ML20070R730
| ML20070R730 | |
| Person / Time | |
|---|---|
| Site: | 05000192 |
| Issue date: | 12/31/1990 |
| From: | Bauer T TEXAS, UNIV. OF, AUSTIN, TX |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9104010377 | |
| Download: ML20070R730 (75) | |
Text
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($12)471 5 787 'l% X ($ 12)471-o 589 April 1, 1991 USNRC Document Control Desk Washington, D.C. 20555
Dear Sir:
Enclosed is one copy of the calendar year 1990 Annual Report. These are being submitted according to 10 Cl"R Section 50.59.
Sincerely, Tfs.cm 2. b*
Dr. Thomas L. Bauer Assistant Director Nuclear Engineering Teaching Laboratory TLB:mm Enclosure 9104010377 901231 PDR ADOCK 05000192 R PDR ((l[7 IIi
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NUCLEAR REACTOR L ABO R ATORY I TECHNICAL REPORT
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l THE UNIVERSITY OF TEXAS l COLLEGE OF ENGINEERING DEPARTMENT OF MECHANICAL ENGINEERING j 4
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1990 ANNUAL REPOPT of The University of Texas at Austin Nuclear Engineering Teaching Laboratory at Taylor Hell Room-104
- January 1, 1990 December 31, 1990 4 Bernard W. Wehring, Director 512/471 5787 T. L. Bauer, Assistant _ Director / Reactor Supervisor ,
512/471 5787
. March 1991 Balcones Research Center-
- 3 ye v v
. i 1990 I
I i
TABLE OF CONTENTS
! List of Tables................................... 3 i . List of Flgurca.................................. 4 i
l 1. Introduction..................................... 5 II, Laboratory Administration....................... 10 l
A. Organization l B. Personnel C. Committees D. College Report III. Laboratory Development.......................... 15 A. Organization B. Nuclear Engineering Teaching Laboratory C. Nuclear Reactor Laboratory D. Nuclear Radiation Laboratory E. Neutron Activation Analysis Laboratory IV. Facility Operations Summary..................... 19 l
A. Operating Experience B. Reactor Shutdowns C. Reactor Utilization D. Reactor Maintenance l
E. Facility Changes F. Area Radiation Surveys C. Radioactive Effluents and Waste V. Laboratory Inspections.......................... 32 A. NRC Inspections B. TDH Inspections VI. Public Service Activities....................... 33 VII Research Activities..............................34 VIII. Publications from the Nuclear Engineerin6 Teaching Program.................... ..... 41 A. Ph.D. Dissertations
. B. Masters Thesis C. Reports and Papers 2
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1990 List of Tables Table No. Page
- 1. Administration and Committees 12
- 2. Facility Personnel -13
- 3. University courses 18 4 Reactor Safety System 20
- 5. Safety System Events 20
- 6. Performance Data 21-
- 7. Annual Utilization Data 22
- 8. Summary of Personnel Radiation Exposures 27
- 9. Radiation Exposure Groups 27 o 10. Laboratory Radiation Levels 28
- 11. Laboratory contamination Levels 28
- 12. Environmental Surveys 29 l
- 13. Monthly Caseous Waste Discharge 30 14, Monthly Liquid Waste Discharge 31
- 15. Monthly Solid Waste Disposal 31 l
16 .- Research Fundin5- 35 G
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.i i i 1990 List of Figures Figure No. Page
- 1. Site Location of Nucicar Engineering Teaching Laboratory 8
- 2. Floor Plan of Nuclear Engineering Teaching Laboratory 9
- 3. Organization Chart of the Nucicar Engineering Teaching Laboratory 11
- 4. Annual Burnup versus Operatic' Year 24
- 5. Samples Irradiated versus Year 24 9
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t r 8 1990 J
- 1. ' INTRODUCTION r The Nuclear Engineerine, Teaching Laboratory (NETL) 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 DE.Ac07.ER03919-Amendment A015. The report covers the period from January 1,1990 to December 31, 1990. -t 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 octivities in one i of the original engineering buildings. Sullding space in Taylor i Hall has provided classroom, laboratory and office areas. By the 1 year 1985 the nuclear program was the only engineering program-still functional in.the building that has become the location of
- the College of Natural Sciences Department of Computer Science. L 4 Other university-organizations such as'the Computation Center are also in areas of the building.
Taylor Hall.
i Host NETL program laboratory activities were. at_ two i ,
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 tho' site of a TRICA_ Mark ~ l' reactor that has steady.
state and pulse modes. Power operation of the reactor was at 250 kilowatts steady state and approximately 250 megawatts-pulse. -At the time of initial' facility acceptance the power level was at 10
~
j,
- kilovacts. The Activation Analysis Laboratory prcvided gamma .
- spectro. copy systems for_ analysis-of neutron activation reactions, i These re.>etions are products of irradiation experiments in
- reactor experimen facilities. -Data acquisition and analysis:was done with high_ efficiency, high resolution detectors.: Intrinsic purity. -
j germanium Jetectors provide radiation detection.with-automatic j control anc acquisition mystems run by' microcomputers.1
?
'Other1.tETL program.-laburatory activities are now. functional at ' Building 159 of Lthe Bale.snes Research Center. - This_ facility _
? provides multipurpose; facility for several engineering'and science- .
} programs,. A Nve? car Radiation Laboratory provided-an experiment'.- l facility :for flu a and energy; measurements of neutro- from' fusion, i - fission, and other neutron-production reactions. -Three sources ..
available are the # ? ' reaction from a Cockcroft-Walton type- I
- accelerator, spontan3ou: fission reaction from'the: isotope
- californium a252-and the alpha neutron reaction from plutonium-
-beryllium, Activities of the laboratory include detection,
~
measurement and analysis.-
L r
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1 1990 NETL program equipment and materials provide support for different types of facility activities. Supplemental equipment and radioactive materials include a subcritical assembly, samma l
. irradiator, portable x ray unit and various isotopic radiation sources. Equipment, instrumentation systems and detection devices for monitoring, measurernent and calibration of ionizing radiation
- are in routine use or availabic 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.
Developmental goals of university and engineering programs have been the inajor cause of change to the NETL program.
Initiation of a project to move activities of the NETL program to the Balcones Research Center (BRC) began in October 1983 and should be completed in August 1991. The program move la in response to needs of the main carnpus for expar.slon 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 Decommissioning Plan (DDP, docket 50 192) for the Taylor llall f acility was submitted to the Nuclear Regulatory Comrnission (NRC) on May 3,1985. An order to authorize the activities that will lead to the license termination was issued on March 9, 1987. Project p lans indicate that the DDP activities will occur in the first quarter of 1991. The R 92 operating license was amended to a possession only license, Building 139 Balcones Research Center Project authorization to move NETL program activities to the i
Balcones Research Center (BRC) site was approved by The University of Texas System Board of Regents on October 13, 1983. A submittal for a construction permit and an operation license was made to the Nuclear Regulatory Commission on November 9, 1984 Subsequent to i a site visit on January 22 thru 24 a license amendment was -
requested on February 27. and responses to NRC questions were l prepared. The construction' permit was issued June 4, 1985, Preliminary architectural and engineering plans were approved by The University of Texas System Board of Regents on August 8, 1985. Final plans were approved on April 10, 1986 and the bid to a general contractor was awarded on December 4, 1986.
CIT Construction Inc. of Stafford, Texas, was specified as the l general contractor and start of construction was recorded on February 10, 1987. Facility completion was scheduled for 16 18
. months af ter start of construction, Project delays. by the general contractor led to removal of the contractor. Completion of the project has been the responsibility of the surety, Firemans Insurnnce Mapany. Acceptance-of the building for--occupancy-was on May 1, ,;989, with subsequent terraination of construction contract r,ctivities on January 31, 1990.
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1990 The Balcones Research Center facility provides laboratories for the TRICA reactor, a neutron generator, radiation measurement systems, preparation and processing of radioactive samples, and office space. Although the facility will move the present TRICA facility and other program activities into a single building at the Research Center, several improvemente to the reactor facility
. vill extend facility capabliity. These include above ground shield structure for access to horitcotal beam tuben, and an increano of power and pulse parameters. Plans are to utilize the present fuel and move some other components from the old to the new facility. A (ev components such as control tod drives have.
been subject to re.'ork procedures to assure appropriate functional operation. Many componento such as reactor structure, instrumentation, and control system vill be nes temponents.
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Floor Plan of Nuclear Engineering L Teaching _ Laboratory l.
9
1990 II. IABORATORY ADMINISTRATION
~
A. Organizatior
. The present organizational chart of the NETL program is presented it Fi 6ure 3, Budgeted NETL funding for the primary staff is previded for a Supervisor / Assistant Director, research associate, operator, secretary, and part time assistant. Budget support ia divided into full time positions for supervisor, reactor operator, research associate, and secretary. The balance of the budget supports a part time assistant, typically halftime, simh as a student. >
Additional funds now support a lull time health physicist-position. Other funds for the next several years are to be available fo' *ip to 2 additional positions ar.uociated with reactor experiment p/. grams.
B. Personnel Personnel associatei 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 summarized in Table I.
C. Standing Committees Two committees monitor the activities of the NETL programs, The Nuclear Reactor Committee functions through the College of Engineering and the Radiation Safety _ Committeo zfunctions 'through the Office of the Precident.
-1. ?!" clear Reactor Committee l The b aclear Reactor Committee convened to review the activities related co facility operation during each quarter of the calender year. Osmmittee meeting dates were-Jaauary 26, April 10, July 24, October 3t and December. 10, 1990. The committee composition is shown in-.able 2. Committee responsibilities are the reactor operation -ussociat ! facility activities and engl.ieer!.g pro 6 rams.
- 2. Radiation Safety iommittee The Radiation Safety Committee convened to review
, radiological safety practices at the university during each academic term. Committee meeting dates were April 11,1990 and Nove'ber 9, 1990. The committee composition is shown in Table 2.
Committee responsibilities are the activities of university research programs tb.c utilt.e radiation source materi Is.
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1990 i Office, President University of Texas at Austin Radiation
, Safe ty Counittee
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i Executive Vice President
, and Provost t l 1 .
I Dean College of Engineering ~~'
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I Nuclear I
l Reactor.
I Committee
- .I l' i Chairman ,
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t I i i Director i l_____. _ .. Nuclear Engineering .__ _ _ _ _ _ _ _I i Teaching Laboratory i I I 1 l l
l- Supervisor h
i Reactor Operations Responsibility ___
l Com.munica t ion - __
l Figure 3 I
. Organization Chart of the Nuclear Engineering l'eaching Laboratory t
11
1990
. Table 1 Administration and Committees Administration The University of Texas System Board of Regents Chairman Louis A. Beecherl Jr.
Vice Chairman Sam Barshop }
Vice Chairman Bill Roden Executive Secretary Arthur H. Dilly Member (1991) Member (1993) Member (1995)
J.S. Blanton Sam Barshop R.J. Cruikshank S.H. Ratliff L. A. Beecherl Jr. Tom Loeffler Bill Roden W. A. Moncrief Jr. H.E. Ramirez Chancellor Hans Mark The University of Texas at Austin President William H, Cunningham (app: 9/1/85)
Executive Vice President and Provost Gerhard J . Fonken
- (app: 9/1/85)
Dean of the College of Engineering Herbert H. Woodson (app: 9/1/87)
Chairman of Department of John R. Howell Mechanical EnBi neering (app: 9/1/87 8/31/90) nneth Diller L 9: 9/1/90)
Nuclear Reactor Committee Chairperson: H. L. Marcus (app: 9/. ')
Member: B. W. Wehring(app: 9/1/90)
Member: D. E. Klein_=(app: 9/1/77)-
Member: J. C. Reis (app:-9/1/90)
Member: R.S. Charbeneau (app: 9/1/89)
Member: G.B. Hallack (app: _9/1/89 8/31/90)
Member, student: J. McWhirter (app: 9/1/89) y Ex officio member:-T. L. Bauer (app: 6/1/78)
Ex officio member: H. W. Bryant (app: 11/1/73)
Ex officio-member: H. H. Woodson (app: 9/1/87)
Ex officio member: J. R. Howell (app: 9/1/87 8/31/90)
Ex officio member: K. R. Diller (app: 9/1/90)
Radiation Safety' Committee Chairperson: E. L. Sutton (app: 9/1/84)
Member: G. W. Hoffman (app: 9/1/84)
Member: D. E. Klein (app: 9/1/83)
Menber: S. A. Monti (app: 9/1/85)
< Member: L. O. Morgan (app: 4/1/75)
Member: B.W. Wehring (app:'9/1/89)
Member: B. Cor,k (app: 9/1/89)
Ex officio member: H. t!. Bryant (app: 11/1/73)
Ex officio member: W. H. Cunninghain -(app: 9/1/85)
V 12
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a 1990 1
Table 2
, Personnel Facility Personngl
- Staff ,
Director B.W. Wehring Assistant Director / Supervisor T.L. Bauer Manager of Analytical Services F.Y. Iskander Manager of Neutron Beam Projects V. On10 Manager of Reactor Operations h . 6. 'Arause Post Doctoral Follow T. Emoto Health Physicist R.C. Woodard Nuclear Technical Specialist I R, Manteufel Administrative Associate J.G. Rawlings Senior Office Assistant E._ Richmond Senior Office Assistant M. McGee I
Support Personnel Safety Personnel Safety Coordinator H.W. Bryant Radiation Safety Specialist L.W. Hamlin l
Researchers t
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College of Engineering T.L. Bauet Nuclear Reactor Leb, F.Y. Iskander Neutron Activation Lab. Research Associate l N.E. Hertel Nuclear Radiation Lab,- ' Assoc. Prof.
University Departments P.S. Schmidt Mech ' Engineering Assoc. Prof.
T.L. Bergman Mech. Engineering Assoca Prof.
D. Smith Geology Prof.
l D.S. Barker Coology. Prof.
l D.E. Klein Mech. Engineering Prof.
Students Graduate Assistants G. Miller H. Cepford J. Kim H.~ Vega'Carrillo l B. Hall C. Rios Martinez B. Nabelssi- J. McVhirter ,
Undergraduate Student Assistants R. Manteufel S. Bertrum McUne S. Midgett C. Lindemann- >
W. Rosella M. Razzoque 1
g 13 -
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1990 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
,rtions of the NETL program concerning the reactor and other radiation producing equipment. Harris Marcus, Reactor Committee Chairman, summarized the activities during this period :
There are two sets of minutes for this years quarterly meetings. Docket 50 192 deals with the ongoing operation in T' .or :lall and Docket 50 602 deals with the construction of the t-v facility at Balcones Research Center. The specific items of.
interest are the following:
The major effort in the program was associated with- the development of the new reactor facility at Balcones Research Center, as well as for decommissioning arrangements af the existing facility. The completion of the BRC NETL facility moved along more slowly than originally planned. A great deal of delay was associated with the difficulties of the building contractor.
The main task of the committee was a review of the procedural documents associated with operating the RRC NETL and meeting the license requirements. The NRC review of the facility has moved I along in an iterative manner. A series of inspections of the facility were made by NRC inspectors and the, requirements to obtain a license were systematically being met.
