane Wave Source in an Unreflected Reactor Assembly", Masters Thesis, Physics (Nuclear Engineering) Department, The University of Texas at Austin,107 pp., August 1963
- 7. D.O. Martin, "Film Detector for a Neutron Spectrometer", Masters Thesis, Physics (Nuclear Engineering) Department, The University of Texas at Austin, June 5%3 ,
l
- 6. H.L. West II, "Flux Decay Rate in a Reflected Suboritical Reactor", Masters Thesis, Physics (Nuclear Engineering)
Department, The University of Texas at Austin, 55 pp., August i 1963 9 R.S. Kolflat, "An Experimental Approach to the Study of Nucleonic i Fundamenta.ls", Masters Thesis. Mechanical Engineering (Nuclear i i
41 l I
l
Engineering) Dopartment, The University of Texas at Austin,190 pp., May 1965.
- 10. J.B. Whitworth, "A Cryogenio Irradiation Device for the TRIGA Mark I Nuclear Reactor", Masters Thesis, Hechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, 52 pp., January 1967
- 11. D.A. Pullen, "A Rod Oscillator Design and Zero Power Transfer Function Measurement for a TRIGA Hark I Reactor," 1: asters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, January 1967
- 12. 0.F. Halan, "Transfer Function Analysis of Temperature and Xenon Feedback in Coupled-Core Nuclear Reactor Systems", Masters Thesis, Mcchanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, 69 pp., August 1967.
13 F.H. Antunez-Castillo, "Gamma Radiation Dosimetry Techniques and Application to Mapping of The University of Texas Cobalt-60 Irradiation Facility", Masters Thesis, Physics (Nuclear Engineering) Department, The University of Texas at Austin, 60 pp., September 1968.
- 14. R. Valiente, "Neutron Radiography with The University of Texas TRIGA Nuclear Reactor", !! asters Thesis, Physics (Nuclear
. Engineering) Department, The University of Texas at Austin, August 1966.
- 15. J. A. Villalobos, " A Study of Camma Radiation Dosimetry Techniques and Application to Radiation field Mapping", Hasters Thesis, Physics (Nuclear Engineering) Department, The University of Texas at Austin, January 1969.
- 16. M. A. Zuniga, "Delayed Neutron Counting Technique for Uranium Determination", Masters Thesis, Physics (Nuclear Engineering)
Departcent. The University of Texas at Austin, January 1969.
- 17. G.D. Atkinson, Jr., "Investigation of the Dynamic Behavior of a Two-Region Suberitical Reactor", Masters Thesis, Mechanical EnCineering (Nuclear Engineering) Department, The University of Texas at Austin, January 1969
- 18. !!. Gallardo, "Trace Elements in six Quartz Samples by !
Nor. destructive Neutron Activation Analysis Technique", !! asters Thesis, Physics (Nuclear Engineering) Department, The University 1 of Texas at Austin, January 1969
. 19 F.O. Pasos, "Nendispersive X-Ray Fluorescence Analysis using a Lithium Drifted Germaniun Detector", Masters Thesis, Physics (Nuclear Engineering) Department, The University of Texas at 1 1
Austin, 54 pp., January 1969.
42 1
- 20. D.C. Jopling, "The Politics of Nuclear Reactor Siting", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, December 1970.
. 21. A.H. Urdaneta, "A Programmed Associative Analyzer",Ifasters '
Thesis,!!echanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, December 1960.
I
- 22. K.R. Waid, "Solid State Radiation Detection Devices: Fabrication, Techniques and Application to Nuclear Engineering", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, ,
The University of Texas at Austin, January 1970.
23 V.H. Chanto, "!!eutron Activation Analysis of Chlorine and Bromine in Some Haliburton-Bancroft Rocks and Minerals", Masters Thasis, Physics (Nuclear Engineering) Department The University of Texas r at Austin, January 1970.
24 R.J. Gramatges-Figueras, "Neutron Waves in Cylindrical Geometries for a Suberitical Reactor", Masters Thesis, Mechanical EngineerinC (Nuclear Engineering) Department, The University of Texas at Austin, 98 pp., May 1970.
l
- 25 E. Oelkers, Jr., "A Learning Method for Identification of Nuclear Reactor Point Dynamics", Masters Thesis, Hechanical Engineering (Nuclear Engineering) Departcent, The University of Texas at Austin, 165 pp., August 1970.
- 26. J.R. Leen, "Calculaticn of Resonance Integrals Using the Intercediate Resonance Approximation", Masters Thesis, Mechanical l Engineering (Nuclear Engineering) Department, The University of Texas at Austin,140 pp., January 1970.
- 27. C.T. Rombough, "Application of Queneing Theory to closed 4 oop i Computer-Reactor Control Systems", Masters Thesis, Hechanical i Engineering (Nuclear Engineerin?,) Department The University of I Texas at Austin, 78 pp., December 1970. l l
- 28. A.H.U. Bohorquez, "A Programmed Associative Analyzer" Hasters i Thesis, Mechanical Engineering (Nuclear Engineering) Department, i The University of Texas at Austin, 98 pp., December 1970. l 29 J.J. Chromik, "Experimental Determination of the Neutron Flux in The University of Texas Californium- 252 Irradiation Facility",
Masters Thesis, Hechanical Engineering (Nuclear Engineering)
- Department, The University of Texas at Austin, 85 pp., December 1971.
- 30. H.B. Owen, "Fuel Manasement Using Dynamic Programming", Hasters l Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, 59 pp., May 1972.
- 31. C.E. Brauer, "Thermal Neutron Radiography with a Lithium-Lead Collinator-Filter", Hasters Thesis, Hechanical Engineering 43 l l
3
e i
i y
(Nuclear Engineering) Department, The University of Texas at Austin, 64 pp., May 1972.
(.
- 32. J.L. MacDonald, "Heuristic Learning Control for Nuclear Reactors", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, 131 pp., August 1972.
33 S.G. Barbee, "Neutronic Calculations in a Simulated Fusion Reactor Blanket", Masters Thesis, Hochanical Engineering (Nuclear '
Engineering) Department, The University of Texas at Austin, 259 pp., Novsuber 1972. ,
34 D.M. Williams, "Identification of Thermal Feedback Parameters for !
4 a TRICA Mark I Reactor", Masters Thesis, Electrio Engineering l Department, The University of Texas at Austin, 53 pp., December 4
- 1972.
i
- 35. L.D. Hansborough, "Overall Tritius Considerations for Controlled Thermonuclear Reactors", Masters Thesis, The University of Texas at Austin, 154 pp., May 1973 ,
- 36. M.E. Senglaub, "Cross Section Studies Based on the Statistical Model", Masters Thesis, The University of Texas at Austin,109 ,
pp., August 1973
, 37 S.P. Nichols, "Experimental Determination of Neutron Fermi Age ;
4 from Californium-252 Fission Spectrum to Cadmiun Covered Indium Resonance in a Graphite Medium", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University cf Texas at Austin, 101 pp., January 1974.
- 38. Thomas L. Eauer, "Discrimination of Uranium-235 and Plutonium-239 i by Cyclic Activation and Delayed Caena Ray Analysis Using j Californium-252 as a Neutron Interrogation Source", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin,178 pp., August 1974.
- 39. Olmn D. Thompson, "Optimization of Shipping Containers for Radioisotopic Neutron Sources", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, 30 pp., (August 1974).
- 40. J.W. Davidson, "A Cost-Benefit Analysis for Partitioning i Strategies Involved in High-Level Nuclear Waste Management",
- Masters Thesis, Mechanical Engineering (Nuclear Engineering)
Department, The University of Texas at Austin, May 1975.
I
), 41. J.P. Percy, "Experimental Determination of Local Convective Heat 1
Transfer Coefficients over a Ribbed Surface", Masters Thesis,
! Hechanical Engineering (Nuclear Engineering) Department, The l University of Texas at Austin, May 1979.
