ML20083N779
| ML20083N779 | |
| Person / Time | |
|---|---|
| Site: | 05000192 |
| Issue date: | 12/31/1983 |
| From: | Bauer T, Klein D TEXAS, UNIV. OF, AUSTIN, TX |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| NUDOCS 8404190286 | |
| Download: ML20083N779 (64) | |
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i NUCLEAR REACT.OR LABORATORY TECHNICAL REPORT THE UNIVERSITY OF TEXAS COLLEGEOFENGINEERING DEPARTMENT OF MECHANICAL ENGINEERING ., C
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1983 ANNUAL REPORT
" of The University of Texas at Austin Nuclear Engineering Teaching Laboratory January 1,.1983 - December 31, 1983 D. E. Klein, Director T. L. Bauer, Supervisor
'~ Taylor Hall 104-512/471-5136 January 1984
TABLE OF CONTE!TrS Page List of Figures . . . . . . . . . . . . . . . . . . . . . . . 11 List of Tables . . . . . . . . . . . . . . . . . . . . . . . iii I. Introduction. . . . . . . . . . . . . . . . . . . . . . . . . 1 II. Laboratory Administration. . . . . . . . . . . . . . . . . . 4 A. Organization B. Personnel C. Standing Commit. tees D. Report to the College of Engineering III. Laboratory Development. . . . . . . . . . . . . . . . . . . . 9 A. Organization B. Nuclear Engineering Tesching Laboratory C. Neutron Activation Analysis Facilities D. Nuclear Radiation Laboratory IV. Facility Operations Swnmary. . . . . . . . . . . . . . . . . . 12
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A. Operating Experience B. Reactor Shutdowns C. Utilization D. Maintenance j E. Facility Changes F. Radiation Exposures l G. Area Radiation Surveys
!! Radioactive Effluents V. Laboratory Inspections. . . . . . . . . . . . . . . .-. . . . 28 A. NRC Inspection February 28 - March 4,1983 B. NRC Inspection March 10-11, 1983 '
C. TDH Inspection February 7-8, 1983 VI. Public Service Activities. . . . . . . . . . . . . . . . . . . 29 A. Summer High School Science Teacher Symposium B. Lectures and Presentations C. Reactor Facility Tours-VII. Research Activities. . . . . . . . . . . . . . . . . . . . . . 30 9
VIII. Publications from the Nuclear Engineering Teaching Laboratory . . . . . . . .-. . . . . .. . . . . . . . . . . 40 l
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3 List of Figures Page Fic_ure No.
1 Floor Plan of Nuclear 2 Reactor Laboratory 2 Floor Plan of the Nuclear 3 Engineering Teaching Laboratory 3 Organization Chart of the 5 Nuclear Engineering Teaching Laboratory 4 Comparison Burnup vs Year 16 5 Comparison of Number of Samples 17 Irradiated vs Year 6 Taylor Hall Environmental 24
- - Survey Locations t
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List of Tables Table No. EAg2
- 1. Facility Personnel 6
- 2. Standing Committees
- 3. Courses Utilizing NETL 10 Facilities
- 4. Reactor Scrams 13
- 5. Comparison.of Yearly 13 Inadvertent Scrams
- 6. NETL Performance Data 1983 14
- 7. Comparison of Previous 15 Utilization Data
- 8. ' Summary of Radiation 19 Exposure 9.. Radiation. Exposure Analysis 20
- 10. ' Laboratory Radiation Levels -21
- 11. Laboratory Contamination 22 Levels
- 12. Environmental Surveys 23 13 . - Monthly Summary of Gaseous 26-Waste Discharges
.14. Annual Summary of LSolid Waste 27 Disposal
- 15. . Research Funding 31
'iii
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. I. INTRODUCTION
- This report has been prepared by the staff of the Nuclear Engineering Teaching Laboratory (NETL), The Uni-versity of Texas at Austin, to satisfy the reporting re-quirements of the.U.S. Department of Energy Contract Number At-(40-1)-3919 and 10 CFR 50.59. The report covers the period from January 1, 1983 to December 31, 1983.
The Nuclear Engineering Teaching Laboratory (NETL) is a part of the Mechanical Engineering Department in the College of Engineering at The University of Texas at Austin. The program's major equipment consists of a 250 kW TRIGA Mark I reactor operated in pulsing and steady state l
. modes. The reactor laboratory and adjacent laboratory i areas are shown in Figures 1 and 2. Other equipment
- - maintained by the NETL program includes two Cockcroft-Walton 14 MeV neutron generators, a Lockheed Aerojet subcritical assembly, and a 1150 curie Co-60 irradiator.
} Isotopic neutron sources available include three 2
californium-252 sources and six plutonium-beryllium sources. A wide array of detectors and electronic F~*
. equipment are available to provide measurement and analysis-l capability of laboratory produced or maintained radiation
. sources.