Note: Bids for the facility at the Balcones Research-Center were opened October 21, 1986 and award of'the general cortract cas approved December 4, 1986. -The University of Texas System Board of Regenta entered into a contract with CIT Construction Inc. of Stafford, Texas. Total project cost for the proposed facility was $5,452,560. An additional
$408,140 is being held in reserve for dismantling activities at the Taylor Hall facility. Authorized total cos*. is
$5,860,700, 4
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. I 1990 III. IABORATORY DFVELOPMENT A. Organization Dr. Bernard W. Wehring as the Director of the NETL Program, has been responsible for laboratory development. Dr. Thomas L.
Bauer continued as Reactor Supervisor / Assistant Director during-the past year.
The changes made in the facility staff during the 1990 calendar year were in several areas. Three managerial positions have been designated for Reactor Operations, Neutron Analytical Services and Neutra- Beam Projects. Two of the positions are held by present ceaff, with the third held by a new appointment.
The Nuclear Reactor Committee changed with the appointment of two different members J. Reis and K. Diller. Dr. H.H. Woodson continues as the Dean of'the College of Engineering. Dr. K.R.
Diller has succeeded J.R. Howell as chairman of the Department of Mechanical Engineering. Dale Klein continues as Associate Dean-for Research in the College of Engineering.
B. Nuclear Engineering Teaching Laboratory The Nuclear Engineering Teaching Laboratory is part of the l Nuclear Engineering Program at The University of Texas.
The Nuclear Engineering Teaching Laboratory's central feature is a Mark I TRICA thermal fission reactor. Originally licensed by the Atomic 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 TRICA reactor toJoperate at a steady state power level of 250 kw which increased experimental capabilities. Routinef operations of the reactor were terminated on April 30, 1988 in preparation to move f> ility .
operations. No reactor operation was performed during 1985 or 1990. Several key routine surveillances will continue tc be performed until fuel is moved.
L Other radiation producing devices'maintaine.o by the l Laboratory are a 750 curie Co-60 Irradiator, vertical nettron beam tube, subcritical assembly, industrial x-ray source, 14 ccV-neutron generator, and several-isotopic neutron sour' m.
~
Different types of radiation detectJon devices provide the capacity to monitor or analyze the various radiation sources, r . One of the functions of the nuclear reactor and itu-associated equipment has been to teach and demonstrate _the fundamentals of rnactor operationi Another function has been the demonstration of specific applications of nuclent technology, i
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. i 1990 Classes that routinely utilize the reactor facility and a few others that use the facility on an infrequent basis will resume normal schedules as facilities become available, Courses
. utilizing the reactor and associated facilities are listed in Table 3. Classes, organizations and groups have been provided tours or demonstratians of the reactor and its associated experimental facilities. No tours or class activities are presently being pursued at Taylor Hall.
Access to the Taylor Hall facilfty has been curtailed pending tre dismantling activities. Several activities of the program have been moved to the BRC site, although no fuel and only calibration sources are available at the BRC facility, The use, operation, regulation and inspection of the Nuclear Engineering Teaching laboratory is controlled by the United States Nuclear Regulatory Commission, the Nuclear Reactor Committee of ,
The University of Texas, the Director of the Nuclear Engineering j Teaching Laboratory, the Radiation Safety Committee and the. Texas 1 Department of Health Division of Radiation Control.
C, Nuclear Radiation Laboratory The Nuclear Radiation Laboratory is utilized by staff and students of the Nuclear Engineering Program at The University of Texas at Austin, A 14 MeV Texas Nuclear neutroa generator.is the main feature of the laboratory. Three californium-252 neutron sources are also availablo for use. The facility, with installed
~ shielding, provides an area where students and staff can perform experiments utilizing not only the high energy neutrons from the a neuttun generator but fission spectrum neutrons from Cf252. In '
addition to the neutrcn generator and the californium sources, othar smaller radioactive sources are also used within the corfines of the Nuclear Radiation Laboratory.
The laboratory was located in an area of the ens ineerins Science Building, Equipment for radiation measurements have been moved from the ENS site and the area released by survey for '
unrestricted use. Activities are now part of the BRC facility, Bldg. 159, room 1.102. All radiation sources for this room 1.102 laborarcry are subject to the u Jversity broad license for radioac tive materials and radiation producing equipment.
D. Neutron Activation Analysis Laboratory The Neutron Activation Analysis Laboratcry has provided nuclear analytical support for individual projects ranging from student project support for clasats to measurements for faculty
. research projects. Studert project support is in the areas of engineerin6, chemistry, physics, geology, biology,-zoology, and other areas. Research project suppor'c includes elemental measurements for environmental and investi6ative research proj ec ts . Scientific articles based upon the results of sponsored and non sponsored research by this laboratory have been published or accepted for publication in several journals and proceedings, g 16
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1990:-
I and have been presented =at conferences at the state, national and-international level, .
Radiation measurement systems;available include, gamma ray, spectroscopy with:three Hpoe detectors coupled'to a microcomputer ,
controlled acquisition and analysis system..Si(Li) detectc. a.
, muttichannel-analyzer for X ray measurements, alphe-bets i{
proportional counter, scintillation detectors, neutror. detectors l and associated electronic modules to accomplish several types of i atandard 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 ;
nuclear radiation' measurements._ This-laboratory is fully l J functional ~ at the BRC_' site, Bldg. 159,croom'3.112. Alliwe k-at_ !
the Taylor Hall site has been comple hd, i
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1990 Table 3 i i
. Courses Utilizing the Reactor and Associated Facilities Course Number Course Description Mechanical Ennineerine Department.
ME 361F Introductory Nuclear Laboratory - studies in radioactive decay, activation, detection and measurement.
ME 361C Reactor Operations studies in nuclear reactor paramotors, instrumentation ,
characteristics and regulation.
ME 377K Proj ects in Mechanical Engineering --
individual study and experiment projects for undergraduates, ME 389R Nuclear-Engineering Laboratory studies: "l for graduate students in nuclear' methods ;
in-measurement and analysis.
Special projects course for-nuclear.
ME S389R engineering laboratory studies as-a summer course for fereign students.
ME 397 Current Studies in Engineering-.special projects cource-for graduate study of selteted topics, s
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i990 l
IV. Facility Operations Summary A, Operating-Experience No reactor operations, pulse or steady state, were performed since April 31, 1988. No significant deviations from normal operating conditions were observed, Established operating procedures and other required procedures remained unchanged.
Routine reactor operation remained terminated throughout the calender year. No power operation was performed. Fuel remained in a storage configuration. Fuel is to be moved from the docket 50 192 facility to the docket 30 602 facility. Until the fuel is moved the fuel is to be stored in pool storage racks and the F-ring of the reactor pool. Estimates and measurements of the reactivity establish >the configuration to be a Keff < 0.8.
Amendment of the facility license has been made for possession only.
Licensed activities were performed by two persons with Genior Operator Permits, T.L. Bauer end M.G. Krause. These activities for the 50 602 facility. consisted of surveillance, fuel movements and administration. Operating activities were in support of reactor surveillance, nuclaar engineering, sample
- irradiations, research and education or demonstrations. No new
, experiments were proposed or approved. "The major experiment performed was neutron activacion to support various research activities. Irradiations were done at the Nuclear Science Center at Texas A&M University. Maintenance during the period consisted l primarily of routine equipment . repair and adjustments. Key surveillance activities continue on schedule.
l l B. Reactor Shutdowns l
Reactor shutdowns (scrams) occurring during the reporting period are summarized in Table 4, categorized according to the type of initiating 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 an operator error or an intentional action of the operator. Operator l
error scrams are the rers.c of judgement errors -or procedural L errors. Instrument and power failure scrams are protective l- actions that result from loss of safety. system function.
Intentional scrams are operator initiated scrams such as tests.
, Manual action scrams are classified either safety or intentional l as determined by the cause of:the manual scram action.
l ,
Inadvertent scrams are all unintentional shutdowns of the reactor j by the protective action of the safety system. Table' 5 comp r. :es -
l the number of inadvertent shutdowns during this reporting period l . to previous-reporting periods.
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1990 i
Table 4 Reactor Safety System *
(scrams)
Safety System 0 Operator Error 0 l
Instrument Error 0 Power Failure O Subtotal 0 Intentional 0 Total 0 ,
Table 5 Safety System Events
- _
(inadvertent) -
1971 13 1981 /
1972 6 1982 6' 1963 10. 1973 10 1983 6 i 1964 5 1974 4 1984 $
l 1965 1975 7 1985 2 1966 .. 1976 5 1986' 9 1967 3 1977- 9 1987 2 196b 11 1978 11 1988 l' 1969 15 1979~ 12 1989 0 1970 11 1980 7 1990 0-
,
- No reactor operation during the years of 19h9~ or 1990, 4
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1990 Table 6 Performance Data'1989 (4)-
, Reactor Operation Hours, Fuel Burn up and Irradiated Samples Cuarter Reactor- Total Burn up Samples Operation Fuel Irradiated-(hours) (kwhrs) (number):
First 0 0 0 Second 0 0 0 Third 0 0 0 Fourth 0 0 0 Total 0 0 0 Notes:
(1) Reactor operation hours record the console key on time or the time power.is applied to the rod control system, Thicd and Fourth greater operation time uttributed to fuel movement activities this reporting period.
(2) One full power hour is 250 kilowatt hours.
2 (3) Scmples that ere irradiated in the experimental facilities-ot the reactor such as the RSR, PNT er CT, (4) No reactor operation during the year e
i 1
21
1990 Table 7 Annual Utilization Data
, Xent Reactor Total Burn up Sampics Operation Puel Irradiated (hours) (kwhra) (number) 1967 154.5 846 265 1968 342.6 28168 -2449 1969 260.8 49985 1452 1970 222.0- 36477 1640 1971 262.5 53912 2990 1972 i'2.8 48389 1946 IS':
- 8.6 45794 1347 1974 ( 2.5 27641 778 1975 201.0 20450 363 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 1983 260.2 2402P 477
~
1984 -179.6 .:306 667 1985 139.9 18607 473 1986 183.1 18660 633 1987~ 293.9 43786 1394 1988 147.1 24257 $41 1989 23.9 0 0 1990 0 0- 0 Total 4893.7 630186- 20967' Note:
(1) Data for 1967 includes.all data recorded for previous operation at 10 kW from'.1963 1967.
(2) Operation power of 250 kilowatts .ias initiated in 1968.
(3) Ne operation after 1988.
4 I
22 , .
- --ae- , r v . -e + +e 4#+ev -4 ** e- "s e o we er
1990 C. Utilization Reactor utilization data for this reporting period h summarized in Table 6. A summary of reactor utilization since
, initial critieni!ty is shown in Table 7. Ser graphs comparing annual butnup and quantities of samples irra11ated since initial-criticality are shown in Figures 4 and 5. The 50-192 facility did not l'. radiate any samples during the years of 1989 or 1990.
D. Maintenance During this reporting period maintenance consisted primarily of rourtne repair and adjustment. Air particulate continuous air.
mr:it,. cad area radiation monitors remain in routine operation and sur<elilance.
Control rod drives have been removed for complete repairs and refurbishment. These drives are still installable in the docket 50-192 facility although the intention is to.transfe. them to the docket 50 602 installation. The rod drives are now.
functional. Installation and functional tests have been done at the 50-602 facility.
E. Facility Changes No. operation of the reactor in the steady-state-mode is planned pending removal ~of equipnient and components. Operation of the reactor in the pulse modo remains discontinued until the operation enaracteristics of the compt sated chamber as related to pulsing is established. This evaluation is not planned since current activitics 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.
l t
l 23
. - - , - . ~ , - - . ,
. . . . . ~ . -- . . ..- .- .. . . . . , . . . .. . . . - . . . . - . . . . . - . . - . - . . .
... .- 1 1
)
-1990 =)
l l
r: s
! NNP a
thr# kg);
s-e R ?
e
', O nn F1 -es R luLE E Pl N - 5 9 sn3 A' 1 .3 1M 3 -X # 3 - .3 . 3 ; R t . C - H :' E 5: r 3 R-Annual.~Burnup versus-Operation' Year. _
Figure 4 k
a-
.j-
- (
'$0MflE$ I e- -
--. htd ):
I #
E
.;g - .: ;
hR=e _ . ,,, m33 ri l E i R _; , ,
'O E eA A.1.3 M 1 3 - a - 2 7 3 - . 3 - g - g .;p a g-(;.c.stn - 7 4
l l- . ' Figure '
t Samples Irradiated versus Yeaf e ,
l: j 3
l -24 -
c , , ,
, , ., .. y y. , . . . .- - - , . - _ . , . . , - . , , . , , _ , , .,,,,_,-......._.,,,J.,,.J#-..w -,; ; . -... ; L ,
- .,v, , _ ,
1990 k
F. Radiation Exposures A summary of radiation exposure; during this reporting period to facility pets tTel, students, and visitors as shown in Table 8. The average exposure per individual and the greatest exposure por 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 r
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 susmarized in Table 11. Environmental surveys performed outside the laboratory are summarized in Table 12.
- 11. Radioactive Ef fluents
- 1. Gaseous Wastes Caseous discharge during the. reporting perit <t is 1Caited to leakage of Ar41 from the reactor laboratory, The tot ~;.1 estimated amount of radioactivity released was calcub.t.3d based on experimental data. A summary of the calculated radioactive gaseous discharges during the reportin6' period-is presented in Table 13.
An estimate of the release volume is calculated from the product of the monthly number of full power hourn- cperated-during the period and the effective-air leakage rate.
Although air leakage from the laboratory is restricted, an effective air change rate of'two per hour (.35 m3/moc) is assumed. The total activity released is calcu ated as the product of the volume released and the equilibrium concentration of Ar41 in the laboratory, measured at 4x10 8 G1/cm3.
The release paint concentration is determined as the product of the equilibrium Ar41 concer.tration in the laboratory, the l
l effective air leakage rate,- release point (0.14 sec/m3),-and the actual full' power hours' operated divided by the total number of hours in'the reporting period. The percent of the maximum permirsible concentration (MPC) is the release point concentration divided by the MPC for Ar41 (4x10 8 Ci/cm3) in unrestricted areas.
- 2. Liquio U-ate No liquid radioactive woste was discharged during the repot,'r.; period, Efforts are made co avoid liquid waste disposal by appropriate evaporatten or-absorption techniques i
2$
- - . - . _ - _ . _ , .4._ _ - . .- - _. .
1990 for small volumes 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. A11~ solid waste materials were packaged and shipped, along with radioactive waste generated in other departments, by the Safety Office. Waste shipments are performed by Texas
~
e 26 L ., . . . _ - , ,. . .
1990 Table 8 Summary of Personnel Radiation Exposures Ranee of Exposure
'A. REM Number of Individuals
-Staff Students Visitors No measurable exposure 9 3 92 Measurable exposure less than 0.1 2 0 1 ,
0.1 0.25 0 0 0 0.25 0.5 0 0 0 0.5 - 0.75 0 0 0 0.75 - 1.0 0 0 -0
. 1.0+ .0 0 0.