)
l 44
- 42. G.A. Taylor, "The Analysis of the Crid Spacer Pressure and Temperature Effects in SAGAP0", Masters Thesis, Hechanical L Engineering (Nuclear Engineering) Department, The University of Texas at Austin, August 1979. ;
43 D.D. Hsu, "Determination of the Relative Toxicities of ths [
Fission Products Produced in the Transmutation of Actinide Wastes", Masters Thesis, Hechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, ,
recember 1979
- 44. M.A. Ross, "Electrical Power Generation and Process Heat Application for Coal Gasification and Liquefaction Using a Very-High Temperature and Gas-Cooled Reactor", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, May 1980.
- 45. T.L. Sanders, "An Alternative Huaerical Method for the Steady State and Transient Thermal-Hydraulio Analysis of Gas-Cooled Fast Breeder Reactor Arrays", Haccers Thesis, Mechanical Engineering l (Nuclear Engineering) Departacht, The University of Texas at Austin, May 1981.
. 46. J.E. Hamann, "Thermal Analyais of a Spent Fuel Railcar Shipping Cask in an Engulfing Fire", Masters Tnesis, Mechanical 3 Engineering (Nuclear Engineering) Department, The University of I
. Texas at Austin, May 1983 )
- 47. 11. Ally, "Preconcentration Method for the Determination of ,
Uranium, Thorium and Transition Elements Using X-Ray Fluorescence and Activation Analysis", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at ,
Austin, May 19P3
- 48. A. Patterson-Hine, "Characterization of the Effects of Continuous l I
Salt Processing on the Performance of Holten Salt Fusion Breeder Blankets", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, May 1984.
49 E. IbrahirJ, "Determinin5 the Itinimum Plasma Minor Radius for a Power Balancett Rt tersed Field Pinched Device at Ignition",
Masters Thesin, Mechanical Engineering (Nuclear Er.gineering)
Department, The University of Texas at Austin, December 1984.
. 50. H.G. Krause, "Design and Fabrication of a Texas Assembly for tno Evaluation of Heat Transfer in Flow Past Discrete Foughness Elements", Masters Thesis, Hechanical Engineering (Nuclear )
. Engineering) Department, The Uriversity of Texas at Austin, 1 December 1984 l l
- 51. R.D. Savage, "Error Analysis for a Hydrogen Filled Benjaetn !
Counter", Masters Thesis, Mechanical Engineering Departa9nt, The University of Texas at Austin, December 1984.
I 45 i
. . l
}
l
> 52. A. Sharif-Hocayoun, "Comparison of Parametric Empirior.1 Bayes l with Maximum Likelihood Estimators When Applied to Nuclear Reliability Data -- A Simulation Study", Masters Thesis, '
Hechanical Engineering Department, The University of Texas at
. Austir, December 1983 53 R.H. Laucius, "Calculation of the Differential Efficiencies of Organic Scintillators to Neutrons", Masters Thesis. Hochanical Engineering Department, The University of Texas at Austin, May 1983
- 54. R.D. Manteufel, "A Numerical Method fo.* the Solution of the Heat Diffusion Problem Which Links the Galerkin Finite Element Method and the Control Volume Finite Difference Method", Masters Thesis, Mechanical Engineering Department, The University of Texas at Austin, December 1987.
i Reports and Papers a
- 1. D.G. Anderson, "A Technique for Recoil Fission Fra; nent Rance a Measurements", Health Physics, 32L'3, 558 ( April 1966).
!. 2. .J. Rodrigue: and D.H. Nguyen, "Time Decay Constants in Pulsed Hultiplying Media", Trana. imer. Nucl. Soc. iiri, 269 (June 1968).
3 P.J., Rodriguez and D.H. Nguyen, "The Maximum Eigen-value in the ,
Pulsed-Neutron Initial-Value Problem", Trans. a mm e . Nuel. Soc.
1112, 576 (November 1968).
- 4. P.J. Rodriguez and D.H. Nguyen, "Contribution of the Continuum to the Neutron Transient Behavior in a Pulsed Multiplying Cylinder",
Trans. Acer. Nuel. Soc. 1112, 582 (Novester 1968). ,
I S. G.D. Boachey and S.J. Gage, ' Neutron Radiography with a Small Suberitical Reactor", Temaa. Amer. Nucl. Soc. 12, 462 (1969).
- 6. G.D. Atkinson, Jr., W. Coltharp, R. Cramatges. E. Celkers D.A.
Roberts, K.R. Waid, S.M. Gage, and B.V. Koen, "Project Atlantist A Design of thu Nuclear Power Supply for an Ur.dersea City", Proc. i of the Offshore Technolorv Conference, Dallas, Texas, 1969.
j 7. V. Chanto, S.J. Gage, and D.F. Barker, "Chlorine and Bromine j
. Concentrations in Some Haliburton-Bancroft Rocks and Minerals by 1
. Neutron Activation Analytis", 1969 !
l 8. H. Gallardo, S.J. Cage, and D.F. Barker, "Trace Elettats In l
- Guartz by Nondestructive Neutron Activation Analysis", 1969. '
I ;
! 9. F.A. Rodr16dete S.J. Gage, and K.H. Ralls, "Nondestructive Neutron Activation Analysis for Trace 1mpurities in Niobium",
a presented at the Sever.th Symposium on Nondestructive Evaluation
- 46 .
w
of Components and Haterials in Aerospace, Weapon Systeza, and Nuclear Applications, San Antonio, Texas, 1969. i
- 10. S.J. Gage and M. Zuniga, "Uranium Trace Analysis by Pulsed Reactor Irradiation", Radiation and Isotope Technology in Latin American Development, American Nuclear Society Topical Meeting, San Juan, Puerto Rico, May 1969.
- 11. R.H. Richardson, "Higration and Enzyme Polymorphisms in Natural Populations of Drosophila", Jao. J. Gan., 1969.
- 12. R.H. Richardson, R.J. Wallace, Jr., S.J. Gage, 0.D. Bouchey, and Margaret Denell, "Neutron Activation Techniques for Drosphila in Natural Populations", Studies in Genetics, Marsh 11 R. Wheeler Ed., The Univarsity of Texas Press, Austin, Texas, 1969.
13 0.D. Bouchey and S.J. Gage, "Developst.e and PotenU al '
Utilization of a Neutron Radiography Facility at The University of Texas Nuclear Reactor Laboratory", presented at the Seventh x Symposium on Nondestructive Evaluation of Components and Haterials in Aerospace, Weapons Systems and Huclear Applications, San Antonio, Texas, 1969.
. 14. G.D. Bouchey and S.J. Gage, "Utilization of The University of Texas TRIGA Reactor for Neutron Activation Analysis Service",
ANS/CNA Transac' ions .tl, 287 (1968). '
- 15. 0.D. Bouchey and G. Gjerstad, "Chemical Studies of Aloe Vera '.
Juice -- II. Inorganic Ingredients", ouarteriv Journal of crude Drur Research, ,oJ.a. (1969). ;
- 16. S.J. Gage, R.H. Rich rdson, and 0.D. Bouchey, aNeutron Activation Techniques for Leteling of Insects with Stable Elements", Trana.
Amer. Mucl. Soc., 12, 495 (1969). j 17 0.D. Bouchey, B.V. Koen, and C.S. Beightler, "The Optimal Allocation of Energy in Industrial and Agro-Industrial Complexes l Using Dynamic Programming". Nuel, sei. and rner., 11, 70 (1970).
i 18. 0.F. Malan and B.V. Koen, "A Nonlinear Prograccing Approech to l Optimal Control of Nuclear Reactors", Trann. iner. Huel. Soc., 1 (1970).
]
19 H.G. Stevecson and S.J. Gage, "Application of a Coup' led Fission Mode Approach to Imdular Reactor Kinetics", Journai of Nuel.
Enerrv, 21, I (1970).
l l
- 20. G.D, Bouchey and S.J. C#.t,e, "Neutron RiAiography at The ;
- . University of Text.s Nuclear Resctor Laboratcry", Tsetonen una '
l Had1& Lien Technt,ierv, ,1, 29t (1970).
- 21. 0.D. Bouccey and S.J. Onge, "Detection and Location of Leaking TRICA 2eactor Tuel Elements", GA Publication T-117, Papers and
]
Abstracta, TRIGA Reactors Owners' Sesinar Denver, Colorado, ,
, February 1970. !