Changes in the NETL program occur as a continuing response to achieve effective operation of various NETL projects land. program development. . During the past year L (the most significant event was the renewal of operation license R-92-for the-period February 9, 1980 to February-
- 9, 1990. -A request
- is'pending for an extension of the license period forfan. additional-ten (10) years.
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1 II. LABORATORY ADMINISTRATION A. Organization The present organizational chart of the NETL program is presented in Figure 3. Budgeted NETL staff funding is pro-vided for a Supervisor / Assistant Director, technician /oper-ator, radiochemist, operator, and secretary. Budget sup-port is divided into full time positions for supervisor, technician and radiochemist; half time for an operator; and quarter time for a secretary.
B. Personnel Personnel associated with the laboratory consist of NETL staff, faculty, students, and certain other university personnel. The personnel involved in the NETL program during the past year are summarized in Table I.
C. Standing committees
- 1. Reactor Committee The Reactor Committee convened and reviewed the activities occurring at the facility during each calendar quarter of this reporting period 7 Committee meeting dates were April 12, July 13, October 11 and January 17. Committee composition is shown in Table 2.
- 2. Radiation Safety Committee The Radiation Safety Committee convened and re-viewed radiological safety priorities at the univer-sity during this reporting. period. Committee meeting dates were April.18 and November.16. Committee comp-osition'is shown in Table 2.
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Dean of Engineering Chairman M. E. Department Director
' Nuclear Engineering v
' Teaching Laboratory s
% Reactor Radiation-Safety / Coninittee s
Committee -
Reactor Supervisor '
Reactor Instructors Technicians Experimenters LINE OF RESPONSIBILITY CONSULTATION AND VET 0 POWER-
- Fig. 3 . ORGANIZATIONAL CHART o
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Table I Facility Personnel Staff and Faculty Director D.E. Klein Assistant Director / Supervisor T.L. Bauer Nuclear Technical Specialist M.G. Krause Nuclear Technical Specialist N.A. Povio !
Radiochemist F.Y. Iskander Assistant Professor N.E. Hertel Administrative Secretary M.G. Morrison Support Personnel Adjunct Associate Professor D.G. Anderson Safety Officer H.W. Bryant Research Scientist J.W. Davidson ,
. Graduate Assistants
. M. Ally A. Gaines A. Patterson- '
- Hine T. Sanders ,
B'. Kolda R. Savage E. Ibrahim G. Polansky L. Grater Y. Kunimoto Student Assistants J. Evans-T. Tran i
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Table 2 Standing Committees Reactor Committee' Chairperson: B. L. Marcus l
Member: N. E. Hertel Member: D. E. Klein Member: J. O. Ledbetter Student Member: R. D. Manteufel Ex officio member: T. L.-Bauer Ex officio member: H. W. Bryant Ex officio member: E. F. Gloyna Radiation Safetv_ Committee.
Chairperson: P. J. Riley Member: F. H. Bronson Member:- L. O. Morgan Member: D. E. Klein Member: R. L. Shipman Member: K. J. Caskey Ex officio member: H. W. Bryant Ex. officio member: P. T. Flawn E
7
1 D. Report to the College of Engineering
. Each year the Reactor Committee provides a report to the Dean of the College of Engineering describing activi-ties of the committee and a review or assessment of the operation of specific portions of the NETL program con-cerning the reactor and other radiation producing equip-ment. Harris Marcus, Reactor Committee Chairman, summa-rized the activities during this period saying, "The past year again has been an active year for the Nuclear Reactor Teaching Laboratory, a continuing conscientious effort to improve the facility has been effectively carried out."
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1 III. LABORATORY DEVELOPMENT A. Oraanization Dr. Dale E. Klein continued as the Director and Dr.
Thomas L. Bauer continued as Reactor Supervisor during the past year. Technical and secretarial personnel also re-mained unchanged. Dr. Felib Iskander filled the vacant radiochemist position. Key faculty and university support personnel remained-unchanged.
B. Nuclear Engineering Teaching Laboratory The Nuclear Engineering Teaching Laboratory is part of the Nuclear Engienering Program at The University of Texas.
The Nuclear Engineering Teaching Laboratory's central feature is a Mark I TRIGA thermal fission reactor. Origin-ally: licensed by the Atomic Energy Commission to operate at 10 KW in 1963, the nuclear reactor and the associated labor-atory 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 TRIGA reactor to operate at a steady state power level of 250 kW which increased experimental capabilities.
Other radiation' producing devices maintained by the
. Laboratory are a thousand curie Co-60 irradiator, vert-ical neutron beam tube, subcritical assembly, industrial x-ray source, 14 MeV neutron generator, and several isotopic neutron sources. Different typeslof radiation detection devices provide the capacity to monitor or.
analyze the various radiation ~ sources.