Table 9-l Radiation Exposure Groups l
l-Exposure rer Individual in mrem Croup Average Createst l
l
{-
Staff 4 80 Students < 10 < 10 Visitors < 10 < 10 4
4 i .27
l l
1990 Table 10 Laboratory Radiation Levels location Average (mR/hr) Maximum (mR/hri-Control Conrale Area 6,8x10 3 2,7x10 2 10 f'., from core axis 6 ft, above pool Water Eystem Ares 1,4x10 2 2,7xio 1 12 ft, from core axis ,
i ft, above pool Above Core 7,3x10-2 _1,4xto.1' 0 ft, from core axis :
16 ft, above pool Table 11 Laboratory Contamination Levels Location .AveraPe Haitimba Floors 26 dpm 57 dpm Surfaces 26 dpm 60 dpm Pool Water 6,7 pCi/1 39 pCi/1 l
l 4
r 1
.28
-%- a- + 4d - _ ,a o -- - + 4 1990 l
l Table 12-Environmental Surveys Location Average Maximum-1 .01 mR/hr .01 mR/hr 2 .01 mR/hr .01 mR/hr 3 .02 mR/hr .02 mR/hr 4 .01 mR/hr ,01 mR/hr 5 .01 mR/hr ,01 mR/hr P
6 ;01 mR/hr .01 mR/hr 7 -15 pCi/1 45 pCi/1 4
e e
( ,
29 e- , e r s- a w- ,- -w-,- w * -<-t-g e*p-" -v*+g- +9
1
'1 1990 Table 13 Monthly Caseous Waste Discharge (ARGON-41)
MONTH EPPH VOLUME Ar.TIVITY REL CONC. X MPC
, (HRS) (M') 'pci) (pCi/CM')
x10 12 1
2 3
4 5 NO RELEASES 6
7 8
9 10 11 12 9
[
Monthly-Cas-ous Waste Discharge -
(gan or particulate)
Month Isotope Total Point of Release Percet' of Release Concentration Maximum
( Ci) (m )' (pci/m') (> 20%):
l l Jan Feb Mar Apr May Jun NO RELEASES Jul l
Aug Sep l Oct Nov Dec
- Total l Table 14
-30 4
=
1 1990 j Monthly Liquid Waste Discharge Month Isotope Total Point of Release Percent of Release Concentration Maximum
( C1) 8 (m ) (pCi/m8 ) (%)
Jan -
Feb -
Mar -
Apr -
May -
Jun -
NO RELEASES Jul -
Aug -
Sep -
Oct -
Nov -
Dec -
Table 15 Monthly Solid Waste Disposal Montt Isotope Total Form Remarks Release Chemical / Physical (pC1) (ft*)
l
! Jan -
)
Feb -
Har -
l Apr -
l May -
l Jun -
NO RELEASES-l Jul -
l Aug -
Sep -
Oct -
Nov -
l Dec -
i -
V. laboratory Inspections h
31
=
1990 l
V. Laboratory Inspections
. n. NRC Inspections l One license inspection for the R 92 license took place during the 1990 calender year. Inspection dates were January 25-28, 1990. Inspections of R 92 activities regarding health physics surveys and records and other activities were done during this inspection. One violation was noted and corrected for the type and frequency of area radiation surveys.
Activities of the construction permit CPRR.123 were subject to inspection three times during the year. Inspections were March 20 22, and two inspections July 18-19. No violation of the docket 50 602 construction permit was identified during. inspections, No NRC inspection.took place during the calender year for the SNM-180 special nuclear material license.
B. TDH Inspections
. The Texas Department of Health Bureau of Radiation Control
- inspections consist of a review of activities and radioactive l materials used at The University of Texas at Austin as authorized l
by TDH License. ~0ne inspection by the State of Texas took place during the calendar year on February 20 21, 1990. The inspection included the activitics ct the Balcones D.osearch Center facility.
No violations were noted, i
l l
l 5*'
1 l
t 1
! 32 l
l 1990 i l
VI. Public Service Activitics A. Lectures and Presentations I On numerous occasions during 1990 the NETL staff talked to various organizations about subjects including but not limited to:
" Nuclear Reactor Safety," " Nuclear Engineering and Society,"
l "Research and Development of Energy Resources," and " Energy and l the Environment."
Examples of programs che laboratory participates in are the Summer High School Science Teacher Symposium and Texas Energy Science Symposium, l
The NETL staff provides tours during the symposiums designed to familiarize high school science teachers with the theory and technology associated with energy resources today. Course credit is given to all participants who successfully complete the course.
The program is funded by various elect ric utility companies in Texas. Approximately twenty (20) teaccers attend the High School Science Teachers symposium every year. The number of Texas Energy Science Symposium students is typically .10, B. Reactor Facility Tours l
During 1990, no tours were held at Taylor Hall facilities.
All tours were at the Nuclear Engineering Teaching Laboratory at the Balcones Research Center. The largest group visiting the laboratory were persons attending the Texas Energy Scienco Symposium. Numerous high school students also toured the facility during an event called The World of Engineering, designed to recruit etudents into the field of Engineering. Special actLvities have also been provided in the efforts to recruit minority students into the engineering fields. Students from several local high schools and students from several non engineering related college courses visited the facility.
Numerous college engineering related classes and several student i
engineering organizations also toured the facility. Safety personnel such as Austin Fire Department, UT Police Departcent, 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.
C. Fuel Transfer Cask Loan A three element transfer cask was obtained as part of the fuel element acquisition from the Northrup Corporation. The donated cask is designed for standard elements of JRIGA fuel and is to be available for loan to otLer university reactor programs.
A container to ship the empty cask is also available. Charges'for
, the cask use vill apply only to shipment costs. The three element cask was Caed by Kansas State University in a defueling operation at that facility during 1989.
(
)
33
- ,_ ,- 0
. v 1990 VII. Research Activities
, The staff and users of the Nuclesr Engineering Teaching Laboratory perform research, as both sponsored and non sponsored proj ec ts , in several different areas. Equipment end personnel are e provided by the laboratory to supplement the research efforts of facility users, that include students, faculty and others. The following section lists research projects active during .the calendar year. Major 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 Bornerd W. Wehring, NETL Thomas L. Sauer, NETL
Description:
l The U.S. Department of Energy has provided research support by I 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 Center for Energy Studies Personnel: John R. Howell, ME Dept. :
Steve Nichols, ME. Dept.
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 j outstanding high school science students for over 25 years. The program is intended to encourage 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.
34
1990
! Table 16 Research Funding Department of Energy Fuel Assistance Program - - -
New Nuclear Engineering Teaching Laboratory (includes D&D for existing facility) 5,860,700 Sandia National Laboratories 131,000 4/87 - 1/91 Texas Parks and Wildlife Department 8/31/90 (Selenium & other metals) 10,143 8/31/91 (Selenium 6 other metals) 10,143 Texas Water Commission 8/31/90 (Selenium 6 other metals) 8,964 lexas Advanced Technology Program 6/88 - 5/1990 (Fusion Research) 344,110 (Cold Neutron Beam) 207,000 Texas Low Level Radioactive Waste Disposal Authority 6/1/88 8/31/89 194,035 College of Engineering
! 1999-1990 5,000 University Reactor Sharing, DOE 1989-1990 5,950 University Instrumentation Program, DOE 8/31/91 32,850 Subtotal 949,195-l a
I 35 l
1990-Heat Transfer and Friction Factor Analysis for Artificially Roughened Surfaces Sponsor: Center for Energy Studies Nat!onal Science Foundation University R3 search Institute Personnel: Dale Klein, NETL J . Parker Lamb, Hech. Eng.
Mike Krause, NETL Michael Michael, Mech. Eng.
David Glebe, Hoch Eng.
Description:
The proposed research is to determine the heat transfer and friction characteristics for surfaces with discrete roughness i geometry. Two major aspects are to be examined in that this is both an experimental and an analytical investigation. Values of R(h+) and G(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 decigned. In addition, a new analytical method has also been developed to determine R(h+) and G(h+) values without making detailed velocity and temperature profile measuremer.ts.
Analytical predictions will be made utilizing fundamental parameters in boundary layer theory coupled with the latest information on rough surfaces using integral techniques. Results 4
from the experimental and analytical methods-will be compared in order to gain insight as to the dominant mechanism involved for the use of discrete rough surfaces. This research has fundamental-application for heat transfer augmentation.
Pressure Drop and Heat Transfer Mes'. ements of Liqit'd Metal
" lowing in a Packed Bed Under the Influrace of a Magnetic Field-Sponsor: Center for Fusion En6i teering Texas Atomic Energy Res' arch Foundation Personnel: Dale Klein, NETL Mike Crawford, Mech. Eng Jon McWhirter
, George Avlonitis, Mech. Eng.
Description:
The flow of electrically conducting flui:is through porous media in the presence of a magnetic field has recently begun to generate-
. significant interest due to potential applicatitns for fusion ._
reactors. This study is designed to extmine tho pressure drop and heat transfer from a liquid metal (NaK) f1'wl.g through a packed bed of stainless steel spheres under the influence of a 36
)
_. - . - .- . -~ . . - - . . - . . . . .--
1990 i
' transverse magnetic field. Results'of this investigation should have direct applications on the design of fusion breeder blankets using liquid metal flowing around spheres of fertile material, l -. Application of COBRA for shipping Cask Analysis ;
l l Sponsor: Sandia National Laboratories Personnel: Randy Manteufel, Mechanical Engineering
' Dale Klein, NETL L Shawn Burns, NETL r
Description:
A thermal hydraulic computer code, COBRA, has been applied for both steady state and transient analysis. Previous-research-at The University of Texas at Austin involved the modification of~thei COBRA code and created a new version. COBRA *GCFR 4P/UTi The current research is directed towards modifying. COBRA *GCFR.4P/UT so that it may-be applied to transient' conditions .for_ shipping cask analysis.- One specific 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, recommendations will be made regarding the development'of a new code for thermal-analysis.
Neutron Transport Studies: Neutron Multiplication by Beryllium
~
Sponsor: National Science Foundation Personnel: Nolan E. Hertel, Center _for Fusion <
Engineering
Description:
The use of' beryllium as a= neutron. multiplier'isJcentral to the current. fusion breeder design. .Recent measurements _of beryllium; neutron multiplication and reevaluations of f beryllium nuclear data :
indicate that the multiplying performance- off beryllium' previously has been overestimated, possibly by_as much as 25%. If . . '3 i
beryllium's performance as a neutron multiplier'has indeed been l overestimated even by as much as 10%, the direction of the~ fusion breeder program in the-United States might;well change. It is a j tantamount to the current fusion breeder concepts that:the_ issue !!
. of' beryllium. neutron multiplication-be-resolved. Therefore, an experiment using a spherical shell'of beryllium is being proposeds
. The beryllium experiment-has been designed to measure multiplication resulting from'DT, DD, PuBe, Land 252Cf neutron sources being placed in-a spherical shell. By doing so the-sensitivity of the multiplication to spectral-shape-can be
}
37 i
, , .. _ . - . , , , , - . _ . . _.au .__ , _._
l
. 1 l
1990 observed. In addition, the use 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 1eakage. 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.
l New Method for the Determination of Iodine Value by Instrumental Neutron Activation Analysis Sponsor: Nuclear Engineering Teaching Laboratory Personnel: F Y. Iskander
Description:
Measuring the degree of unsaturation for oils and fats, as expressed by iodine value (I.V.), is an important step in the production of shortenings and margarine fats. Measuring-I.V. La also of great importance to detect. adulteration of vegetable oils with highly saturated animal fats and mineral oils. Early methods for the determination of I.V. depend on mixing a halogenating agent with the oil sample for a certain period of time,-then titrating the residual unrescted halogenating agent. Most of these mcthods require preparation of special reagents, large t -
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 I.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 by instrumental neutron activation analysis-(INAA).
The analysis of 50 sawples was completed in 75 100_ minutes (compared to several days by other methods).
Selenium and Other Metals in Fish Tissues
, Sponsor: Department of Parks and Wildlife, Stam* of Texas l
! Personnel: T.L. Bauer i
F.Y. 1skander
Description:
Tissue from muscle and liver _of fish samples from several Texas
, lakes are analyzed for several elements known to be toxic.
Elements of interest are selenium, arsenic, mercury and zinc.
This measurement is part of an environmental program for the State to examine the conditions of waters subject to certain types of power plant or industrial effluent releases.
38 '
- . _, ci. _ _ . . .
1990-Rare Earth Elements in Geological-Samples
. Sponsor: Department of Geology Personnel: F.Y. Iskander T.L. Bauer ,
Description:
1 Several geological samples including duplicates and several sources _of standards are being examined by: Instrumental 1 Neutron-Activation Analynis. ' The project is to determine the best' procedures and applicable methods'for the measurement of rare .
earths'in specific geologic-samples. -
CR39 Track Recorders for Fast Neutron Microdosimetry Sponsor: College of Engineering- -
Personnel: B.V. Wehring
-Heather Cepford- ,
Description:
An investigation-of the application'of CR39 trackietch types recorder is in progress. The project will study the-characteristics'of the CR39 track recorder-to determine an
. accurate measurement of-~ dose equivalentLand~ develop a method for inexpensive _ image analysis, 3
{ Development of a Cold Neutron Source J Sponsor: Texas Advanced _TechnologyfProgram Personnel: B.W. Wehring.
Takashi Emoto '
Description:
, A cold-neutron-source'will be' designed and' fabricated-fort
! the BRC TRICA facilityf Modification of a design 1first developed at j Corne11' University will belthe . basis ' for the proj ect. The source will use a low energy neutron scatter,.--mesitylene, withia-
-cryogenic. refrigeration 1 type system external to'the beam tube =to
- produce 1the= cold neutrons, fA wave guide system willsbe insta11edo to extract the' neutron beam. . The completed: system will provide at neutron beam'with a low energy! characteristic:that-will be available to-researchers-in other~ disciplines. LTwo majora experimental; goals _of _ the -project are to provide s'ubthermal neutrons!and to obtain a good signal to3 background relationship, 39
1990 Radiological Assessment of Low Level Waste Site
- Sponsor: Texas Low Level Waste Disposal Authority Personnel: Nolan E. Hertel Randall Charboneau
Description:
A performance assesame;.c of the proposed site for Texas loa icvel waste disposa! is 'oeing done. Radiation exposure pathways of significance .ro being defined. Modeling of the pathways will assess the environmental impact of the disposal site.
Radiation Transport Studies for IGNITEX Sponsor: Texas Advanced Technologies Programs Personnel: N.E. Hertel R. Carrera T Parish
Description:
Problems in radiation transport that relate to operation of the IGNITEX proposal are being analyzed. Problems identified include nuclear heating rates, neutron activation and dose rates of the
. fusion ignition experiment proposal.
Phantoms and Dosimetry Sponsor:
Personnel: Nolan E Hertel-
Description:
Phantoms, sources and geometries applied in laboratory calibrations of personnel dosimetry differ from the international definitions and practical use of dosimeters on personnel, Monte Carlo simulations of irradiation conditions were performed to provide insite into the dosimeter response.
4 40
_ .. - _ - ~ _
VIII. Publications From the Nuclear Entineering Teaching Laboratory Ph.D. Dierettations
- 1. R.D. O' Dell, "The Angular Thermal Neutron Spectrum in the Vicinity of the Interface Between Two Media", Ph.D.
Dissertation, The University of Texas at Austin, 186 pp.,
January 1965.
- 2. B.E. Thompson, Sr., " Cryogenic Neutron Spectra Measurements Across a Discontinuity in Temperature and Properties", Ph.D.
I Dissertation, 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 University of Texas at Austin, 203 pp. .. August 1968.