1 i 47
! 22. 0.D. Bouchey and S.J. Gage, "Neutron Radiography with a Small Suboritical Assembly", International Journal of Wondestructive Testine, 1970.
, 23 0.D. Atkinson, Jr., J.B. Whitworth, and S.J. Gage, "NAACOL -- A Spectrum Analysis Routine for the Small Laboratory", presented at the 21st Mid-America Symposium on Spectroscopy, Chicago, Illinois , 1970.
24 S.J. Gage, 0.D. Atkinson, Jr., J.B. Whitworth, and A.H.
Pradzynski, "Computer-Aided Multielement Danma Ray Analysis with a Compton Suppressed Ge(L1) Radiation Source", presented at the Ninth National Society of Applied Spectroscopy, New Orleans, Louisiana, October 1970.
- 25. J.J. Chromik and E.L. Draper, Jr., "Energy Integral Tests of Differential Fission Cross Section Data", Trann. imer. Nuci.
222., l'112, 755 (1970).
- 26. S.J. Gage and D.C. Jopling, The Nucler concentt Potential for the SIMB Recion, Southern Interstate Nuclear Board, 250 pp., March 22, 1971.
, 27 0.F. Halan and 3.V. Koen, "Application of Nonlinear Programming to the Optimal Control of a Point Model Nuclear Reactor", Engl.
Sei. and rnen., (1971),
- 28. 0.D. Bouchey, B.V. Koen, and C.S. Beightler, "Optimization of Material Safeguards Samplin8 System". Trann. Amar. Nucl. Soc.,
Winter Heeting, 1971.
- 29. A.H. Pradzynski and S.J. Gage, "Nondestructive Identification of Haterial by Nondispersive X-Ray Fluorescence Spectrosecpy Usint Si(L1) Detectors and Radio-isotopio Sources", Proc. Sichth Synoosium on Nondestructive Evaluation in Aerosence. Waanons Systems. and Nuclear leelientions, San Antonio, Texas, 1971.
- 30. 0.D. Atkinson, Jr. and S.J. Gage, "Uranium Assay by Delayed Gamma Ray Analysis Following Cf-252 Neutron Interrogation", Proc.
Twelf th Annual Meetinc Institute of Nuclear Materials Manarament, Palm Springs, Florida, July 1971.
- 31. S.J. Cage, E. Linn Draper, Jr., 0.D. Bouchey, and R.R. Day, "Design and Construction of a Versatile Cf-252 Source Shield and Experimental Facility", Neutron Sources and loolientions, CONF-710402, 2, Proc. of ANS Topical Meeting, Augusta, Georgia, April 1971.
l
. 32. D.0. Jopling and S.J. Gage, "Public Resistance to Nuclear Reactor Siting", Nuclear News,.1113, 32 (March 1971).
33 J.B. Whitworth 0.D. Atkinson, and S.J. Gage, "Some Recent Applications of Nuclear Analysis Techniques to Typical Forensic Evidence" presented at the 23rd Annual Program American Academy for Forensic Sciences, Phoenix, Arizona, February 1971.
48
(
1 I
34 0.D. Bouchey, E. Linn Draper, Jr. B.V. Koen, and C.S. Beichtisr, "Multiple Foil Activation Spectrum Determination Using a Numerical Direct Search Technique", Trana. A-=r. Nuoi. son.,
,dl2, 667 (October 1971),
t I' 35. 0.D. Bouchey, B.V. Koen, and C.S. Beightler, "The Optimization of !
Nuclear Systems by Geometric Programming, Nucl. Set. and Fnan,,
31, 267 (1971).
- 36. 0.D. Bouchey, B.V. Koen, and C.S. Beightler, "Optimization of Nuc1 car Msterials Safeguards Campling by Dynamic Programming", .
1 Quelear Technoloav, J2,18 (1971), l l
. 37. S.J. Gage 0.D. Atkinsce, Jr., and 0.D. Bouchey, "Cyclic Neutron Activation Analysis with a Cf-252 Neutron Source", Icana, A=ar.
Nuel. Soc,, (October 1971). j
- 38. E. Linn Draper, Jr., "Integral Reaction Rate Datermination Part I Tailored Reactor Spectrum Preparation and Measurenenta, Engla.
sei. and Ener. , ah, 22 (1971).
39 E. Linn Draper, Jr., "Integral Reaction Rate Determination Part II: Fission Rate Measurements", kuel. sei. and rn'".. 31, 31
,. (1971).
I
- 40. 9.D. Bouchey and S.J. Gage, "Detection and Location of Leaking TRIGA Reactor Fuel Elements", Nuaiear Taehnolerv, JD, 211 (1971).
- 41. 0.D. Bouchey and S.J. Oage, ' Neutron Radiography with a Small Suberitical Retotor", Int _ J. of Mondantruettve Testina, 2, 335
('971).
i
- 42. 0.D. Bouchey and S.J. Gace. "The Economics of Subcritical j Radiographya, Trans. amar. Muel. see., ja, 123 (1971).
i 43 0.D. Bouchey, E. Linn Draper, Jr., and S.J. Gage, "Neutron 1 Radf ography with Cf-252: The Effect of Tailoring Neutron Energy Spectra on Photographio Images", Eggiryn sources and Aeolientions, CONF 210402, 3, Proc. ANR Toeie Meetinr, Augusta, Georgia, April 1971.
- 44. 0.D. Atkinson, Jr., J.B. Whitworth, and S.J. GaEe, "Computer-Assisted Analysis cf Gamma-Ray Spectraa , comouter Physica enmmunientions, 2, 40 (1971).
. 45. S.J. Gage, E. Linn Draper, Jr., and 0.D. Bouchey, "Recent Developments in Radioisotopic Source Neutron Radiography *, Irgsu.
Elahth Synconium on ggndgatructive Evaluation in Aaronomea.
, }feanen Svatama, and Muelear len11eatiota, San Antonio, Texas, 1971.
- 46. E. Linn Draper, Jr., Mary Elizabeth Foster, and 0.D. Bouchey, "X-Ray Fluoreecence Analysis and Neutron Activation Analysib in 49
4
. O an Analytical Chemistry Laboratory", presented at the Combined Meeting of the Texas Association for Radiation Research and SSuth Central Photobiology Group, !!ouston, Texas, November 1971.
47 E. Linn Draper, Jr. and 0.D. Bouchey, "Utilization of a Portable Californium-252 Source for Neutron Activation Analysis and Neutron Radiography", presentec at the Combined Meeting of the Texas Association for Radiation Research and South Central Photobiology Group, Houston, Texas, November 1971.
- 40. E. Linn Draper, Jr. and J.J. Chromik, "Production and Measurement of a Reference Spectrum in a Versatile Experimental Facility",
Trans. _im?r. Nucl. Soc. , .liti, 157 (1972). t
- 49. E. Linn Draper, Jr. and Andrzej J. Pradzynski, "Identification of Alloys by Energy Dispersive Y-Ray Spectroscopy", presented at the Ninth Symposium on Nondestructive Evaluation, 1972.
- 50. 0.D. Atkinson, Jr. , E. Linn Draper, Jr. , and 0.D. Bouchey, ,
"Subcritical TRIGA Reactivity Heasurements Using the Source Jerk Technique", presented at the TRIGA Owners' Conference II, College Station, Texas, 1972.
, 51. 0.D. Atkinson, Jr. sr.d E. Linn Draper, Jr. , "Transient Rod Failure in a Pulsing TRIGA !! ark I Reaetor", presented at the TRIGA Owners' Conference II, College Station, Texas, 1972.
- 52. 0.D. Atkinson, Jr., "A Safeguards Minicourse", presented at the 16th Annual Heeting of the American Nuclear Society, Las Vegas, Nevada (1972).
53 0.D. Atkinson, Jr., E. Linn Draper, Jr., 0.D. Bouchey, and S.J.
Cage, "Radioisotopic Source Amplification Using a Heteroger.eous Suberitical Assembly", Proc. 18th Annual Meetine of the leeriegg Enslear Society, Las Vegas, Nevada (1972).