One of the functions of the nuclear reactor.and its associated equipment has been1to teach and demonstrate the fundamentals of reactor operation. Several organized classes routinely utilize the reactor facility. Numerous other-classes,_ organizations and groups schedule tours or demonstrations of the reactor facility. Courses utilizing-the reactor and associated facilities are listed in Table-
- 3. Approximately 1,700 persons were : admitted into- the reactor facility duringLthe past year.~
The.use, operation, regt ation, security,-and moni-
.- toring of_the Nuclear: Engineering Teaching Laboratory is
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controlled by the United States-Nuclear Regulatory Commis-sion, the Nuclear Reactor' Committee of The University.of 1 Texas, the DirectorEof.the Nuclear Engineering Teaching !
Laboratory,Lthe' Radiation Safety, Committee and the Texas !
Department of Health Radiation Control Board.
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Table 3 Courses Utilizing the Reactor and Associated Facilities
. Mechanical Engineering Department Course Number Course Description ME 361F Introductory Nuclear Laboratory -
studies in radioactive decay, acti-vation, detection and measurement.
ME 361G Reactor Operations - studies in nuclear reactor parameters, instru-mentation characteristics and regu-lation.
ME 389R Nuclear Engineering Laboratory -
studies for graduate students in nuclear methods in measurement and analysis.
ME S389R Special projects course for nuclear engineering laboratory sutdies as a summer course for foreign students.
ME 377K Projects in Mechanical Engineering -
individual study and experiment projects for undergraduates.
lME 397 Current Studies in Engineering -
special projects course for grad-uate study of selected topics.
-Additional' Courses in Other Departments GEO_388L Isotope Geology - graduate course CH 376K- Advanced Analytical Chemistry -
senior level course in instrumental and analytical methods..
CE 390L Environmental ~ Analysis graduate course PHR 37.0K Nuclear Pharmacy - senior level.
. course in measurement and analysis methods _with nuclear pharmaceuticals.
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l C. Neutron Activation Analysis Facilities l
The Nuclear Analytical Laboratory has provided support for individual projects ranging from student laboratory sup-port for advanced classes in chemistry, zoology, physics, and engineering to investigative projects in environmental monitoring. Scientific articles based upon the results of sponsored and unsponsored research by this laboratory have been published or accepted for publication in several jour-nals and proceedings, and have been presented at confer-ences at the state, national and international level.
Radiation detection systems available include gamma ray spectroscopy HpGe detection acquisition and analysis system, multi sample -
proportional counter, NaI detectors, Si(Li) detector, neutron detectors and associated electronic modules to accomplish several types of standard nuclear measurements. An important function of the laboratory is to support various research projects with the neutron activation analysis method and other re-lated nuclear radiation research techniques.
D. Nuclear Radiation Laboratory The Nuclear Radiation Laboratory is utilized by the students and staff of the Nuclear Engineering Program at
. The University of Texas at Aust n. The laboratory was moved to the Engineering Science Building in the summer of 1983 since the building housing the laboratory at Balcones Research Center is to be demolished as part of the Balcones Research Center development program. The main feature of the laboratory is a 14 MeV Texas Nuclear neutron generator. Three californium-252 neutron sources are also available-for use. The facility, with installed neutron shielding, provides an area where students and staff can perform experiments utilizing not only the high energy neutrons from the neutron generator but. fission spectrum neutrons from Cf252 .In addition to the neutron generator and the californium sources, other smaller radioactive sources are also used within the confines of the Nuclear Radiation Laboratory.
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j' f-IV. Facility Operations Summary A. Operating Experience 1-Renewal of operating license R-92 was received ef-
. fective for the period July 29, 1983 through February 9, 1990. A request for license term extension is pending.
During the fall of 1983, the University Broad Radioactive Material License issued by the Texas Department of Health j was renewed, with expiration date June 30, 1988. The facility emergency plan was rewritten and resubmitted to the NRC for' review. Established operating procedures i and other required procedures remained unchanged. A
- study has been initiated to determine economic and license i- feasibility of continued operation of the NETL facility in response.to possible reallocation of current site functions for alternate university program plans.
L Licensed activities were performed by three persons with Senior Operator Permits, T.L. Bauer, M.G. Krause and N.A. Povio. Most operating. activities were in support of nuclear engineering and reactor operations, research and education or demonstrations. .No new experiments were proposed-or approved. Excluding operation for demon-stration, instruction or routine _ surveillance, the major experiment performed was neutron activation to support
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various research activities. Some operation occurred for
. radioisotope production.- Most maintenance was routine with.
.two conditions assessed as unacceptable.and. subsequently
- modified. . The first modification was the installation i of,new. fuel temperature measurement channels. The
'second condition was' inconsistent performance of the.
uncompensated ionization chamber..