- 4. P.J . Rodriguez , " Time and Energy Dependent. Neutron Distribution in a Pulsed Multiplying Medium", Ph,D. Pissertation, 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-Interrogation", Ph.D. Dissertation, The University of Texas at Austin, 183 pp., August 1971.
l 7. G.D. Bouchey, "The Optimization of Nuclear Systems",. Ph.D.
l Dissertation, The University of Texas at Austin, 231- pp. ' August i 1971.
l 8. J.B. Whitworth, "The Development and Application of a Systematic Approach to Elemental Analysis in Forensic. Investigations",
Ph.D. Dissertation, The University of Texas at Austin, 223 pp.,
December 1971.
l
- 9. J. Freim, " Theoretical and Experimental ~ Evaluation of Nuclear l Data and Calculation Techniques for Fusion Reactor Blanket Design", Ph.D. Dissertation, The University. of Texas at Austin,-
210 pp., December 1972.
l
- 10. D.C. Anderson, " Fission Product Mass Yield Measurements from Intermediate Energy Neutron Fission of Plutonium 239 and ,
Plutonium 241", Ph.D. Dissertation,' The University 'of Texas at Austin, 125 pp., December 1972, i
41
l l
1 11, J.R. Deen, " Measurement of Fission Product Yic1ds from Thorium- 1 232 in a Californium 252 Fission Neutron Spectrum", Ph.D.
Dissertation, The University of Texas at Austin, 141 pp., Hay 1973.
- 12. T.A. Parish, "Neutronic and Photonic Analyses of Simulated Fusion teactor Blankets Containing Thorium and Natural Uranium",
Ph.D. fissertation, The University of Texas at Austin, 329 pp. ,
Januar) 1974,
- 13. J.H. Va nston, Jr. , "Use of the Partitive Analytical Forecasting (PAF) lechnique for Analysis of the Effects of Various Funding and Adninistrative Strategies on Nuclear Fusion Power Plant Development", Ph.D. Dissertation, The University of Texas at Austin, 459 pp., January 1974,
- 14. E.M.B. Sorensen, " Thermal Effects on the Biological Magnification of Arsenic in Green Sunfish, Lepomis Cyanellus",
Ph.D. Dissertation, The University of Texas at Austin, 233 pp.,
May 1974,
- 15. S.P. Nichols, " Application of the Partitive Analytical Forecasting (PAF) Technique to the United States Controlled Thermonuclear Research Effort," Ph.D. Dissertation, Mechanical
. Engineering (Nuclear 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 the Identification of Splitting Surfaces in Monte Carlo Particle Transport Calculations", Ph.D. Dissertation, The University of Texas at Austin, August'1975.
- 18. S.A. Hodge, "I'etermination of Friction Factors and Heat Transfer Coefficients for Flow Past Artificially Roughened Surfaces",
Ph.D. Dissertation, Mechanical Engineering (Nuclear Engineering)
Department, The University of Texas at Austin, December 1979.
- 19. Y. Yang, " Heat Transfer Through A Randomly Packed Bed.of Spher s by.the Monte Carlo Method", Ph.D. Dissertation, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, December 1981.
- 20. M.M. Razzaque, " Finite Element Analysis of Combined ~ Mode Heat Transfer, Including Radiation in Gray Participating Media",
Ph.D. Dissertation, Mechanical Engineering (Nuclear-Engineering)
, Department, The University of Texas at Austin, May 1982.
42
I
- 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,
- 22. 'Yukitaka Kunimoto, "A Core . Inventory Model for Fuci Trajectory '
Analysis in' fusion Fission Symbiotic Systems, Ph.D.
Dissertation, August 1983.
- 23. T. L. S anders , "Magnetohydraulic Flow'Through a Packed Bed of
. Electrically Conducting Sphares", Ph.D. Dissertation,: Mechanical l Engir.eering (Nuclear Engineering) Department,- The. University of Texas at Austin, May 1985,
- 24. R.D. Smith, " Routing and Sche'duling of Radioactive Material I Shipments",-Ph.D. Dissertation, Mechanical Engineering Department, The University,of Texas at Austin,; August -1987,
- 25. Richard W, Hartley, " Neutron Multiplication by Beryllium", Ph'D; .
Dissertation, December 1987.
- 26. Frances Ann Patterson Hine, " Object-oriented Programming Applied-to the Evaluation of_ Reliability Fault;Treos",,Ph.D.
. Dissertation, Mechanical Engineering Department,'The University; of~ Texas at Austin,.May.1988.-
- 27. Arlen Sharif Heger, "An Adaptive Interface-(KNOWBOT) for Nuclear
. Power Industry Databases", Piv.D. Dissertation, Mechanical-l Engineering Department, The. University _ of Texas at Austin,-
August 1989.
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, . . , . _ . , - _ _ . . , . _ . _ . _ _ . . ~ , _ _ . . _ - . _ . . _ . - . _ _ . . _ . _ -
Masters Thesis
- 1. K.L. Gilbert, " Neutron Flux Mapping of a Subcritical Reactor Core with a Polyethylene Reflector", Masters Thesis, Physics (Nuclear Engineering) 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 Engineering) 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 Suberitical Reactor", Masters Thesis, Physics (Nuclear Engineering) Department, The University of Texas at Austin, 85 pp., August 1962,
- 5. P. Berananda, " Neutron Flux Distribution of a Suberitical
. Reactor Core with a Graphite Reflector", Masters Thesis, Physics (Nuclear Engineering) Department, The University of Texas at Auscin, 40 pp. , January 1962.
- 6. T.A. Fredericks, " Thermal Neutron Flux Distribution Due to a Plane Wave Source in an Unreflected Reactor Ascombly", Masters Thesis, Physics (Nuclear Engineering) Department, The University of Texas at Austin, 107 pp., August 1963,
- 7. D.G. Martin, " Film Detector for-a Neutron Spectrometer", Masters Thesis, Physics (Nuclear Engineering) Department, The University of Texas at Austin, June 1963.
8, M.L. West II, " Flux Decay Rate in a Reflected Subcritical Reactor", Masters Thesis, Physics (Nuclear Engineering)
Department, The University of Texas at Austin, 55 pp. , August 1963,
- 9. R.S. Kolflat, "An Experimental Approach to the Study of Nucleonic Fundamentals", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, 190 pp., May 1965.
~
- 10. J.B. Whitworth, "A Cryogenic Irradiation Device for the TRIGA Mark I Nuclear Reactor", Masters Thesis, Mechanical Engineering
, (Nuclear Engineering) Department, The University of Texas at Austin, 52 pp. , January 1967, 44
- _ . - . - . . - . . . . . - . - . . . - . - - . --- . ~ ~ - . . _ . -
- 11. D.A. Pullen,c"A Rod Oscillator Design and Zero Power Transfer- 3' Function Measurement for a TRIGA Mark I Reactor," Masters _
Thesis, Mechanical' Engineering-(Nuclear Engineering) Department, The University of Texas at Austin, January 1967.
- 12. G.F. Malan, " Transfer Function Analysis of Temperature and Xenon Feedback in Coupled Core Nuclear Reactor-Systems",-Masters l Thesis, Mechanical Engineering (Nuclear Engineering) Department, _ l The University of Texas at Austin, 69 pp... August:1967. I
- 13. F.H. Antunez Castillo, " Gamma Radiation Dosimetry Techniques and Application to Happing of The_ University of Texas Cobalt 60-Irradiation Facility", Masters Thesis, Physicsf(Nuclear Engineering) Department, The. University of Texas at Austin,:602 pp., September 1968' .
' 14. R. Valiente, " Neutron Radiography with-The University of Texas-TRICA Nuclear Reactor", Masters Thesis, _ Physics-(Nuclear ~
Engineering) Department, The University of Texas at- Austin,-
August 1968,
- 15. J.A, Villalobos, "A Study of Gamma' Radiation. Dosimetry l Techniques and Application to Radiation Field Mapping", Masters '
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);
Department, The University of Texas at- Austin, January 1969.=-
- 17 . - G.D. Atkinaon, Jr. , " Investigation of the Dynamic' Beshavior.;of a Two Region Suberitical Reactor",--Masters Thesis, Mechanical-Engineering (Nuclear Engineering); Department,,The University ofu Texas at; Austin,' January 1969.
- 18. M. Gallardo', " Trace Elements-in-Six Quartz Samples'by- '
Nondestructive Neutron Activation; Analysis Technique", Masters; Thesis, Physics-(Nuclear Engineering) Department.--The University-of Texas .at Austin, January 1969. ,
- 19. F.C. Pasos, "Nondispersive X Ray _ Fluorescence Analysis.using a- 1
. Lithium Drifted Germanium Detector"- Masters Thesis, Physics
, 4 (Nuclear Engineering) Department, The University of Texas at '
Austin,- 54 pp., January 1969.
- 20. : D.G. Jopling', "The Politics of Nuclear Reactor Siting", Masters Thesis, Mechanical Engineering'(Nuclear Ena'neering): Department,-
J The University of Texas at Austin, December.1970.
- 21. A.H.-Urdaneta, "A Programmed Associative Analyzer",-Masters:
Thesis, Mechanical Engineering (Nuclear Engineering) Department,
. The University.of-Texas at Austin,' December,1960.
J
-45
_ . . . _ . - . . _ . _ _ ._. _. , _ _ _ _ . , , a... . . _ . ~ . .
r
- 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, " Neutron Activation Analysis of Chlorine and Bromine in Some Haliburton-Bancroft Rocks and Minerals", Masters Thesis, Physics (Nuclear Engineering) Department, The University of Texas at Austin, January 1970,
- 24. R.J . Gramatges-Figueras , " Neutron Waves in Cylindrical Coometries for a Subcritical Reactor", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The Univoraity of Texas at Austin, 98 pp. , May 1970.
- 25. E. Oelkers, Jr. , "A Learning Method for Identification of Nuclear Reactor Point Dynamics", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, 165 pp., August 1970.
- 26. J.R. Deen, " Calculation of Resonance Integrals Using the Intermediate Resonance Approximation", Masters Thesis, Mechanic 11 Engineering (Nuclear Engineering) Department, The University of Texas at Austin, 140 pp., January 1970.
- 27. C.T. Rombough, " Application of Queucing Theory to closed Loop Computer-Peactor Control Systems", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, 78 pp., December 1970.
- 28. A.H.U. Bohorquez, "A Programmed Associative Analyzer", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, 98 pp., December 1970,
- 29. J.J. Chromik, " Experimental Determination of the Neutron Flux in The University of Texas Californium 252 Irradiati .i Facility",
Masters Thesis, Mechanical Engineering (Nuclear Engineering)
Department, The University of Texas at Austin, 85 pp., December 1971.
30, M.B. Owen, " Fuel Management Using Dynamic Programming" Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, 59 pp,, May 197?.
- 31. C.E. Brauer, " Thermal Neutron Radiography with a Lithium-Lead Collimator-Filter", Masters Thesis, Mechanical Engineering (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.
46 ,
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- 33. S.G. Barbee, *Neutronic Calculations in a Simulated Fusion Reactor Blanket", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, 259 pp., November 1972; 34, D.M. Williams, " Identification of Thormal Feedback Parameters for a TRIGA Mark I Reactor", Masters Thesis, Electric Engineering Department, The University of Texas at Austin, 53 pp., December 1972.
35, L.D, Hansborough, "Overall Tritium Considerations for Controlled ,
Thermonuclear Reactors", Masters Thesis The University of Texas at Austin, 154 pp., May 1973, i
36, M.E. Senglaub, " Cross Section Studies Based on the Statistical Model", Masters Thesis, The-University of Texas at Austin, 109 j
pp., August 1973. .
- 37. S.P. Ninhols, " Experimental Determination of Neutron Fermi Age from Californium 252 Fission Spectrum to Cadmium Covered Indium Resonance in a Graphite Medium", Masters Thesis, Mechanical Engineerit.d (Nuclear Engineering) Department, The University of Texas at Austin,101 pp. , January 1974.
. 38. Thomas L. Bauer, " Discrimination of Uranium 235 and Plutonium-239 by Cyclic Activation and Delayed Gamma Ray Analysis Using 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. Olan D. Thompson, " Optimization of Shipping Containers for -
Radioisotopic Neutron Sources", Masters Thesis, Hechanical ,
! Engineering (Nuclear Engineering) Department. The University of' Texas at Austin, 30 pp.,- (August 1974). .
l 40, J.W. Davidson, "A Cost Benefit Analysis for Partitioning .
Strategies Involved in High-Level Nuclear Waste Management",.
Masters Thesis, Mechanical Engineering (Nuclear Engineering)
Department, The University of Tovas at Austin, May 1975.
9 41, J.P. Percy, " Experimental' Determination of Local' Convective Heat Transfer Coefficients Over a Ribbed Surface", Masters Thesis, ,
L Mechanical Engineering (Nuclear Engineering) Department..The
! University of Texas at Austin, May 1979.
- 42. G.A. Taylor, "The Analysis f the Grid Spacer Pressure and Temperature Effects in SAGaP0", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, August 1979, D
47
- 43. D.D. Hsu, " Determination of the Relative Toxicities of the Fission Products Produced in the Transmutation of Actinide Wastes", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, December 1979.
- 44. M.A. Ross, " Electrical Power Generation and Process Heat Application for Coal Casification and Liquefaction Using a Very-High Temperature and Cas Cooled Reactor", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, May 1980.
- 45. Y. Kunimoto, " Waste Stream Toxicities in Thorium Fuel Cycles for Pressurized Water Keactors", M.S.~ Thesis, May 1980.
- 46. S.J. Ganther, "The Effects of Initial Enrichment in the Accelerator Breeding of Nuclear Reactor Fuel", M.S, Thesis, August 1980.
- 47. W.E. Murphie, " Measured Neutron and Gamma Ray Spectra in a Tissue-Equivalent Liquid Irradiated with 14 MeV Neutrons", M.S.
Thesis, December 1980.
- 48. T.L. Sanders , "An Alternative Numerical Method for the Steady
. State and Transient Thermal-Hydraulic Analysis of Cas-Cooled Fast Breeder Reactor Arrays", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, May 1981.
- 49. J . E. Hamann, " Thermal Analysis of a Spent Fuel Railcar Shipping Cask in an Engulfing Fire", Masters Thesis, Hechanical Engineering (Nuclear Engineering) Department,1The University of Texas at Austin, May 1983,
- 50. M. 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 1983.
- 51. A. Patterson-Hine,
- Characterization of the Effects of Continuous Salt Processing on the Performance of Molten Salt Fusion Breeder Blankets", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, May 1984.
- 52. E. Ibrahim, " Determining the Minimum Plasma Minor Radius for a Power Balanced Reversed Field Pinched Device at Ignition",
Masters Thesis, Mechanical Engineering (Nuclear Engineering)
Department, The University of Texas at Austin, December 1984.
I 48
y
- 53. M.C. Krause, " Design and Fabr'ication of.a Texas Assembly for the Evaluation-of Heat Transfer-in Flow Past Discrete Roug'hness 4
- Elements", Masters Thesis,- Mechanical Engineering (Nuclear:
Engineerin6) Department, The Universityrof Texas at Austin, December 1984.
- 54. R.D. Savage, " Error Analysis for a Hydrogen Filled Benjamin. ,
i Counter", Masters Thesis, Mechanical. Engineering Department The:
l University of Texas at' Austin, December 1984.