54 E. Linn Draper, Jr. and 0.D. Atkinson, Jr., "Transient Rod Failure in a Pulsing TRIGA Hark I Reactor", published in Proc. of 2nd TRIG A Dwners' Conference, February 1972.
- 55. E. Linn Draper, Jr., John W. Davidson, S.J. Gage, and 0.D.
Bouchey, "A Systcm for Reduction of 41A Release from a Research Reactor Facility", Trans. Amer. Nucl. Soc., 1511, 4 (1972).
- 56. E. Linn Draper, Jr., et al, "Standard for the Development of
, Techaical Specifications for Research Reactors", Trans. Antti Nucl. Soc., (1972).
- 57. E. Linn Draper, Jr., 0.D. Atkinson, Jr., and B.B. Tomlin, "A Radiography and Capture Gamma Ray Facility for Californium-252",
Proc. of the American Nuclear Society "Aeolientions et Californiue-252' National Terical Meeting, September 1972.
50
. o i
- 58. E. Linn Draper, Jr., G.D. Bouchey, G.D. Atkinson, Jr., and S,J. '
Gage, "A Versatile Suboritical Assembly for Undergraduate Nuclear Engineering Instruction", Proc. of the Angrican Nuclear Society "Acolications of Californium-262" National Toeical Meetina, September 1972.
l 59 E. Linn Draper, Jr. and S. J. Gage, "The FusionFission Breeder: !
Its Potential in a Fuel Starved Thermal Reactor Economy",
presented at the 93rd Annual Meeting of ASME, New York,1972.
- 60. E. Linn Draper, Jr., "Technological Innovation and Assessment: A Novel Course for Nuclear Engineering", presented at the Winter Meeting of ths American Nuclear Society, November 1972.
- 61. D.T. Hall, E. Linn Draper, Jr., and P.S. Schmidt, "Management of the Transition to Nuclear Power Generation", Technical Report ESL-3, Energy Systems Laboratories, College of Engineering, The University of Texas at Austin, December 1972.
- 62. P.S. Schmidt and 0.0. Park, "Heat Dissipation in a Power Plant Cooling Bay", ASME, Paper No. 72-WA/HT- 61, November 1972.
63 P.S. Schmidt and 0.P. D' Arch, "Entry Region Effects on Flow and Pressure Drop of Lithiuu in Fusion Re- actor Blankets", Proc. of the Texas Symoosium of Technolory of controlled Thermonulaar Fusion Exoerinents and Engine.erinn Asoects of Fusion Reactors,
. Austin, Texas, November 1972.
- 64. E. Linn Draper, Jr. and Charles Brauer, "Lithium-Lead Collimator Fabrication for Radioisotopic Source Neutron Radiography", Irang.
Amer. Nucl. Sqq. , .15.1.1, 142 (1972) .
- 65. E. Linn Draper, Jr. and James B. Freim, "Theoretical and Experimental Evaluation of Nuclear Data and Calculation l Techniques for Fusion Reactor Blanket Design", presented at the Texas Symposium on the Technology of Controlled Thermoraclear Fusion Experiments and the Engineering Aspects of Fusiaa Reactors, November 1972.
- 66. E. Linn Draper, Jr., "Status of CTR Related Integral Experiments" presented at the Conference on Nuclear Data and Neutronics of CTR Blankets held in Seattle, Washington, September 1972. 4 1
- 67. E. Linn Draper, Jr., "Fusion Reactor Engineering in the Nuclear Engineering Curriculum at The University of Texas at Austin",
Trans. Amer. Nucl. Soc., (1972).
- 68. E. Linn Draper, Jr. and S.J. Gage, "The Fusion Fission Breeders j Its Potential in a Fuel Starved Thermal Reactor Economy", i presented at the Texas Symposium on the Technology of Controlled '
Thermonuclear Fusion 2xperiments and the Engineering Aspects of l Fusion Reactors, November 1972. ,
51
~
i
- l. .
69 James B. Frcim and E. Linn Draper, Jr., "Experimental Determination of the Fusion Spectrum in Graphite", Trana. (mer.
Nucl. Soc., (1972).
, 70. G.D. Atkinson, Jr., S.J. Gage, and G.D. Bouchey, "Cyclic Activation with a Californium-252 Source", Nuclear Technology (1972).
- 71. G.D. Atkinson, Jr., "Whhc You Always Wanted to Know about Californium Source Facilities", Invited Paper, National Topical Heating on the Applications of Californium-252, Austin, Texas (1972).
- 72. T.L. Bauer and G.D. Atkinson, JP., "Discrimination Between Plutonium and Uranium by Gamma Ray Analysis Following Cf-252 Interrogation", presented at the National Topic 1 Heeting on the Applications of Californium-252, Austin, Texas, 1972.
73 E. Linn Draper, Jr., Fditor, Proc. of Teran Symoosium on the Technolocv of Controlled Thermo- nuclear Fusion Erneriments and the Ennineerine Asoects of Fucion Reactors, published by USAEC.
- 74. E. Linn Draper, Jr., Editor, Proc. of the Tmolications of Nuclear Power in Teras, published by the Texas Atomic Energy Research Foundation.
- 75. E. Linn Draper, Jr. , J.R. Deen, and J.J. Chromik, "Measurement of the Integral Fission Cross Section of Th-232 in a Cf-252 Fission Neutron Spectrum", Trans. As51. Nucl. Soc., (1973).
- 76. D.G. Anderson and E. Linn Draper, Jr., "Fission Product Mass-Yield Measurements from Intermediate Ener6y Neutron Fission of Plutonium-239 and Plutonium-241", Trana. Amer. Nucl. Soc.,
(1973).
- 77. E. Linn Draper, Jr. and James B. Freim, "Experimental Determination of the Fusion Spectrum in Graphite", Trans. Amer.
Nucl. Soc., 11, 9 (1973).
- 78. E. Linn Draper, Jr. , "Fusion Reactor Engineering in the Nuclear Engineering Curriculum at The University of Texas at Austin",
Trans. Amer. Nucl. Sna., 11, 16 (1973).
- 79. E. Linn Draper, Jr., Theodore A. Parish, and Brian J. McArdle, "A Neutronic-Photonic Comparison of Vanadium and Niobium Containir5 Fusion Reactor Blankets", Trans. Amer. Nucl. Soc., (November 1973).
, 80. John H. Vanston, Jr., "Use of Partitive Analytical Forecasting (PAF) Techniques for Fusion Development Analysis", Trana. Ame r.&
- Nucl. Soc., (November 1973).
52
' ,s'
- 81. Theodore A Parish and E. Linn Draper, Jr., "Neutronic and Photonic Analyses of Fusion Reactor Blankets Containing Thorium",
- presented at the Fifth Symposium on Engineering Problems of Fusion Research, Princeton, New Jersey, November 1973 82.
C.E. Locke and D.R. Paul, "Graf t Copolymer tbdification of Polyethylene-Polystyrene Blends. I. Graft Preparation and Characterization", Journal of Aeolied Polymer Science, ll, 2597 (1973).
83 C.E. Locke and D.R. Paul, "Graft Copolymer Modification of Polyethylene-Polystryene Blends. II. Properties of Modified Blends", dagpnal of Aeolied Polymer Science, jl, 2791 (1973).
- 84. B. Linn Draper, Jr., M.J. Voltin, Jr., J.L. MacDonald, C.T.
Rombough, L.D. Hansborough, S.G. Barbee, and J.H. Vanston, Jr.,
"A University's Involvement in Municipal Decision-Making on Nuclear Power", Trans. Aner. Nucl. Soc., (1973).
- 85. E. Linn Draper, Jr., J.L. MacDonald, and M.J. Voltin, Jr.,
"Nuclear vs. Coal: An Economic Comparison of Power Plant i Economics in Texas", Trans. Amer. Nucl. Soc., (1973).
- 86. R.E. Henry, "Forensic Applications of Neutron Activation Analysis", presented at the Combined Meeting of the Texas Association for Radiation Research and South Central Photobiology Group, San Marcos, Texas, November lo"' .
- 87. G.D. Atkinson, Jr. , " Appl:lcations of .. : tron Activation Analysis to the Life Sciences", prosented at the Combined Meeting of the Texas Association for Radiation Research and South Central j Photobiology Group, San Mt.rcos, Texas, Tovember 1973
- 88. E, Linn Draper, Jr. and J.R. Deen, "Measurement of Fission Product Yields from Thorium-232 in Californium-252 Fission Neutron Spectrum", Trans. Amer. Nucl. Soc., J2. 531 (1973).
- 89. E. Linn Draper, Jr., M. Etzion, S.P. Nichols, and W.G. Davey, "Neutron Fermi Age in Grap.3ite from Fission a.nd Fusion Sources to Indium Resonance", CONF 740402, USAEC, April 1974
- 90. E. Linn Draper, Jr. and T.A. Parish, "Neutronic and Photonic Analyses of Fusion Reactor Blankets Contaf.ning Natural Uranium",
CONF-740402, USAEC, April 7974.
- 91. G.D. Atkinson, Jr. , B.D. Adams, and S.J. Gage, " A Programmable and Automated System for Gamma and X-Ray Analysis", Proc. TREE 1571 Nuclear Science Symoosium, San Francisco, California, 1973
~
- 92. G.D. Atkinson, Jr. and R.E. Henry, "Neutron Activation Analysis:
Environmental and Biolgical Applications", presented at the Sixth Annual Meeting of the Texas Association for Radiation Research, San Marcos, Texas, 1973 53
s 93 M. Etzion, R.G. Spangler, and E. Linn Draper, Jr., "Multiple Foil Activation Measurement of the Californium-252 Fission-Neutron
(' Spectrum, Trans. Amer. Nucl. Soc., (October 1974).
. 94. A.H. Pradzynski, "Determination of Selenium in Water on the ppb level" presented at the Texas Association of Radiation Research, Dallas, Texas, November 1974.
- 95. J.R. Deen and E. Linn Draper, Jr., "Measurement of the Fission Product Yields and the Energy Integral 'r'ission Cross Section of Thorium-232 in a Californium 252 Fission-Neutron Spectrum",
Nuclear Technolocv, 25, 416 (1975).
- 96. E. Linn Draper, Jr., T.A. Parish, and M. Etzion, "Utilization of a Small Accelerator for Fusion Reactor Blanket Design", Proc. of the Third Small Accelerator Conference, USAEC, CONF-741021, 1974.
- 97. R.G. Spangler, E. Linn Draper, Jr., and T.A. Parish, "14 MeV Cross Section Measurements of Threshold Reactions for Seven s
Metals", Trans. Amer. Nucl. Soc. , 22, 818 (November 1975).
- 98. W.R. Smith, Jr. and E. Linn Draper, Jr. , "Measured and Calculated Fast Neutron Spectra in a Graphite Medium", Trans. Amer. Nucl.
Eng., 22, 800 (November 1975).
- 99. J.W. Davidson and E. Linn Draper, Jr., "Costs for Partitioning Strategies Involved in High-Level Nuclear Waste Mar.agoment",
Trans. Amr,. Nucl. Soc., 22, 348 (November 1975).
100. M.J. Voltin, Jr. and E. Linn Draper, Jr. , "Sensitivity of Total Fuel Cycle Cost to Variations in Enrichment Tails Assay Strategies", Trans. Amer. Nucl. Soc., 22, 322 (November 1975).
101. T.A. Parish, J.W. Davidson, and E. Linn Draper, Jr.,
"Transmutation of Fission Products in Fusion Reactor Blankets",
Trans. Amer. Nucl. Soc., 22, (November 1975).
102. T.A. Parish, J.W. Davidson, and E. Linn Draper, Jr., "The Effects of the D-T Fusion Neutron Energy Spectrum on High Energy Reaction Rates", submitted to the Sixth Symposium on Engineering Problems of Fusion Research, San Diego, California, November 1975.
103 A.H. Pradzynski, R.E. Henry, and J.L.S. Stewart, "Determination of Selenium in Water on the ppb Level by Coprecipitation and Energy Dispersive X-Ray Spectrometry", Radiochem. Radioanal.
. Letters, 2J15, 277 (1975).
104. B.E. Bulla, E. Linn Draper, Jr., R.E. Henry, M.J. Voltin, Jr., et al, Texas Nuclear Power Policies! A Study of Alternatives. Volume II: Methodolorv. The University of Texas at Austin Centec for Energy Studies, Policy Alternative Study No. 1 (1975).
i 54
l I
I
)
105. A.H. Pradzynski, R.E. Henry, and J.L.S. Stewart "Determination of Transition Metals by Radioisotope-Excited Energy Dispersive X-Ray Spectrometry", Trans. Amer. Nucl. Soc., 2113, 34 (1975).
. 106. A.H. Pradzynski, R.E. Henry, and J.L.S. Stewart, "Non-destructivo Determination of Toxic Elements in Toys", Proc. of 10th Symnosium on Nondestructive Elements, San Antonio, Texas, April 1975.
107. R.E. Henry, "Determination of ppb Levels of Selected Elements in Natural Water Using Radioisotope-bxcited Energy Dispersive X-Ray Fluorescence Analysis", presented at the Eighth Annual Meeting of the Texas Association for Radiation Research, Austin, Texas, October 1975.
108. T.A. Parish, J.W. Davidson, and E. Linn Draper, Jr., "The Minimization of the Hazard Resulting from Transmutation of Fission Products", Transactions of the American Nuclear Society, 23, 59 (June 1976).
109. T.A. Parish, "Fusion-Fission Hybrid Studies at The Univers_,y of Texas", presented at the U.S.-U.S.S.R. Symposium on Fusion-Fission Reactors, Lawrence Livermore Laboratories, July 1976.
110. T.A. Parish, J.W. Davidson, and E. Linn Draper, Jr., "Neutronic Performance of Graphite Fusion Reactor Blankets Containing Sr90 and I129", presented at the Second ANS Topical Meeting on the Technology of Controlled Thermonuclear Fusion, Richland, Washington, September 1976.
111. T.A. Parish, J.W. Davidson, r.nd J.B. Cornwell, "The Effectiveness of a Sr90 Fusion Reactor Transmutation Waste Management Program",
Transactions of the American Nuclear Society, 21, November 1976.
112. A.H. Pradzynski and J.R. Rhodes, "Development of Synthetic Star.dard Samples for Trace Analysis of Air Particulates", ASTH i Special Technical Publication 5SA, 320 (1976). '
l 113 A.H. Pradznyski, R.E. Henry, and J.S. Stewart, "Determination of ;
ppb Concentrations of Transition Metals by Radioisotope-Excited l Energy-Dispersive X-Ray Spectrometry, Journal of Radiennalytical '
Chemistry, 32, 219 (1976).
114. A.H. Pradzynski, R.E. Henry, and E.L. Draper, Jr., "Determination of ppb Concentrations of Uranium, Thorium and Molybdenum in Water l using APDC Preconcentration and Radioisotope Excited X-Ray j Emission Spectrometry", Proceedines of ERDA Symoosium on Y- and Onamn-Ray Sources and Aeolications, Ann Arbor, Michigan, May 1976.
115. A.H. Pradzynski, R.E. Henry, and E.L. Drapor, Jr., "Determination of Trace Elements of Hydrogeochemical Prospecting by APDC-Coprecipitation and X-Ray Spectrometry", Invited Paper at The International Conference on World Nuclear Energy a Statue Report. Transactions of f mer. Nuclear Soc!atg, 21, 119 (1976).
55
116. R.R. Gay, G.F. Brockett, and R.T. Johnson, "Two-Phase Flow Heasurement Techniques for Nuclear Safety Research", Two-Phase Flow and Heat Transfer Symposium Workshop, Miami Beach, Florida, 1976.
117 C.W. Savery and R.R. Gay, "Effect of Entrained Droplet Phase Upon Predicted Compartmental Pressures in Nuclear Containments",
Two-Phase Flow and Heat Transfer Symposium-Workshop, Miami Beach, l Florida, 1976.