~
55 A. Sharif-Homayoun, " Comparison of: Parametric Empirical Bayes g
with Maximum Likelihood Estimators When Applied toLNuclear l Reliability Data A Simulation Study", Masters Thesis, L Mechanical Engineering Department, The- University of, Texas at !
Austin, December =1983.
- 56. R.M. Lauclus, " Calculation of.the Differential Efficiencies.of organic Scintillators to Neutrons", Masters Thesis, Mechanical-Engineering Department, The University of Texas ?at' Austin, May - _
1983,
- 57. N,D. Poor, "A Comparison of Low Level Radioactive Waste Storage and Disposal Techniques",~M.S. Thesis, August-1985..
. 58. R.D. Manteufel, "Analagous Fidite Element /Einite Difference Method for the Heat Diffusion Problem", Masters-Thesis,
- Mechanical-Engineering-Department, The University 'of Texas at--
- Austin, December ~1987.
l 59. Jose Nicloas Perina Cruz, "Determinacionide Cromo en1Suero de=
l- Bovinas Medicante el Metedo de Analists por Activacion. con' .
Neutrones", Universidad Autonoma de Neuvo Leon,: September 1983.
l.
- 60. M.A, McGraw, " Exposure Assessment for Disposal;ofyLow Level;
[ Radioactive. Soil", M.S. Thesis, December 1989-(Civil Engineering
. Department, Co Advisor with Dr. R.J. _ Charbeneau) .
- 61. C.C. Pollard, " Analysis of the Biotic Pathways;for a. Texas Low-Level Radioactive Waste Disposal- Facility", August 1990' .
l .(Biological-Sciences, Co Advisor with Dr. C. McMillan)u
- t
- 62. E. Takesuye, " Photon Dose Equivalents in: Phantoms"..M.S. Thesis, . -;
May'1991.'
l L .
49 b
Reports and Papers
- l. D.G. Anderson. "A' Technique for Recoil Fission Frag ment Range Mensurements", Health Physics, 1216, 558 (April 1966).
- 2. P.J. Rodriguez and D.H. Nguyen,- " Time Decay Constants in Pulsed Multiplying Media", Trans. Amer. Nucl. Soc. 11:1, 289 (June 1968).
- 3. P.J. Rodriguez and D.Hi Nguyen, "The Maximum Eigen value in the Pulsed Neutron Initial Value Problem", Trans. Amer. Nucl. Soc.
1112, 578 (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. Amer. Nucl. Soc.-11:2, 582 (November 1968).
- 5. G.D. Bouchey and S.J Gage, " Neutron Radiography with a Small Suberitical Reactor", Trans. Amer. Nucl. Soc. 12, 462-(1969).
- 6. C.D. Atkinson, Jr. , W. Coltharp, R. Cramatges, E. Oelkers, D. A, Roberts, K.R Wald, S.H. Gage, and B.V. Koen, " Project Atlantis:
A Design of the Nuclear Power Supply for an Undersea City",
Proc. of the Offshore Technolorv Conference, Dallas, Texas, 1969,
- 7. V, Chanto, S.J. Gage, and D.F. Barker, " Chlorine and Bromine Concentrations in Some Haliburton Bancroft Rocks and Minerals by Neutron Activation Analysis", 1969.
- 8. M. Gallardo, S.J. Gage, and D.F. Barker, " Trace Elements in Quartz by Nondestructive Neutron Activation Analysis", 1969.
- 9. F.A. Rodriguez, S.J. Cage, and-K.M. Ralls, " Nondestructive Neutron Activation Analysis for Trace Impuritios in Niobium",
-presented at the Seversh Symposium on Nondestructive Evaluation of Components and Mater'als in Aerospace, Weapon Systems,.and Nuclear Applications, ,an Antonio, Texas, 1969,
- 10. S.J. Gage and M. Zuniga, " Uranium _ Trace Analysis by Pulsod' 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, " Migration and Enzyme Polymorphisms in Natural Populations of Drosophila", Jao. J . Gen. , 1969.
^
- 12. R.H. Richardson, R.J Wallace , J r. , S.J . Gage , G.D. Bouchey, _ and Margaret Donell, " Neutron Activation Techniques for Drosphila in Natural Populations", Studies in Genetics,. Marshall R. Wheeler Ed. , The University of Texas Prese, Austin, Texas, 1969.
b 50-
- 13. C.D. Bouchey and S.J. Gage, " Development and Potential Utilization of a Neutron Radiography Facility at The University of Texas Nuclear Reactor Laboratory", presented at the Seventh-Symposium on Nondestructive Evaluation of Components and Materials in Aerospace, Weapons Systems and Nuclear 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 Transactions 11, 287 (1968).
15, G.D. Bouchey and G. Gjerstad, " Chemical Studies of Aloe Vera_ ,
Juice - II. Inorganic Ingred' .,cs", Ouarterly Journal of Crude i Drug Research, 9:4, (1969),
- 16. S.J. Cage, R.H. Richardson, and G.D. Bouchey, " Neutron Activation Techniques for Labeling of Insects with Stable Elements", Trans. Amer. Nucl. Soc., 12,-495 (1969).
17, G.D. Bouchey, B.V. Koen, and C.S. Belghtler, "The Optimal Allocation of Energy in Industrial and Agro Industrial Complexes Using Dynamic Programming", Nucl. Sci. and Ener., 41, 70 (1970).
- 18. G.F. Malan and B.V. Koen, "A Nonlinear Programming Approach to
. Optimal control of Nuclear Reactors", Trans. Amer. Nucl. Soc.,
(1970).
- 19. M.G. Stevenson and S,J. Gage, " Application of a Coupled Fission-Mode Approach to Modular Reactor Kinetics", Journal of Nucl ,
$ Energy, 14, 1 (1970).
- 20. G.D. Bouchey and S.J. Gage, " Neutron Radiography at The.
University of Texas Nuclear Reactor. Laboratory", Isotopes and Radiation Technology, 1, 294 (1970).
- 21. G.D. Bouchey and S.J. Gage, " Detection and location of Leaking TRIGA Reactor Fuel Elements", CA Publication T-ll7, Papers and
. Abstracts, TRIGA Reactors Owners' Seminar, Denver,-Colorado, February 1970,
- 22. G,D. Bouchey and S.J. Gage, " Neutron Radiography-with a Small Suberitical Assembly", Internntional Journal of Nondestructive Testing, 1970.
- 23. G.D, Atkinson, Jr. , J .B. Whitworch, and S.J . Gage , "NAACOL - A Spectrum Analysis Routine for the Small Laboratory", presented at the 21st Mid America Symposiumion Spectroscopy, Chicago, Illinois, 1970.
, 24. S.J . Gage , G.D. Atkinson, Jr. , J ,B Whitworth, and A.H.
Pradzynski, " Computer Aided Multielement Gamma Ray Analysis with a Compton Suppressed Ge(Li) Radiation Source", presented at the Ninth National Society of Applied Spectroscopy, New Orleans, Louisiana, October 1970.
51
- 25. J .J . Chromik and E.L. Draper, Jr. , " Energy Integral Tests of Differential Fission Cross Section Data", Trans. Amer. Nucl.
h , 1112, 755 (1970).
- 26. S.J . Gage and D G. Jopling, The Nunlex Concept: Potential for the SINB Renton, Southern Interstate Nuclear Board, 250 pp.,
March 22, 1971,
- 27. G.F. Malan and B.V. Koen, " Application of Nonlinear Programming to the Optimal Control of a Point Model Nuclear Reactor", Nucl.
Sci. and Engr., (1971),
- 28. G.D. Bouchey, B.V. Koen, and C.S. Beightler, " Optimization of Material Safeguards Sampling System", Trans. Amer. Nucl. Soc.,
Winter Meeting, 1971,
- 29. A.H. Pradzynski and S.J. Cage, " Nondestructive Identification of-Material by Nondispersive X-Ray Fluorescence Spectrosocpy Using Si(L1) Detectors and Radio isotopic Sources", Proc. Eichth Symposium on Nondestructive Evaluation in Aerospace. Weapong Syrtems. and Nuclear Apollentions, San Antonio, Texas, 1971,
- 30. G.D. Atkinson, J r. and S.J . Gage , " Uranium Assay by Delayed Gamma Ray Analysis Following Cf 252 Neutron Interrogation",
Proc. Twelfth Annual Meeting Institute of Nuclear Materials Manacement, Palm Springs, Florida, July 1971.
- 31. S.J . Gage, E. Linn Draper, Jr. , G.D. Bouchey, and R.R. Day,
" Design and Construction of a Versatile Cf-252 Source Shield and Experimental Facility", Neutron Sources and Acolications, CONF-710402, 2, Proc, of ANS Topical Meeting, Augusta, Georgia, April 1971.
- 32. D.G. Jopling and S,J. Gage, "Public Resistance to Nuclear Reactor Siting", Nuclear News, lill, 32 (March _1971),
j 33, J .B. Whitworth, G.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.
- 34. G.D. Bouchey, E. Linn Draper, Jr. B.V. Koen, and C.S. Beightler,
" Multiple Foil Activation Spectrum Determination Using a Numerical Direct Search Technique", Trans. Amer. Nucl. Soc.,
l 1sl2, 667_(October 1971),
- 35. G.D. Bouchey, B.V. Koen, and C.S. Beightler, "The Optimization of Nuclear Systems by Geometric Programming, Nucl. Sci. and Engh, M, 267 - (1971) .
- 36. G D. Bouchey, B.V. Koen, and C.S. Beightler, " Optimization of Nuclear Materials Safeguards Sampling by Dynamic Programming",
Nuclear Technolony, 12, 18 (1971).
52
- 37. S.J . Gage , G.D. Atkinson, Jr. , and G.D. Bouchey, " Cyclic F ron Activation Analysis with a Cf 252 Neutron Source", Irans. s sr.
Nucl. Soc., (October 1971).
. 38. E. Linn Draper, Jr. , " Integral Reaction Rate _ Determination Part I: Tailored Reactor Spectrum Preparation and Measurement", Entl.
Sci. and Entr., 44, 22 (1971).
- 39. E. Linn Draper, Jr. , " Integral Reaction Rate Determination Part II: Fission Rate Measurements", Epel. Sci. and Entr., 44, 31 (1971),
- 40. G.D. Bouchey and S.J. Gage, " Detection and Location of Leaking TRIGA Reactor Fuel Elements", Nuclear Technolony, 19, 211 (1971).
- 41. G.D. Bouchey and S.J. Gage, " Neutron Radiography with a Small Subcritical Reactor", Int. J. of Nondestructive Testing, 2, 335 (1971),
- 42. G.D. Bouchey and S.J. Cage, "The Economics of Suberitical Radiography", Trans. Amer. Nucl. Soc., 14, 123 (1971),
- 43. G.D. Bouchey, E. Linn Draper, J r. , and S.J . Gage , " Neutron
. Radiography with Cf 252: The Effect of-Tailoring Neutron Energy Spectra on Photographic Images", Neutron Sources and Anolications, CONF 210402, 3, Proc. ads Tooie-Meetinc,' Augusta, Georgia, April 1971.
- 44. G. D. Atkinson, J r. , J . B. Whitworth, and S .J . Gago , " Computer-Assisted Analysis of Gamma Ray Spectra", Computer Physint Communications, 2, 40 (1971).
- 45. S .J . Gage , E. Linn Draper, Jr. , and G.D. Bouchey, "Recent Developments in Radioisotopic Source Neutron Radiography", Proc.
Elchth Symposium on Nondestructive Evaluation in Aerospace.
Wennon Systems. and Nuclear Applications, San Antonio, Texas, 1971.
- 46. E. Linn Draper, Jr. , Mary Elizabeth Foster, and C.D. Bouchey, "X-Ray Fluorescence Analysis and Neutron Activation Analysis in an Analytical Chemistry Imboratory", presented at the Combined Meeting of the Texas Association for Radiation Research and South Central Photobiology Group, Houston, Texas,' November 1971.
- 47. E. Linn Draper, Jr. and G.D. Bouchey, " Utilization of a Portable Californium 252 Source for Neutron Activation Analysis and Neutron Radiogr?phy", presented at the Combined Meeting of the Texas Association for Radiation Research and South Central
. Photobiology Group, Houston, Texas, November 1971.
- 48. E. Linn Draper, Jr. and J.J. Chromik, " Production and Measurement of a Reference Spectrum in a Versatile Experimental Facility", Trans. Amer. Nucl. Soc., lill, 157 (1972).
l 53
=
4 1
-49. - E. Linn Draper, Jr. and Andrzej J . Pradzynski, " Identification of Alloys by Energy Dispersive X Ray Spectroscopy", presented at the Ninth Symposium on Nondestructive Evaluation, 1972._
< 50. G.D. Atkinson, J r. , E. Linn Draper, J r. , and G.D. Bouchey,.
"Subcritical TRIGA Reactivity Measurements Using the Source' Jerk Technique", presented at the TRICA Owners' Conference II, College-Station, Texas, 1972.
- 51. G.D. Atkincon, Jr. and E. Linn ' Draper, Jr. , " Transient Rod Failure in a Pulsing TRIGA Mark I Reactor", presented at the TRIGA Owners' Conference II, College Station, Texas, 1972, 1
- 52. G.D. Atkinson, Jr. , "A Safeguards. Minicourse", presented at the 18th Annual Meeting of-the An ican Nuclear _ Society, Las Vegas,-
Nevada (1972).
- 53. G.D. Atkinson, Jr. , E. Linn Draper c Jr. , G.D. Bouchey, and1S /J .
Cage, " Radioisotopic Source Amplification Using a !!eterogeneous Suberitical-Assembly", Proc. 18th Annuar Meeting of the'American Nuclear Society, Las Vegas,' Nevada _(1972). ;
54, E. Linn Draper, Jr. - and G.D. Atkinson, Jr. . " Transient Rod Failure in a Pulsing TRIGA Mark I Reactor", published in Proc.
- of 2nd TRIGA Owners' Conference, February.1972.
- 55. E. Linn Draper, Jr. , John W. Davidson, S.J . . Gage , and G.D.
~
Bouchey, "A Systa- I'r Reduction of 41A' Release from-a'Research Reactor Facill :y", Trans . - Amer. Nucl . Soc . , ));1, 4 -(1972); . ,
- 56. E. Linn Draper, Jr. . et al, " Standard foruthe Development of.
Technical Specifications for Research' Reactors".,'Trans-. Amer.
Nucl. Soc.. (1972).
- 57. E. Linn Draper, J r. ,- G.D, Atkinson, Jr. , and B.B. - Tomlin, "A 1
Radiography and Capture Gamma Ray Facility for Californium 252",
Proc. of the American Nuclear Society "Acolications ofL Californium 252": National Toolcal Meeting, September _1972. 4
- 58. E. Linn Draper, J r. .. G.D. Bouchey, G. D D Atkinson,; J r . ,: and S .J . _
Gage, "A Versatile- Suberitical: Assembly for Undergraduate ,
Nuclear Engineering Instruction" g Proc. of-~the'American Nuclear {
Society "Apolications of Californium 252"' National-Tonical' Meetine, September ~1972.