118. Rodney R. Gay, "Reactor Hydrodynamics During the Reflood Phase of Loss-of-Coolant Accident", Nuclear Technology, 3412, 229 (December 1977).
l 119 D.E. Klein, S.R. Bull, and J.B. Hiles, "Flow Visualization Around --
GCFR Fuel Rod Roughness Elements", Trann. Amer. Nucl. Soc., 23, l (June 1978). j i
120. D.E. Klein, S.R. Bull, and J.B. Hiles, "Pressure Drop for GCFR l Fuel Rod Roughness Elements", Trans. Amer. Nuol. Soc., 3D, j (November 1978). j 121. E.H.B. Sorensen, R.E. Henry, and R. Ramirez-Mitchell, "Time )
. Dependent Localization of Arsenic in Subcellular Hepatocyte !
Fractions", J. of Patholory and Toricolory, 221, 1161 (1979).
122. E.H.B. Sorensen, R.E. Henry, and R. Ramirez-Mitchell, "Arsenic Accumulation, Tissue Distribution, Cytotoxity in Teleosts ;
Following Indirect Aqueous Exposure", Bulletin of Environmental l Contamination and Toxicolorv, 21, 162 (1979). j 123 J.W. Davidson and T. A. Parish, "Fission Product Toxicity Reduction via Transmut,ation Using D-T Fusion Neutrons", presented ;
at the Eighth Symposium on Engineering Problems of Fusion l Research, San Francisco, California, November 1979 124. J.W. Davidson and T.A. Parish, "An Evaluation of the Requirements and Performance of a Transmutation Waste Management System, I.cn Amer. Nucl. Soc. , 33, (November 1979).
~
125. S.A. Hodge, J.P. Sanders, and D.E. Klein, "Deterndnation of Friction Factors and Heat Transfer Coefficients f or Flow Past Artificially Roughened Surfaces", Oak Ridge National Laboratory Report, ORNL-5599, November 1979.
. 126. D.E. Klein, "Nuclear Problems and Prospects", National Energy Policy Issues, Council on Energy Resources, The University of Texas at Austin, !!ay 1979 127 D.E. Klein, H.E. Woodson, and J.W. Davidson, "Conmercial Nuclear Power 09neraticn", Council on Energy Resources, the University of Texas at Austin, June 1979.
56
128. f.F.B. Sorensen, R.R. Mitchell, A. Pradzynski, T. Bauer, and L. ;
Graham, "Morphometric Analyses of Arsenic-Induced '
Histopathological Changes in Parenchymal Hepatocytes", Tennessee ,
Academy of Science Annual Meeting, Nashville, TN, November 16-17, 'l
. 1979. l 129. A.H. Fradzynski, "Determination of V and Ba in Marine Sediments I and Biota", Internal Report, Nuclear Engineering Teaching l Laboratory, Mechanical Engineering (Nuclear Engineering) <
Department, Tha University of Texas at Austin, 1979 130. N.E. Hertel, B.W. Wehring, and J.J. Dorning, "Integral Test of ENDF/B-IV High-Energy Neutron Cross Section Data for Tungsten", !
Trans. Amer. Nucl. Soc., 32, 632 (1979).
131. R.H. Johnson, K.R. Koch, B.W. Wehring, and N.E. Hertel, "TDL Heasurements in an Iron Sphere Containing a DT Source", Trana.
Acer. Nucl. Soc., 32, 632 (1979).
1 132. B.W. Wehring, J.J. Dorning, N.E. Hertel, D.T. Ingersoll, and R.H.
Johnson, "Benchstrk Shieldin6 Problems Obtained from Integral Tests of Neutron Cross Sections", Trana. Amer. Nucl. Soc., 33, 666 (1979).
133 N.E. Hertel, R.H. Johnson, J.J. Dorning, and B.W. Wehring, l "Mearsurements and Analyses of Neutron Transport Through Iron",
- Proc. Conf. Nuclear Cross Sections and Technolorv, Knoxville, TN, October 22-26, 1979, NBS Special Publication #594, pp. 568-571.
134. N.E. Hertel and 3.W. Wehring, "Absolute Monitoring of DD and DT Neutron Fluences Using the AssociatedParticle Technique", Engli Ina.L . Meth. , .122, 501 (1980).
135. S. A. Hodge, J.P. Sanders, and D.E. Klein, "Slope and Intercept of the Dimensionless Velocity Profiles for Artificially Roughened Surfaces", Int. J. Heat Mass Transfer, 23, 135 (February 1980).
136. N.E. Hertel, J.B. Smathers, and R.G. Graves, "Gamma-Ray Spectra Measured in a Tissue-Equivalent Medium Irradiated with Neutron Radiotherapy Sources", Trann. Amer. Nucl. Soc., 25, 457 (1980).
137. N.E. Hertel, W.E. Murphie, and R.J. Calhoun, "Measurements of Neutron and Gamma-Ray Spectra in a Phantom Irradiated with 14-MeV Neutrons", presented at the Health Physics Society Annual Meeting, Louisville, Kf, June 21-26, 1981.
138. D.E. Klein, S.R. Bull, and J.B. Miles, "Pressure Drop Measurements and Flow Visualization Surrounding Roughness
. Elements", Jcurnal of Enerry, 313, 112 (1980).
139. D.E. Klein, "ANS Student Involvement in Public Inforaation - The University of Texas at Austin", Invited Paper, Trans. Amer. Nucl.
322., lh (1980).
57
140. R.B. Pope, H.R. Yoshimura, J.E. Hamann, and D.E. Klein, " An Assessment of Accident Thermal Testing and Analysis Procedures for Radioactive Materials Shipping Package", ASME 80-HT-38, April 1980.
141. J.E. Hamann, D.E. Klein, R.B. Pope, and H.R. Yoshimura, "Modelling of Pool Fire Environments Using Experimental Results of a Two-Hour Test of a Railcar/ Cask System", Paper #147, PATRAM-80, West Berlin, FRO., November 1980.
142. M.A. Ross and D.E. Klein, "Synthetic Fuel Production Utilizing
' Texas Lignite and a VHTR for Process Heat", Trans. Amer. Nuci.
Ess., 25, (1980).
143 J.W. Pavidson and D.E. Klein (co-editors), Proc. of the International Conference on Nuclear Vaste Transmutation, The University of Texas at Austin Press, March 1981.
144. M.A. Ross and D.E. Klein, "Synthetic Fuel Production Using Texas Lignite and a VHTR for Process Heat", _ Nuclear Te 3hnology, 5f13, (March 1982).
145. T.L. Sanders and D.E. Klein, "A Modified Numerical Scheme for
- GCFR Flow Transient Analysis", Trans. Amer. Nuci. Soc., 33, (November 1981).
146. M.A. Ross and D.E. Klein, "Synthetic Fuel Production Using Texas Lignite and a Very High Temperature Gas Cooled Reactor for Process Heat and Electrical Power Generation", The University of Texas at Austin Center for Energy Studies Research Report,13, May 1981.
147 M.M. Razzaque, J.R. Howell, and D.E. Klein, "Finite Element Solution of Heat Transfer for Gas Flow Through a Tube", IAA Journal 2012, July 1982.
148. S. Yang, J.R. Howell, and D.E. Klein, "Radiative Heat Transfer Through a Randomly Packed Bed of Spheres by the Monte Carlo Method", AIAA/ASME 3rd Joint Thermophysics, Fluids, Plasma & Heat Transfer Conference, ASME 82-HT-5, St. Louis, Missouri, June 1982.
149. J. Andersen and D.E. Klein, et al., "Peer Review of the Preliminary Design and Program Interfaces for the Iransuranio Waste Eggkage Iransporter (TRUPACT)", Sandia Report, SAND 81-2405, June 1982.
150. T.L. Sanders and D.E. Klein, "Transient Thercal-Hydraulic
. Analysis Using a Hodified Version of COERA-IV", 7th International Heat Transfer Conference, Munich, Germacy 82-IHTC-104, September 1982.
58
151. S. Yang, J.R. Howell, and D.E. Klein, "Monte Carlo Simulation of Thermal Conduction Through a Randomly Packed Bed of Spheres", 7th International Heat Transfer Conference, Munich, Germany, 82-IHTC-91, September 1982.
152. T.L. Sanders and D.E. Klein, "Comparison Analysis of Severe Flow Blockages for Computational Efficiency Using COBRA", Proc. from Gas-cooled Reactors Today conferenet, British Nuclear Energy Society, London, England, September 1982.
153 H.H. Razzaque, J.R. Howell, and D.E. Klein, "Finite Element Solution of Radiative Heat Transfer in a Two-Dimensional Rectangular Enclosure with Gray Participating Media",
82-WA/HT-51, ASME Annual Meeting, Phoenix, Arizona, November 1982.
154. J.B. Scathers, N.E. Hertel, and R.G. Graves, "In Phantom Photon Spectra Measurements for High-Energy Neutron Therapy Sources",
Proc. from the Fourth Symoosium on Neutron DosimetrvrBaam Dosimetry, Neuherberg/Hunich, Germany, June 1981.
155. N.E. Hertel, B.W. Wehring, and J.J. Dorning, "Heasurements and
. Analyses of High-Energy Neutron Transport Through Tungsten",
accepted for publication (subject to revision) in Nucl. Sci, and Engn., November 1981.
156. Y. Kunimoto, J.W. Davidson, and N.E. Hertel, "A Core Inventory l Model for Fuel Trajectory Analysis in Fusion-Fission Symbiotic Systems", Trans. Amer. Nucl. Soc., 31, 1978 (June 1982). ,
l 157 N.E. Hertel and W.E. Murphie, "The Use of Neutron and Gamme-Ray NE-213 Spectral Measurements and Calculations to obtain :
Dosimetric Information for DT Neutrons", Medical Physics, 10:66, I (1983).
158. R. Laucius, J.W. Davidson, and N.E. Hertel, "Calculation of the Differential Efficiencies of Organic Sointillators to Neutrons Above 10 MeV", Trana. Amer. Nucl. Soc. , 33, 625 (November 1982).
159 J.W. Davidson and N.E. Hertel, "Bonner Ball Detection Responses for Neutrons from Thermal Energies to 17 3 HeV", Health Physics Society Annual Meeting, Baltimore, Maryland, 1983 160. N.E. Hertel, J.W. Davidson, and R.H. Laucius, "NE-213 Response
. Hatrix for Neutron Spectrometry Up to 50 HeV", Health Physics Society Annual Meeting, Baltimore, Maryland, 1983 161. N.E. Hertel, J.W. Davidson, and .7.H. Laucius, "An NE-213 Response Matrix to 50 HeV", Trann. Amer. Nucl. Soc., 35, 607 (1983).
59
162. J.W. Davidson and N.E. Hertel, "An Equal Probability Neutron Detection System Using Bonner Spheres", Trans. Amer. Nucl. Soc.,
A5, 609 (1983).
. 163 H.H. Razzaque, J.R. Howell, and D.E. Klein, "Coupled Radiative and Conductive Heat Transfer in a Two Dimensional Rectangular Enclosure with Gray Participating Media Using Finite Elements",
ASME/JSME Thermal Engineering Joint Conference, ASHE-H-35, Honolulu, Hawaii, Marc 3 1983 164. S. Yang, J.R. Howell, and D.E. Klein, "Radiative Heat Transfer Through a Randomly Pacl:ed Bed of Spheres by the Monte Carlo Method", Journal of Heat Transfer, 105:2, 325 (Hay 1983).
165. H.H. Razzaque, J.R. Howell, and D.E. Klein, "Finite Element Solution of Radiative Heat Transfer in a Two Dimensional Rectangular Enclosure with Gray Participating Media", (accepted by the Journal of Heat Transfer).
166. H.H. Razzaque, J.R. Howell, and D.E. Klein, "Coupled Radiative and Conductive Heat Transfer in a Two Dimensional Rectangular Enclosure with Gray Participating Media Using Finite Elements",
Journal of Heat Transfer, JDS, 613 (1984).
167. E.M.B. Sorensen, C.W. Harlan, M.D., T.L. Bauer, and A.
Pradzynski, "Hepatocyte Changes Following Selenium Accumulation in a Freshwater Teleost", The Amer. Journal of Forensic Medicine and Patholony, 313, 8 (1982).
168. E.H.B. Sorensen and T.L. Bauer, "A Correlation Between Selenium Accumulation in Sunfish and Changes in Condition Factor and Organ Weight", Evironmental Pollution Series A, Ala3, 357 (1984).
169. E.H.B. Sorensen, T.L. Bauer, J.S. Bell, and C.U. Harlan, "Selenium Accumulation and Cytotoxicity in Teleosts Following Chronic, Environmental Exposure", Bulletin of Environmental contani nation and Toricolecy, 22, 699 (1982).
170. E.H.B. Sorensen and T.L. Bauer, "Selenium Induced Hematological Dyscrasia in Teleosts", Archives Environ. Contam. and Toxicology, j 12, 135 (1983).
171. E.M.B. Sorensen, P.M. Cumbie, T.L. Bauer, J.S. Bell, and C.W.
Harlan, "Histopathological, Hematological, Condition Factor and Organ Weight Changes Associated with Selenium Accumulation in
. Fish from Belews Lake, North Carolina", Archives Environ. Contam.
and Torinnlagr 13,153 (1984).
172. E.H.B. Sorensen, R.R. Mitchell, A. Pradzynski, T.L. Bauer, and L.
Graham, "Sterological Analyses of Hepat ocyte Changes Parallel Arsenic Accumulation in the Livers of Green Sunfish", (accepted by The Journal of Environmental Patholory. Toxicolorv and Oncolorv).
60
173 N.E. Hertel and J.W. Davidson, "The Effect of Cadmium Covers on Bonner Sphere Responses", to appear in the Proc. of the Personnel Radiation Dosimetry Svcoosium, Knoxville, Tennessee, October 1984.
174. N.E. Hertel and J.W. Davidson, "The Response of Bonner Spheres from Thermal En<srgies to 17 3 MeV", (accepted for publication Nuclear Instruments and Methods, (February 1985).
175. A. Patterson-Hine, J.W. Davidson, and D.E. Klein, "Characterization of Product Buildup in Continuously Processed Molten Salt Fusion Breeder Blankets", Trans. Amer. Nucl. Soc.,
15, (1983).
176. A. Patterson-Hine, J.W. Davidson, and D.E. Klein, "Contributions to the Thermal Power of Continuously Processed TMHR Holten Salt Blnnkets", 10th Symposium on Funion Engineering, Philadelphia, Pennsylvanie, December 5-9, 1983 177. G.P. Polansky, J.P. Lamb, and D.E. Klein, "A Finite Element Analysis of Incompressible Laminar and Turbulent Flow with Heat Transfer", presented to the 5th International Symposium on Finite Elements and Flow Problems, The University of Texas at Austin,
. Auntin, Texas, January 23-26, 1984.
178. H. Ally, D.E. Klein, and T.L. Bauer, "Preconcentration Methods of Trace Elements in Water for EDXRF and INAA", 5th International i Conference on Nuclear Methods in Environmental and Energy Research, Mayaguez, Puerto Rico, April 2-6, 1984.
l 179. D.E. Klein and W.H. Hiller, "Student ANS Branch Involvement in '
Public Information", Invited Paper, Trans. Amer. Nucl. Soc., June 1984.
180. F.Y. Iskander, D.E. Klein, and T.L. Bauer, "Toxic and Other Elements in American Cigarette Tobacco Compared with International Brands", 17th Annual Meeting of Texas Association for Radiation Research, Denton, Texas, November 1984.
181. F.Y. Iskander and R.H. Filby, "Formation of Anatase from Ti(IV)-pre-asphaltene Complexes under Coal Liquefaction Conditions", Euni, 63, 280 (1984).
182. F.Y. Iskander and R.H. Filby, "Speciation of Titanium in Solvent Refined Coal Using SESC-INAA", Proc. of American Nuclear Seelety
, Meetine, Fifth International Conference, Hayaguez, Puerto Rico, April 2-6, 1984.