E 59, E. Linn Draper, Jr. and S. J.: Gage, '"The FusionFission Breeder:
Its Potential- in a Fuel' Starved Thermal Reactor Economy", l presented at the 93rd Annual Meeting of LASME, New York,1972._
. 60. E. Linn Draper, Jr.-, " Technological Innovation;and Assessment; }F Novel Course 1for Nuclear Engineerlag"., presented at the' Winter ,
Meeting of-the American Nuclear Soc?ety, November 1972.- l 1
.54
- -. . - - . . .. - - - - . ~ ,
. . _ . . - ~ . . - . _ _ . . - . - - . -
i 1
- 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, l
- 62. P.S. Schmidt and G.G. Park, " Heat Dissipation in a Power Plant Cooling Bay", ASME, Paper No. 72-WA/HT 61, November 1972.
- 63. P.S. Schmidt and G.P. D' Arch, " Entry Region Effects on Flow and _
Pressure Drop-of Lithium in Fusion Re actor Blankets",. Proc. of:
the Texas' Symoosium of Technolocv of Controlled Thermonulear Fusion Experiments and Encineerint Ascects of Fusion Reactors,--
- 64. E. Linn -Draper, Jr. and Charles Brauer, " Lithium Le'ad Collimatori Fabrication for Radioisotopic Source-Neutron Radiography",-
Trans. Amer . Nucl . Soc . , -U ;1, 142 (1972) ..
- 65. E. Linn Draper, Jr._ and James -B.' Freim, . " Theoretical and' Experimental Evaluation of Nuclear' Data and Calculation-Techniques.for Fusion Reactor Blanket = Design",_ presented at the Texas Symposium on the-Technology of Controlled-Thermonuclear-Fusion Experiments and the~ Engineering Aspects'of Fusion-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,iWashington, September 1972.
- 67. E. Linn Draper, _ Jr. , " Fusion Reactor Engineering in the Nuclear:
Engineering Curriculum at The'Universityfof Texas at Austin",
Trans.-Amer. Nucl. Soc.,-(1972).
- 68. E. Linn Draper, Jr. and S,J. Gage. "The Fusion Fission Breeder:
Its Potential in a: Fuel Starved Thermal' Reactor: Economy"p I
- presented at the Texas Symposium on the Technology of, Controlled
-Thermonuclear Fusion Experiments and the Engineering-Aspects _of i Fusion' Reactors, November 1972.
- 69. James B. Freim and E. Linn Draper, _ Jr. -7" Experimental" Determination of the Fusion Spectrum.in Graphite", Trans. Amer.
Nucl. Soc., (1972).
.70. G.D. Atkinson,- Jr. , S.J . Gage , .and G.D. Bouchey, . " Cyclic Activation with a Californium 252 Source",7 Nuclear Technolony
' (1972).
a 4 : 71. G.D. Atkinson, Jr. , "What lYou Always Wanted ~ to tKnow about -
Californium Source Facilities", Invited Paper, National Topicall
, Meeting on the Applications of Californium-252,. Austin, Texas (1972).
i -
I J
55
d .
l
- 72. T.L. Bauer and G.D. Atkinson, Jr. , ' Discrimination Between
~
Plutonium and Uranium by Gamma Ray Analysis Following Cf 252 1 Interrogation", presented at the National Topical Meeting on the Applications of Californium 252. Austin, Texas,1972. !
- 73. E. Linn Draper, Jr. , Editor, Proc. of Texas Symoosium on the-Technolorv of Controlled Thermo nt clear Fusion Exocriments and '
.ths.,Janineerine Aspects of Fusion Reactors, published by_USAEC.
- 74. E. Linn Draper, Jr. , Editor, Proc . of t'he Imolicatio'ns of' Nuclear Power in Texas, published by the Texas; Atomic Energy- ,
Research Foundation.-
l
- 75. E. Linn Draper, Jr. , J ,R. Deen,_ and J .J . Chromik, '" Measurement l of the Integral Fission Cross Section- of Th 232 in a Cf 252 l Fission Neutron Spectrum", Trans. Amer. Nucl.-Soc.,-(1973). l
-i 7 6 .- D.G. Anderson and E. Linn Draper, Jr. ,~ " Fission Product Mass- -i Yield Measurements from Intermediate Energy Neutron Fission of' '
Plutonium 239 and Plutonium 241"..Trans. Amer. Nucl. Soc.,
(1973).
- 77. E. Linn Draper, Jr. and James _ B. Freim,g" Experimental .)
'J
. Determination of the Fusion Spectrum 1in Graphite",.Trans. Amer.
Nucl. Soc., M ,;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. Soc., M , 16-(1973).
- 79. E. Linn Draper, Jr. , Theodore A - Parish, and Brian J McArdle, "A Neutronic Photonic Comparison of Vanadium and Niobium Containing Fusion Reactor Blankets", Trans; Amer. Nue11-Soc... 4 (November 1973).
. 80. John 11. ; Vanston, Jr. , "Use _of Partitive- Analytical Forecasting =
(PAF) Techniques for-Fusion Development Analysis",1Trans. Amer. .
Nucl. Soc., (November 1973). i
, 81. 1 Thodore A Parish and E. Linn Draper, Jr. , ~"Neutronic and
- , s'ic Analyses-of Fusion Reactor. Blankets Containing1
, , 4" , presented at the Fifth Symposium on Engineering.
1* j ems of Fusion Research, Princeton.- New Jersey,: November c i .i .
~
- 82. C.E. Lockefand D.R._ Paul, " Graft Copolymer.Modificationiof Polyethylene-Polystyrene' Blends. I.-Graft Preparation'and Characterization", Journal of Aon11ed Polymer Science, H, -2597
. (1973).
- 83. C.E. I.ocke and D.R. Paul, "Graf t Copolymer Modification of Polyethylene-Polystryone Blends. II. Properties _of Modified l Blends", Journal of~Apolled Polymer Science, M.,~ 2791 (1973). j I
I 1
l 56
- 84. E. Linn Draper, Jr. , M.J . Voltin, Jr. , J .L. Mac Donald, C.T.
Rombough, L,D. Hansborough, S .G. Barbee , and J .H. Vanston, J r. ,
"A University's involvement in Municipal Decision Making on Nuclear Power", Trans. Amer. Nucl. Soc., (1973).
E. Linn Draper, Jr. , J .L. MacDonald, and M.J . Voltin, Jr. ,
85.
" Nuclear vs. Coal: An Economic Comparison of Power Plant 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 1973.
87, G.D. Atkinson, Jr. , " Applications of Neutron Activation Analysis to the Life Sciences", presented at the combined Meeting of the Texas Association for Radiation Research and South Central Photobiology Group, San Marcos, Texas, November 1973.
- 88. E. Linn Draper, Jr. and J .R. Deen, " Measurement of Fission Product Yicids from Thorium 132 in Californium 252 Fission Neutron Spectrum", Trans. Amer Nucl. Soc., 12, 531-(1973)'.
- 89. E. Linn Draper, Jr. , M. Etzion, S.P. Nichols, and W.G. Davey,
" Neutron Fermi Age in Graphite- from Fission and 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'Containing Natural Uranium",
CONF 740402, USAEC, April 1974,
- 91. C.D. Atkinson, Jr. , B.D. Adams ,- and S.J Gage , "A Programmable and Automated System for Gamma and X-Ray Analysis", Proc. IEEE 1973 Nuclear Science Symoostum, San Francisco, California, 1973.
- 92. G,D. Atkinson, Jr. and R.E. Henry, " Neutron Activation Analysis:-
Environmental and Biolgical Applications",. presented at the l
Sixth Annual Meeting of the Texas Association for Radiation Research, San Marcos, Texas, 1973.
! 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 Fission Cross Section of Thorium 232 in a Californium 252 Fission Neutron Spectrum",
Nuclear Technolory, 11, 416-(1975).
57
l
- 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 l Cross Section Measurements of Threshold Reactions for Seven 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 Craphite Medium", Trans.
Amer. Nucl. Soc., 12, 800 (November 1975),
- 99. J.W. Davidson and E. Linn Draper, Jr. , " Costs for Partitioning Strategies Involved in High Level Nuclear Waste Management",
Trans. Amer. Nvel. 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).
4 102. 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. Radioana}.
Letters, 21:5, 277_(1975).
104. B. E. Bulla, E. Linn- Draper, J r. , R. E. Henry, M.J . Voltin, Jr. ,
et al, Texas Nuclear Power Policies! A Study of Alternatives.
Volume II: Methodolony, The University of Texas at Austin Center for Energy Studies, Policy Alternative Study No.1 (1975).
105. A.H. Pradzynski, R.E. Henry, and J.L.S. Stewart " Determination of Transition Metals by Radioisotope Excited Energy Dispersive X-Ray Spectrometrv", Trans. Amer. Nucl. Soc., 21:3, 34 (1975).
106. A.H. Pradzynski, R.E. Henry , and J .L.S. Stewart, "Non-destructive Determination of Toxic Elements in Toys", Proc. of 10th Symposium on Nondestructive Elements, San Antonio, Texas, April 1975.
58
107. R.E. Henry, " Determination of ppb Levels of Selected Elements :in Natural Water Using Radioisotope Excited Energy Dispersive X Ray.
Fluorescence Analysis", presented at the Eighth Anaual 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, ,
22, 59 (June 1976) .
109. T.A. Parish, " Fusion-Fission Hybrid-Studies at The University 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 Craphite Fusion Reactor Blankets Containing Sr90 and 1129", presented at the Second ANS Tcpical Meeting on-the Technology of Controlled Thermonuclear Fusion, Richland, Washington, September 1976, 111. T. A. Parish, J .W. Davidson, and J .B. Cornwell, "The Effectivenoss of a Sr90 Fusion Reactor Transmutation Waste Manageners Program", Tran9 actions of the American Nucicar
. Society, 24, November 1976.
112. A.H. Pradzynski and J.R. Rhodes, " Development of Synthetic Standard Saiaples for Trace Analysis of Air Particulates", ASTM Special Technical Publication, 111,.320 (1976).
113. A.H. Pradanyski, R.E. Henry, and J .S. Stewart, " Determination of ppb Concentrations of Transition Metals by Radioisotope Excited Energy-Dispersive X Ray Spectrometry, Journal of Radionnalytical Chemistry, 12, 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 using APDC Preconcentration and Radioisotope Excited X-Ray Emissicn Spectrometry", Proceedings of ERDA Symposium on X- and Camma Rav Sources and Aeolications, Ann
~
Arbor, Michigan, May 1976.
115. A.H. Pradzynski, R.E. Henry, and E.L. Draper, 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 Status Report. Transermions of Amer. Nuclear Society, 24, 119 (1976).
116. R.R. Cay, C.F. Brockett, and R.T. Johnson, "Two-Phase Flow Measurement Techniques for Nuclear Safety Research", Two-Phase Flow and Heat Transfer Symposium Workshop, Miami Beach, Florida, 1976.
59
l l .
117. C.W. Savery and R.R. Cay, "Effect of Entrained Droplet Phase Upon Predicted Compartmental Pressures in Nuclear Containments",
' Two Phase Flow and lleat Transfer Symposium Workshop, Miami Beach, Florida, 1976.
118. Rodney R,= Cay, " Reactor Hydrodynamies During the Reflood' Phase
' of Loss-of Coolant Accident", Nuclear Technology,. M 11, 229 (December 1977).
119. D , F. . Klein, S.R. Bull, and J .B. Miles ,- " Flow Visualization' Around CCFR Fuel Rod Roughness Elements",:Trans. Amer. Nucl.
f h, 23, -(June 1978) .
120. D.E. Klein, S.R. Bull, and J.B. Miles, " Pressure Drcp for CCFR Fuel Rod Roughness Elements",--Trans. Amer. Nucl. Soc.,_ M ,
(November 1978),
121. E.M.B. Sorensen, R.E. Henry, and R. Ramirez Mitchell, " Time Dependent Localization-of Arsenic in Subcellular liepatocyte Fractions", J. of Pathology and' Toxicology, 2.1!t, 1161:(1979).
122. E.M.B. Sorensen, R.E. Henry, and R.' Ramirez Mitchell,J" Arsenic.
Accumulation, Tissue Distribution Cytotoxity in Teleosts Following Indirect Aqueous Exposure" . Bulletin of Environmental Contamination and Toxicology, 21, 162 (1979).
123. J.W. Davidson and T,A. Parish, " Fission Product Toxicity ~
- Reduction via Transmutation Using D T Fusion Neutrons",
presented-at the Eighth Symposium on Engineering ~ Problems of-Fusion 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,~Trans. Amer. Nucl. Soc., H ,.(November _1979).
125. S. A. Ilodge, J.P. Sanders, (and D.E. Klein, " Determination of Friction-Factors and' Heat Transfer Coefficients for 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.Universit) or Texas at Austin, May 1979. _
127. D.E. Klein, H.H. Woodson, and J.W. Davidson, " Commercial Nuclear Power Generation"', Council-on Energy Resources,' The-University of Texas at Austin, June 1979.
128. E.M.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,.1979.
,60
L .
l 129. A,H. Pradzynski, " Determination of V and Ba in Marine Sediments and Biota", Internal Repor t, Nuclear Engineering Teaching
'
- Laborat.ty, Mechanical Engineering (Nuclear Engineering)
Department, The 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",
Irans. Amer. Nucl. Soc., }2, 632 (1979),
131. R.H. Johnson, K.R. Koch, B,W, Wehring, and N.E. Hertel, "TDL Measurements in an Iron Sphere Containing a DT Source", Trans.
Amer Nucl. Soc., 12, 632 (1979),
132, B,W, Wehring, J.J. Dorning, N.E. Hertel, D T. Ingersoll, and-R.H. Johnson, " Benchmark Shielding Problems Obtained from Integral Tests of Neutron Cross Sections", Trans. Amer. buel.
S m ,, 666 (1979). 133. N.E. Hertel, R,H Johnson, J .J . Dorning, and B,W, Wehring,
" Measurements and Analyses of Neutron Transport Through Iron", ,
Proc. Conf. Nuclear Cross Sections and Technolony, Knoxville, TN, October 22 26,1979,NBS Specini Publication #594,pp.568-571, 134. N.E. Hertel and B W. Wehring, " Absolute Monitoring of DD and DT Neutron Fluences Using the Associated Particle Technique", Nucl. Instr. Me_th., 112, 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, 11, 135 (February 1980),
136, N.E. Hertel, J.B. Smathers, and R.C. Graves, " Gamma-Ray Spectra Measured in a Tissue Equivalent Medium Irradiated with Neutron Radiotherapy Sources", Trans. Amer. Nucl. Soc., 11, 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, KY, June 21-26,'1981, , 138, D. E. Klein, S.R. Bull, and J , B, Miles , " Pressure Drop Measurements and Flow Visualization Sucrounding Roughness Elements", Journal of Enercy, 411, 112 (1980), 139. D.E. Klein, "ANS Student Involvement in Public Information The University of Texas at Austin", Invited Paper, Trans. Amer. l Nucl. Soc., 14 (1980), 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, i l 61
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, VATRAM 80, West Berlin, FRC., November 1980. 142. M. A. Ross and D.E. Klein, " Synthetic Fuel Production Utiliring Texas Lignite and a VHTR for Process Heat". Irans. Amer. Nucl. Ent , 11, (1980). 143. J.W. Davidson and D.E. Klein (co editors), Proc. of the International Conference on._Nucicar Wasta Transmutation. The University of Texas at Austin Press, MrTch 1981, 144. M. A. Ross and D.E. Klein, *Syntha*'.c Fuel Production Using Texas Lignite and a VHTR for Proces', Heat", Nucicar Technolorv, 1111, (March 1982). 145. T.L. Sanders and D.E. Klef n, "A Modified Numerical Scheme for CCFR Flow Transient Analy.is", Trans. Amer. Noel. Soe m, }}, (Novemoer 1981). 146. M.A. Ross and D.E. Klein, " Synthetic Fuel Production Using Texas Lignite and a Very High Temperature cas 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 Cas Flow Through a Tube", IAA Journal 2.Q11, 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 Prograin Interfaces for the IIansuranic Waste fat kage Iransporter (TRUPACT)", Sandia Report, SAND 81-2405, June 1982, 150. T.L. Sanders and D.E. Kielu, " Transient Thermal Hydraulic Analysis Using a Modified Version of COBRA IV", 7th International Heat Transfer Conference, Munich, Germany 82 IHTC-104, September 1982.
- 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, 62 i l - --- - -_-
152. T.L. Sanders and D.E. Klein, " Comparison Analysis of Severe Flow Blockages for Computational Efficiency Using COBRA", Proc. from Cas Cooled Reactura Todov Conference, British Nucicar Energy Society, London, England, September 1982. 153. M.M. Razzaque , J .R. Howell, and D.E. Klein ' Finite Element Solution of Radiative Heat Transfer in a Two-Dimensional Rectangular Enclosure with Cray Participating Media", 82 WA/HT-51, ASME Annual Meeting, Phoenix, Arizona, November 1982. 154. J,B. Smathers, N.E Hertel, and R.C. Graves, "In Phantom Photon Spectra Measurements for H16 h Energy Neutron Therepy Sources", Proc. from the Fourth tvmnosium on Neutron Dosimetry:BeWD Do m i.me t ry , Neuherberg/ Munich, Germat y, June 1981. 155. N.E. Hertel, B.V. Wehring, and J.J. Dorning, " Measurements and Analyses of High Energy Peutron Transport Through Tungsten", accepted for publication (subject to revision) in Nycl. Sci. and Enu , November 1981. 156. Y. Kunimoto, J.W. Davidson, and N.E. Hertel, "A Core Inventory Model for Fuel Trajectory Analysis in Fusion Fission Symbiotic Systems", Ira.ns . Amer. Nucl . S_oc. , il,1978 (June 1982) . 157. N.E. Hortel and W.E. Murphie, "The Use of Neutron and Gamma Ray NE 213 Spectral Measurements and Calculations to Obtain Dosimetric Information for DT Neutrons", Medien1 Phvoies, 10:66,
. (1983).
158. R. Laucius , J.W. Davidson, and N.E. Hertel, " Calculation of the Differential Efficiencies of Organic Scintillators to Neutrons Above 10 MeV", Irans. Amer. Nucl. Soc., 61, 625 (Nevember 1982). 159. J.W. Davidson and N.E. Hertel, "Bonner Ball Detection Responses for Neutrons from Thermal Energies to 17.3 MeV", Health Physics Society Annual Meeting Baltimore, Maryland, 1983, 160. N.E. Hertel, J .W. Davidson, and R.M. Laucius, "NE 213 Responso Matrix for Neutron Spectrometry Up to 50 MeV", Health Physics Society Annual Meeting, Baltimore, Maryland, 1983. 161. N.E. Hertel, J .W. Davidson, and R.M. Lauclus, " An NE 213 Response Matrix to 50 MeV",'Trans. Amer. Nucl. Soc., ii. 607 (1983). 162. J.W. Davidson and N.E. Hertel, "An Equal Probability Neutron Detection System Using Bonner Spheres", Trans. Amer. Nucl. SEEs,
- kl, 609 (1983).
163. M.M. Razzaque , J .R. Howell, and D.E. Klein, " Coupled Radiative and Conductive Heat Transfer in a Two Dimensional Rectangular Enclosure wAth Cray Participating Media Using Finite Elements", ASME/JSHE Thermal Engineering Joint Conference, ASME H 35, Honolulu, Hawaii, March 1983. 63 3
- - . - . . .-- -. - _ - ~ - - - . - . . _ , _ - . - -
164. S. Yang, J.R. Howell, and D.E. Klein, " Radiative Heat Transfer Through a Randomly Packed Bed of Spheres by the Monte Carlo
. Method", Journal of Heat Transfer, 105:2, 325 (May 1983).
165. M.M. Razzaque, J.R. Howell, and D.E. Klein, " Finite Element Solution of Radiative Hont Transfer in a Two Dimensional Rectangular Enclosure with Cray Participating Media", (accepted by the Journal of Heat Transfer). 166. M.M. Razzaque, J.R. Howell, and D.E. Klein, " Coupled Radiativo and Conductiv: Heat Transfer in a Two Dimensional Rectangular Enclosure with Cray Participating Media Using Finite Elements", Journal of Heat Transf tr. 121, 613 (1984). 167. E.M.B. Sorensen, C.W. Harlau. M.D. , T.L. Bauer, and A. Pradzynski, " Hepatocyte Changes Following Selenium Accumulation in a Freshwater Teleost", Ibe Amer. Journal of Forensic Medicine and Patholory, 11}, 8 (1982). 168. E.M.B. Sorensen and T.L. Bauer, "t Correlation Between Selenium Accumulation in Sunfish and Cha.iges in Condition Factor and Organ Weight". Evironmental Pollution Series A, Ql4}, 357 (1984), 169. E.M.B. Sorensen, T.L. Bauer, J .S . Bell, and C.W. Harlan.
" Selenium Accumulation and cytotoxicity in Teleosts Following Chronic, Environmental Exposure", Bulletin of Environmental contamination and Toxicolony, 22, 699 (1982).
170. E.M.B. Sorensen and T.L. Bauer, " Selenium Induced Hematological-Dyscrasia in Teleosts", Atchives Environ. Contam. and Toxicolony, 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 Accumuistion in Fish from Belews Lake, North Carolina", Archives Environ. l Contnm. and Toxicolony, 11, 153 (1984). i 172. E.M.B. Sorensen, R.R. Mitchell, A. Pradzynski, T.L. Bauer, and L. Craham, "Sterological Analyses of Hepat ocyte Changes Parallel Arsenic Accumulation in the Livers of Creen Sunfish", (accepted by The Journal of Environmental Patholony. Toxicolony and Oncolony), 173. N.E. Hertel and J.W. Davidson, "The Effect of Cadmium Covers on Bonner Sphere Responses", (abstract) Proc. of the Personnel Radiation Dosimetry Symnesium, Knoxville, Tennessee, October 1984. 174. N.E. Hertel and J.W. Davidson, "The Response of Bonner Spheres from Thermal Energies to 17.3 MeV", Nuclear Instruments and Methods, 6211, 509 (1985). 64
, 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.,
41, (1983). 176. A. Patterson Hine, J.W. Davidson, and D.E. Klein, " Contributions to the Thermal Power of Continuously Processed TMHR Molten Salt i Blankets", 10th Symposium on Fusion Engineering, Philadelphia, Pennsylvanie, December 5 9, 1983. 177. C.F. Polansky, J .P. Lamb, and D.E. Klein, "A Finite Element Analysis of Incompressible iaminar and Turbulent Flow with ileat Transfer", presented to the 5th International Symposium on Finite Elements and Flow Problems, The University of Texas at
- Austin, Austin, Texas , January 23-26, 1984, 178. M Ally, D.E. Klein, and T.L. Bauer, "Preconcentration Methods of Trace Elements in Water for EDXRF and INAA", 5th
.' International Conference on Nuclear Methods in Environmental and Energy Research, Mayaguez, Puerto Rico, April 2 6, 1984, 179. D.E. Klein and W.H. Miller, " 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 a Elemente in American Cigarette Tobacco Compared with International Brands", 17th Annual Meetin6 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", Fuel, 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 Society Meetine, Fifth International Conference, Mayaguez, Puerto Rico, April 2 6, 1984, i 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 Meetin5 on the Technology of Fusion Energy, San Francisco, California, March 1985, 184. T.L. Sanders, D.E. Klein and M.E. Crawford, "A Liquid Metal. Facility for the Analysis of MHD Effects in Fusion Related Systems", Egnion Technolocv, 111 (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 Molten Salt Fusion Breeder Blankets",
accepted to J. of Fusion Enercy. i 65
186. F.Y. Iskander, " Neutron Activation Analysis of an Egyptian Cigarette and its Ash", J. Radionnal. Nucl. Chem , E2, 511 , (1985). 187. F.Y. Iskander.
- Egyptian and Foreign cigarettes. Determination
- of Trace Elements in C16 arette Filter Before and After Smoking", J. Radionnn1. Nucl. Chem., 21, 191 (1985). 188. F.Y. Iskander, " Cigarette Ash as a Possible Source of Environmental Contamination", Environ. Pollut. (Series B), 11, , l (1986). 189. F.Y. Iskander, " Egyptian and Foreign cigarettes. 2. Determination of Trace Elements in Tobacco, Ash, and krapping Paper", 2, Radioanni. Nucl. Chem , 11, 107 (1986). 190. F.Y. Iskander, T.L. Bauer, and D.E Klein, " Determination of 28 Elements in American Cigarette Tobacco by Neutron Activation Analysis" Annivst, 111, 107 (1986). 191. F Y. Iskander, D.E. Klein and T.L. Bauer, " Determination of " Trace Impurities in Aspirin Tablets by Neutron Activation Analysis", J. Rndiennni. Noel. Chem., 22, 353 (1986). 192, H.M. Morad, F.Y. Iskander, L.W. Rooney, and C.F. Earp, "Physico-chemical Properties of Alkali cooked Corn Using Traditional and Presoaking Procedures", Cerent chem., k}(3) (1986) 255, 193. F.Y. Iskander and M.M. Morad, " Neutron Activation Analysis of Texas Hard Red Winter Vheat snd its Milling Fractions", American Association of Cereal Chemistry, 70th Meeting, Orlando, Florida, paper 151, 1985. 194. F.Y. Iskander, " Neutron Activation Analysis for_ Assessing the Concentration of Trace Elements in Laboratory Detergents", J. Apol Radiat. Isotones, }2 (5) (1986) 435. 195. F.Y. Iskander, T.L. Bauer, and D E. Klein, "Some Considerations of Elements Content of cigarette Wrapping Paper", TAPPl, k2 (5) (1986) 134. 196. F.Y. Iskander, M.M. Morad, D.E. Klein, and T.L. Bauer, (1987).
" Protein, In Vitro Protein Digestibility and Minerals Content of Hard and Soft Red Wheat Varieties", Ctr,tal Chem. 64: 285, 197. F Y. Iskander, (1987). Neutron activation analysis for measuring the unsaturation in edible oils. J. Radioanal. Nucl. Chem._
. Letters 118(2):149
- 198. F.Y. Iskander and M.M. Morad, " Minerals and Protein Contents in Texas Hard Red Winter Wheat and Its Milling Fractions", E22d Science..il (1986) 1522, 66
199, F.Y. Iskander, D.E. Klein, T.L. Bauer, and M.M. Morad, " Protein and Nutritional Elements Content in Texas Wheat", 18th Annual Meeting of Texas Associr. tion for Radiation Research, San Antonio, Texas, November 1985. 200. F.Y. Iskander and M.M. Morad, "Multielement Determination in Wheat and Bran", Radinochem. Radioanal. Letters, 1Q} (3) (1986) 151, 201, 0.1. 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, De nmark , 1986. 202. F.Y. Iskander, (1987). Maturation stage and mineral content in soybeans. J. Food Chem. 2h: 29. 203. T.R. Ajayi, F.Y. Iskander, 0.1. Asubiojo, D.E. Klein,(1989) Ceochemistry of upper cretaceous classic sediments of Ifon area, S. W. Nigeria. Journal of Mining and Geology. 25 (1,2):11. 204. K.R. Davis, F.Y. Iskander, H. Ashour, H.F. Hassan, 1990, Aluminum content in Egyptian brer.ds, J. Food Chem. 11:197. 205. F.Y, Iskander (1986). Use of NAA to determine nutritive elements in immature and mature soybeans. Trann. Am. Nucl. 1222, 12: 170 206. J . A. Adeptu, 0. I . Asubioj o, F.Y. Iskander, and T.L. Bauer, (1988). Elemental composition of Nigerian harmattan dust for ecological monitoring using instrumental neutron activation 1 analysis. J. Radionnal. Nucl. Chem. 121(1):141. . 207. R.D. Manteufel. D.E. Klein, and H.R. Yoshimura, " Benchmarking of Q/TRAN Thermal Analysis-Computer Code"_, PATRAM 86,'IAEA.SM. j 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 3 Containers", 1986 PATRAM User's Conference. 209. C.F. Polansky, J.P. Lamb and D.E. Klein, " Finite Element Simulation of Recirculating Flows with Heat Transfer", Communleation in Applied Nummerleal Methods, Vol 3, No. 1, P. 17 22, Jan Feb, 1987.
- 210. F.Y. Iskander, (1989) " Determination of iodine value by Br/INAA." Accepted J. Am'. Oil Chem Sce; 22:498.
211. 0.1. Asubiojo, F.Y. Iskander,(1988) . "A Trace element study of commercial infant milk and cereal formulas " J. Radioanal. Nucl. Chem. 12): 265.- -- 67
=.
m i l 212. Garcia F.M., Martinez, C.R., Torres, L.Q., Carrillo, H.R., Rivera, J .F. , Iskander, F Y. " Elemental Composition of Some
- Mineral Mines of Zacatecas State" The VIII Symposium in Nuclear Chemistry.. Radio Chemistry and Radiation Chemistry",.luly 1990.