. 183 T.L. Sanders, D.E. Klein, and M.E. Crawford, "A Liquid Metal Facility for the Analysis of Phenomena Related to the Magnetohydrodynamics of Fusion Related Systems", Sixth Topical Meeting on the Technology of Fusion Energy, San Francisco, California, March 1985.
{ 61
i l
184. T.L. Sanders, D.E. Klein and H.E. Crawford, "A Liquid Metal Facility for the Analysis of HHD Effects in Fusion-Related Systems", Fusion Technolor.v. fil, (1985).
185. A. Patterson-Hine, J.W. Davidson, D.E. Klein, and J.D. Lee,
' Characterization of the Effects of Continuous Salt Processing on the Performance of Holten Salt Fusion Breeder Blankets", accepted .
to J. of Fusion Energy. l 186. F.Y. Iskander, "Neutron Activation Analysis of an Egyptian Cigarette and its Ash", J. Radionnal. Nucl. Chem., SS, 511 (1985).
187. F.Y. Iskander, "Egyptian and Foreign Cigarettes.1. Determination l of Trace Elements in Cigarette Filter Before and After Smoking",
J. Radionnal . Nucl . Chem. , SJ., 191 (19b5) .
188. F.Y. Iskander, "Cigarette Ash as a Possible Source of Environmental Contamination", Environ. Pollut. (Series B), 11, (1986).
189 F.Y. Iskander, "Egyptian and Foreign Cigarettes. 2. Determination of Trace Elements in Tobacco, Ash, and Wrapping Paper", d.
. Radionnal. Nucl. Chem., SI, 107 (1986).
190. F.Y. Iskander, T.L. Bauer, and D.E. Klein, "Determination of 28 5 Elements in American Cigarette Tobacco by Neutron Activation Analysis", Analyst, JJ1, 107 (1986).
191. F.Y. Iskander, D.E. Klein and T.L. Bauer, "Determination of Trace Impurities in Aspirin Tablets by Neutron Activation Analysis", Ja.
Radionnal. Nucl. Chem., SI, 353 (1986).
192. H.H. Morad, F.Y. Iskander, L.W. Rooney, and C.F. Earp, "Physico-chemical Properties of Alkali-cooked Corn Using Traditional and Presoaking Procedures", Cereal Chem., 63(3)
(1986) 255.
193 F.Y. Iskander and M.H. Horad, "Neutron Activation Analysis of Texas Hard Red Winter Wheat and its Hilling Fractions", American Association of Cereal Chemistry, 70th Heeting, Orlando, Florida, paper 151, 1985.
194. F.Y. Iskander, "Neutron Activation Analysis for Assessing the Concentration of Trace Elements in Laboratory Detergents", Ja.
Aeol. Radiat. Isotooes, JJL (5) (1986) 435.
195. F.Y. Iskander, T.L. Bauer, and D.E. Klein, "Sone Considerations
. of Elements Content of cigarette Wrapping Paper", TAPPI, SS (5)
(1986) 134.
62
l 196. F.Y. Iskander, M.H. Morad, D.E. Klein, and T.L. Bauer, (1987).
"Protein, In-vitro Protein Digestibility and Minerals Content of Hard and Soft Red Wheat Varieties", Cereal Chem. 64:285.
. 197. F.Y. Is:cander, (1987). Neutron activation analysis for measurj ng the unsaturation in edible oils. J. Radionnal. Nucl. Chem.
Letters 118(2):149 198. F.Y. Isl:ander and M.H. Morad, "Minerals and Protein Contents in Texas Hard Red Winter Wheat and Its Hilling Fractions", E22d Science. 51 (1986) 1522.
199 F.Y. Iskander, D.E. Klein, T.L. Bauer, and M.H. Morad, "Protein and Nutritional Elements Content in Texas Wheat", 18th Annual Meeting of Texas Association for Radiation Research, San Antonio, Texas, November 1985.
200. F.Y. Iskander and M.M. Horad, "Multielement Determination in Wheat and Bran", Radinochem. Radicanal. Letters, 125 (3) (1986) 151.
201. 0.I. Asubiojo, J.A. Adepetu, and F.Y. Iskander, "Determination of the Chemical Composition of Nigerian Harmattan Dust by Instrumental Neutron Activation Analysis", The 7th International Conference, Modern Trends in Activation Analysis, Copenhagan, Denmark, 1986.
6 202. F.Y. Iskander, (1987). Haturation stage and mineral content in soybeans. J. Food Chem. 24:29, 203 T.R. Ajayi, F.Y. Iskander, 0.I. Asubiojo, D.E. Klein, Geochemistry of upper cretaceous classic sediments of Ifon area, S. W. Nigeria. Accepted, Nigerian Journal of Mining and Geology.
204. K.R. Davis, F.Y. Iskander, H. Ashour, H.F. Hassan, Aluminum content in Egyptian breads. Submitted to Cereal Chem.
205. F.Y. Iskander (1986). Use of NAA to determine nutritive elements in immature and mature soybeans. Trans. Am. Nucl. Soc., 53:170 206. J.A. Adeptu, 0.I. Asubiojo, F.Y. Iskander, and T.L. Bauer, (1938). Elemental composition of Nigerian harcattan dust for ecological monitoring using instrumental neutron activation analysis. da_Jadiennal. Nucl. Chem. 121(1):141.
63
l 207 R.D. Manteufel, D.E. Klein, and H.R. Yoshimura, "Benchnarking of Q/TRAN Thermal Analysis Computer Code", PATRAM-86, 1 IAEA-SH-286/95P, pp. 465-474.
. 208. R.D. Manteufel, D.E. Klein, and H.R. Yoshimura, "Comparison Study of PATRAN and Q/TRAN for Thermal Analysis of Shipping l Containers", 1986 PATRAM User's Conference.
209 G.F. Polansky, J.P. Lamb and D.E. Klein, "Finite Element j Simulation of Recirculating Flows with Heat Transfer", I Communication in Annlied Nummerical Methods, Vol 3 No. 1, P.
17-22, Jan-Feb, 1987 210. F.Y. Iskander, "Determination of iodine value of some vegetable )
oils by Br/INAA. In preparation for J. Am. 011 Chem Soc. j 211. 0.I. Asubiojo, F.Y. Iskander, "A Trace element study of concercial infant milk and cereal formulas." Submitted to J6.
Radiennal . Nucl . Chem.
212. K.R. Davis, P.Y. Iskander, H. Ashour, H.F. Hassan, "Aluminum content in E(;yptian breads." Submitted to Creal. Cham. j l
213 F.Y. Iskander and A. Askar, (1987). "Hinor and Trace elements in two faba bean meals." Ernahrune-Nutrition 11 756.
214. D.E. Klein, "Nuclear Engineering Teaching Laboratory at The University of Texas at Austin", invited paper, Trana Am Nuci.
sas , 55, November ,1987 215. R.D. Manteufel, D.E. Klein and H.R. Yoshimura, "An Evaluation of a Translator for Finite Element Data to Resistor / Capacitor Data
! for the Heat Diffusion Equation", 1987 ASME Annual Meeting, HTD-Vol. 88, pp 67-72.
216. J.E. Hamann, D.E. Klein and H.R. Yoshimura, "Thermal Analysis of a Spent-Fuel Railcar Shipping Cask in an Engulfing Fire", Sandia National Laboratories (submitted 1987).
4 64
.e O '> .. COLLEGE OF ENGINEERING
= P4^ 5' THE UNIVERSITY OF TEXAS AT AUSTIN
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4; (y- Dep.trimentol AiechanicalEngineering NuclearEngineeringProgram Austin, Texas 78712 (312)471-31%
March 29, 1988 Director of Inspection and Enforcement U.S. Nuclear Regulatory Cenniasion Washington, DC 20555
Dear Sir:
Enclosed are twelve (12) copies of the calendar year 1987 Annual Report. These are being submitted according to 10 CFR Section 50.59.
Sincerely, f{ z~ v< :). (Snw Dr. Thomas L. Bauer Assistant Director Nuclear Engineering Teaching Laboratory TLB:dlw Enclosure cc: Dr. Dale Klein l
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