213. F.Y. Iskander and A. Ankar, (1987). " Minor and Trace elements in two faba bean meals." frnahrunc Nutritio; 31:7$G. , 214 D.E. Klein, " Nuclear Engineering Teaching Laboratory at The University of Texas at Austin", invited paper, Trans Am Nucl. E m ., 11, 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 Datt, 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), t 217. Iskander, F.Y. " Determination of Iodine value by:Br/INAA." (Abstract). The 102nd Annual meeting and exhibition of the Association of Official Analytical Chemists. Palm Beach, Florida, Aug.1988. Paper J336, 218. Behardi . .F. , Iskander, F.Y. , Freeland Graves , J . , Line, P.H. and Bauer, T. (1988). Mineral Balance in young men fed a' constant conventional diet. (Abstract). Federation of-American Societies of Experimental Biologists,;Las Vegas, Nevada May 1988, 219. N.E. Hertel, C.G. Pollard, and B.A.;Ganthner,- "Tranportation-Worker Exposure from the Transport of BRC Radwaste," Proceedings of the Waste Management '88 Symposium. Tuscon, February 28 March-3, 1988. 220. R.S.LHartic; .N.E. Hertel, and J.W. Davidson,5" Neutron Multiplication in Beryllium," Fusion Ener.-Des. 1Q, 133 1989, 221. N.E. Hertel, R.S. Hartley, and J,W. Davidson.1 " Measured land ' Calculated Neutron Leakage Multiplication .for Beryllium Shells," Trans. Jun. Nucl . Soc. 56 123 (1988). 222, N.E. Hertel, J.W, Davidson, and'R.S. Hartley. " Analysis of the,. Texas Beryllium Neutron Leakage Multiplication Experiments,"1 , Eighth Topical Meeting on the Technology-of Fusion Energy, Salt ] Lake City, Utah, October. 9-13,.1988.. 223. T. Parish, R. Carrera, and'N.E. Hertel, " Nuclear Radiation- l Analysis in the IGNITEX! Ignition-Experiment," Eighth. Topical - 3 Meeting on the Technology.of Fusion Energy,1 Salt Lake City,- October- 9 13, 1988. - - - . l
, . - , . w. x.--.-- --. .a....~ .. . a . ,_ - - - . .
s 224. R. Carrera, M. Driga, J.H. Cully, N.E. Hertel, J. Hopf, K.T. Hsieh, E. Mc.italvo, C. Ordones, T. Parish, M.N. Rosenbluth W.A. Walls, W.C. Weldon, M. Worst., end H.H. Woodson, " Ignition . Experiment in a Single Turn Coil Tokamak, Eighth Topical Meeting on-the Technology of Fusion Energy, Salt Lake City, October 9- ; i . 13, 1988. 9 225. N.E. Hertel and J.C. Mcdonald, " Dose Equivalent and Phantoms in Conventional Calibration Practice," Trans. Am. Nucl. Soc..il, 219 (1988). 1 226. Klein, D.E. , Taborek, J.J. , and Fair, J.R. , "Ener6y Savings by use of Disk / Donut Baffling in Tubular Heat Exchangers," Tenth Annual Industrial Energy Technology Conference,; Houston, Texas, t 1988. 227. Hopf, J. , Carrera, R. , Klein, D. and Montalvo E. , " Plasma Physics Simulation of Alternative Modes of Operation in the ICNITEX Experiment," Thirtieth Annual. Meeting,' PLASMA: Physics Oct Nov 1988, 228. D. Coff and T.L. Bauer, " Scram Circuit Safety Analysis for The Universtiy of Texas TRICA Reactor". NETL Technical Report, July 19, 1988. 229. B.W. Wehring, " Tour of the Nuclear Engineering Teaching Lab 1at-Austin, Texas", 19PI TRTR Meeting, Raleigh, North Carolina Oct 4 6,-1989, i 230. Torres, L.Q., Martinez. C.R., Carrillo, H.R., Iskander, F.Y.,
" Mineral Tails Content Determination", The VIII Symposium on ,
Nuclear Chemistry, Radio Chemistry and Radiation Chemistry"; July 1990. 231, Martinez, C.R., Carrillo H.R.,-Torres, L Q., Iskander,-F.Y.,
" Impurities Silanos Samples Monitoring by_ Means of Neutron Activation Analysis" The VIII-Symposium on Nuclear Chemistry, Radio Chemistry and Radiation Chemistry" July .1990, 232. Carrillo,-H,R., Martinez. C.R..- Torres, L.Q., Hertel, N.E.,
Iskander, F.Y., "Zinalco and Zirca11oy.4 Nuclear Characterization" The VIII Symposium in Nuclear Chemistry, Radio chemistry and Radiation Chemistry" July 1990.- 233. T. Parish, R. Carrera, and N.E. Hertel. " Nuclear Radiation Analysis in the ICNETEX Ignition Experiment,": Fusion Tech. 11,
-459-(1989).
234. R. Carrera, M. Driga, .J - H. Cully, N.E. Hertel,, J. Hopf, K.T. Hsieh, E.- Montalvo, C.~.Ordonez, T. Parich -M.N. Rosenbluth, W.A.- l
.: Walls , W. F. Weldoa, M. Werst , and H.H. Woodson', " Ignition
= Experiment _in a Single Turn Coil Tokamak,": Fusion Tech'. 150, 402
_(1989).- - 69 l m
t 235. R, Carrera, M. Barrington, R. Bickerton, W.D. Booth, Y. Chen, J . Dong, M. Driga , S. Eways , C. Fu, J . Gully, G. Hallock, J .
. Helton, N. Hertel, L. Hively, J. Howell, K. Hsieh, J. Ling, G.
Miller, E. Montalvo, C. Ordonez, D. Palmrose, T. Parish, M. Rosenbluth, S. Tamor, D. Tesar, J. Van Dam, P. Varghese, A. Walls, W. Weldon, M. Werst, and H. Woodson, "IGNITEX Experiment," (abstract) 16th IEEE International Conference on Plasma Science, Buffalo, New York, May, 1989, 236. T. A. Parish, R. Carrera, R.J. Charbeneau, S. Fetter, and N.E. Hertel, " Preliminary Analysis of Raiological Hazards for the Fusion Igniticu Experiment IGNITEX," Proceedings of the 13th International Symposium on Fusion Engineering, Knoxvill, Tennessee, October 2 6, 1989. 237. G. A. Miller, N.E. Hertel, R. Carrera, and T. A. Parish,
" Multidimensional Radiation Analysis for the Fusion Ignition Experiment IGNITEX," Proceedin&s of the 13th International Symposium on Fusion Engineering, Knoxville, Tennessee, October 2 6, 1989.
238. D. Palmrose, T. Parish, R. Carrera, H. Hertel, and G. Miller,
" Nuclear Radiation Analysis of the IGNITEX Experiment,"
(abstract) 16th IEEE International Conference on Plasma Science, Buffalo, New York, May, 1989, 239. N.E. Hertel, C,0, Pollard, and J. Haldonado, " Environmental Monitoring at che Potential Low Level Radioactive Waste Disposal Site in Texas," (abstract), 1989 Health Physics Society Annual Meeting, Albuquerque, New Mexico, Health Physics $6, Suppl. 1, S68 (1989). 240. N.E. Hortel, "New Dose Equivalent Quantities: Possible Directions for Neutron Dosimetry," 1989 Health Physics Society Annual Meeting, Albuquerque, New Mexico. Invited Talk in Special Session on the Implementation of the ICRU 39 Dose Equivalent Quantities. 241. D.E. Palmrose, T.A. Parish, R. Carrera, N.E. Hortel, "The Impact of Dose Rates Due to Decay Photons on the Design of the IGNITEX Device," Proceedings of the 13th Internt1'Symp on Fusion Engr., Knoxville, Tennessee, October 2 6, 1989. 242. C,R. Martinez, H.R. Carrillo, L.Q. Torres, N.E, Hertel, F.Y. Iskander (1990) "Zinalco and Zircalloy-4 Nuclear Characterization" Announcer 20 (2):63. 243. R.C. Woodard, T.L. Bauer, B.V. Wehring, " Methodology for. Development of Health Physics Proceduresuat Research Reactors in Agreement States", Implementation of Current NCRP and ICRP Guidance, 24th Midyear Topical Meeting of the Health Physics Society, Rallegh, N.C., January 21-25, 19911 .. 70
a _ _ ,au- .-m% J .mgu._.:: -- == A-.h ;- _ 244. B.W. Wehring, " Direct Physical Measurements of Independent Fission Yields at a 1 KW Research Reactor". ANS Transactions , Vol. 61 (1990). 245. N.D. Poor and N.E. Hertel, " A Comparison of Low Level . Radioactive Waste Storage and Disposal Alternatives" (abstract), Health Physics Society Annual Meeting, Chicago, Illinois, (1985). 246. N.E. Hertel, R.H. Johnson, J .J. Dorning, and B.V. Wehring,
" Transmission of Fast Neutrons through an Iron Sphere". Fusion Tech. 2, 345 (1986).
247. A.D. Faines and N.E. HErtel, " Calibration of Bonner Spheres at The University of Texas" (abstract), Health Physics Society Annual Maeting. Pittsbur6 h, Pennsylvania. Health Physics 50, Suppl. 1, 522 (1986). 248. N.D. Poor and N.E. Hertel, "How to Evaluate a Low. Level Radioactive Waste Disposal Technology", (abstract), Health Physics Society Annual Meeting, Pittsburgh, Pennsylvania, Health Physics 50, Suppl. 1, 568 (1986). 249. H.W. Bryant, N.E. Hertel, T.L. Bauer, and J .W. Jagger,
" Dosimetry in the Vicinity of IEXI", Proceedings of the 20th e Midyear Symposium of the Health Physics Society, Health Physics of Radiation Generatint Machines, Reno, Nevada, February 1987, CONF-8602106, 250. R.S. Hertley and H.E. Hertel, " Neutron Multiplication in Beryllium," Trans. Am. Nuc. Soc. 54, 126 (1987).
251. N.E. Hertel, R.S. Hartley, T.L. Bauer, J.L. Horton, and V. A. Otto, " Neutron Measurements in the Vicinity of Medical Electron Accelerators," Proceedings of the 20th Midyear Symposium of the Hedith Phycies Society, Hen 1th Physics of Radiation Generatine Machines, Reno, Nevada, February 1987, CONF 8602106. 252. N.E. Hertel, R.S. Hartley, and A.D. Caines, " Determining Calibration Factors for Bonner Spheres," Trans. Am. Nucl. Soc., 11, 220 (1987) 253. N.E. Hertel, C.C. Pollard, and B.A. Cartner, " Transportation Worker Exposure from the Transport of BRC Radwaste," Proceedings of the Waste Mananement "B8 Svenosium. Tucson, Arizona, February. 28 March 3, 1988. , 254. N.E. Hertel, R.S. Hartley, and J.W. Davidson, " Measured and Calculated Neutron Leakage Multiplication for Beyllium Shells," Trans. Am Nucl. Soc. 56, 123 (1988). 255. N.E. Hertel and J.C. Mcdonald, " Dose Equivalent and Phantoms in Conventional Calibration Practice," Trans. Am. Nucl. Soc. 57 219 - (1988)' . 71
256. R.S. Hartley, N.E. Hertel, and J.W. Davidson, " Neutron Multiplication in Berylliwa," Fusion Ener. Des. 10, 133 (1989). 257. T. Parish, R. Carrera, and N.C. Hertel, " Nuclear Radiation Analysis in the IGNITEX Ignition Experiment " Fusion Tech.15,
- 459 (1989).
258. R. Carrera, M. Driga, J.H. Gully, N.E. Hertel, J. Hopf, K.T. Hsieh, E. Montalvo, C, Ordonez, T. Parish, M,N, Rosenbluth, W.A. Walls , W . F. Weldon, M. Wers t , and H.H. Woodson, " Ignition Experiment in a Single Turn Coil Tokamak," Fusion Tech. 15, 402 (1989). 259 N.E. Hertel, C.G. Pollard, and J. Maldonado, " Environmental Monitoring at the Potential Low 1.evel Radioactive Waste Disposal Site in Texas," (abstract), 1989 Health Physics Society Annual Meeting Albuquerque, New Mexico, Health Physics 56, Suppl. 1, S68 (1989), 260, N.E. Hertel, "New Dose Equivalent Quantities: Possible Directions for Neutron Dosimetry," 1989 Health Physics Society Annual Meeting, Albuquerque, New Mexico, Invited Talk in Special Session on the Implementation of the ICRU 39 Dose Equivalent Quantities. 261. D.E. Palmrose, T.A. Parish, R. Carrera, and N.E. Hertel, "The impact of Dose Rates Due-to Decay Photons on the Design of the IGNITEX Device," Proceedincs of the 13th International Symoosium on Fusion Engineering, Knoxville, Tennessee, October 2 6', 1989. 262. T. A. Parish, B. Shofolu, R.- Carrera, N. Hertel, R, Charbeneary, D. Klein, and S. Fetter, " Preliminary Analysis of Radiological Hazards for the Fusion Ignition Experiment IGNITEX," Proceedings 21_the 13th International Symposium on Fusion Engineerinc, t Knoxville, Tennessee, October 2 6, 1989. 263. G.A. Miller, N.E. Hertel, R. Carrera, and T.A, Parish, "Hultidimensional Radiation Analysis for the Fusion Ignition Experiment IGNITEX," Proceedincs of the 13th International Symposium on Fusion Entineering, Knoxville, Tennessee, October 2 6, 1989. 264. N.E. Hertel and J.C. Mcdonald, "Calcualtions of Anisotropy l Factors and Dose Equivalents for-Unmoderated Cf-252 Sources," j Radiation Protection Dosimetry 32, 77 (1990). ; 265. R.J. Charbeneau, N.E. Hertel, M. Becker and C,0. Pollard,"
- . Performance Assessment of the Potential Low Level Radioactive Waste Disposal Site in Texas," Proceedings of the Waste Management '90 Symnosium, Tucson, Arizona, February 25 March 1, 1990.
72
r 266. R.J. Charbeneau, N.E. Hertel, M. Becker, and C.C. Pollard, -
" Texas Low Level Radioactive Waste Disposal Site Performance l
Assessment,' (abstract) 1990 Health Thysics Society Annual Meeting, Anaheim, Californai, June '24 28, 1990, Health Physics 1 11 Suppl. 1, S35 ('1990). 267. J. Smathers, N. Hertel, and L.- Meyers, " Benchmarking Shield Calculations for 46 MeV (p,Be) Neutron sources with Bonner Sphere Measurements," (abstract) 1990 Health Physics Society. Annual Meeting, Ansheim, California,' June 24 28, 1990, Health Ehysics f8 Su9pl. 1, S$3 (1990). 268. J. Smathers, N. Hertel, and L. Meyers, "Bonner Sphere Neutron Measurements of the= Environments _ Created by a 46 MeV (p, Be) Neutron Therary Facility," (abstract) 1990-Health Physics Society Annual Meeting, Anaheim, California,-June 24 28, 1990, llealth Physics 58 Suppl. 1, S$3 (1990) 269. Y. Watanabe, T.A. Parish, V.D. Booth, R. Carrera, B. Shofolu, and N,E. Hertel, " Evaluation of Radiation Streaming Effects in A Single Turn. Ignition Tokamak," accepted as a technical paper to the Ninth Topical Meeting on the Technology of-Fusion Energy, Oak Brook, Illimois, October, 1990. 270. C.G. Pollard, R.J. Charbeneayuy, N E. Hertel, and M. Becker," Biotic Pathways for a Texas Low Level Radioactive Was?- , Disposal Facility," Trans-. Am. Nucl.' Soc. 62, 468 (1990), e 271. B. Nabelssi, N.E. Hertel, R.J. Charbeneau, and C.C. Pollard,
" Atmospheric Dispersion Doses for a. Texas Low Level Radioactive Waste Disposal Site," Trans~. Am. Nucl. Soc. 62, 469=(1990).
272. N. E. Hertel, V.G. - Lovely , J .R. -Jupena ,-. and C.C. ' Pollard, .
"Modelling a Roll Off Container Transportation Worker Dose Scenario for BRC Radwaste," Trans. Am; Nucl. Soc. 62, 460 (1990).
273. N.E. Hertel and J.C, Mcdonald, " Methods for the ' Calibration of Photon Personnel Dosemeters-in Terms of the Ambient Dose Equivalent," Radiation Protection Dosimetry-(in. press). 274. N.E. Hertel and J.C. Mcdonald, " Calculated Dosimetric Quantities for D20 Moderated Cf 252 Sources," Radiation Protection Dosimetry (in press), i c 275. J.B. Smathers, N.E. Hertel, and -L. Myers, " Comparison of Bonner. a ' Sphere Measurements with Shield Calculations for 46 MeV (p, Be)
. . Neutron Sources.". undergoing revision for publication in'the Health Physics Journal as a technica11 paper.
276. N.E. ~ Hertel and J.C- Mcdonald, " Methods for the Calibration of-Neutron Personnel Dosemetersi in Terms offthe: Ambient Dose Equivalent," accepted for publication as a ; technical papers in - Radiation Protection Dosimetry. l < 73
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