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- B. ReactorLShutdowns:
[Reactot shutdowns ..(scrams)' occuring during the 7
reporting. period are summarized in Table 4,~categor-ized according to the type of initiating event. Table 5 compares thesnumber of. inadvertent 1 shutdowns during:
this reporting tperiod-to previous reporting: periods.
C. Utilization
- Reactor utilization data'for_thisEreporting:periodLis.
< s summarized in Table 6.. A summary of reactor utilization
- 'since~ initial criticality is.shown in Table"7. Bar graphs comparing-annual burnup;and. quantities of: samples
- - ? irradiated since initial-criticality areishown in Figures 4 and15.
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TABLE 4 e
REACTOR SCRAMS s
Intentional -- 6
' Operator Error -- 1 Instrument Error -- 5 Power Outage -- 0-Safety. '-- 0-Total -- 12 t
'- TABLE 5-COMPARISON OF YEARLY INADVERTANT SCRAMS
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'63' '64 . '65 '66 67 '68 '69 70- - '71.
'72 - '73'
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'74. -'75 ' 7'6 ~ :
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TABLE 6 NUCLEAR ENGINEERING TEAOIING LABORATORY PERFORMANCE DATA, 1983 Total Hours Total Number of Reactor In Burn-up Samples Operation * (kW-hrs) Irradiated First Quarter 1983 40.4 1126 37
'Second Quarter *
. 1983 56.0 5399 52 Third Vuarter-1983 70.0 0143 184 Fourth Quarter 1983 93.8 9360 204 TOTAL 260.2 24028 477 (1.0 MWD)
- Time Reactor Key on; ' includes certain experimental setup time, maintenance, etc.
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TABLE 7 s.
COMPARISON OF PREVIOUS UTILIZATION DATA Number of Hours Reactor Burn-up Samples In Operation * (kW-hrs) Irradiated Year
'1965-66** 104.5 251 63
'1966-67 150.0 595 202 1967-68*** '342.6 28,168 2449 1968 260.8 49,985 1452 1969-70 222.0 36,477_ 1640 1970-71 262.5' 53,912 2990
'1971-72 222.8 48,389 1946
'1973 318.6'. 45,794 1347 1974 226.1 27,641' 778 1975- 207.0 20,450 -363 1976 135.7 11,312 468 139.3 7,509 164
.1977-1978 171.9- 26,870 178 '
1979- _311.6_ ~72,616. 1568:
.1980 184.1. 11,760 150-1981' 258.5 18,165- 330 1982 247.6 - 16,~150 294
.1983 260.2 24,028- 477 TorAL ~ 4025.6 48,084; 16,859 (20. 19fD) - . ,,
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- Includes experimental setup time, maintenance, etc.
- 1965 was the firstiyear the utilization data' was maintained.
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- Reactor upgraded from 10 to 250.kW during'this'aca'demic' year..
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- 76 "77 *78 ' 79'80'81 '82 ' 83 YEAR' Fig. 4 TC7fAL BURNUP PER YEAR 16 9
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< D. Maintenance
.- During this reporting period maintenance consisted primarily_of routine repair and adjustment. The only non-routine maintenance performed was the replacement of both fuel temperature measuring channels described .
in the facility changes section.
, E. Facility Changes 1
- 1. The wooden structure used to separate the t area inside the reactor. laboratory designated tne radio-chemical room was removed. The benefits of this action
' included the generation'of more open work space, the re-moval of an aesthetically unpleasant structure, and a sub- s stantial decrease in the amount of combustible material in the laboratory.
No unreviewed safety questions are presented by removal-
- of the structure.
.2. Relay and loop resistance problems with fuel temp-erature measurement channels initiated redesign and replace--
ment of the channels.- Solid-state temperatu m contr.ollers *
(0-800*C) replaced the loop resistance metet (0-600'C).
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' Designed for Cr-Al thermocouples, the channels provided Ai more reliable' measurements and failure' indication-despite- "
' the additional circuit l complexity.
No unreviewed safety questions are presented bj o ,
- - t 1 1 the' temperature channel modifications. -Substantial improve-
- ment of temperature measurement. accuracy'and indication'of. '
failure conditions are.possible_with the modifications.
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- Radiation Exposures-F. ,
m A summary of radiation exposures:during this repdrting . s N period'to. facility personnel,_-students',.and visitors is n;* 1' Y
shown in Table 8.. The average-exposure per individual ?.
l and. the greatest exposure -per: individual- for :each group 4:N ;}&
^ 1 is summarized.in' Table 9. No' exposures (in excess'of the s.
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Area Radiation' Surveys %N
/An annual' summary.oflthe normalJradiation levels' mea-
' sured in the laboratory is~shown in Table 10. The_results-
-,of. routine . surface 'and pool: water: contamination surveys . 1
. .-. Hare summarized'in Table 11.- Environmental surveys;per- 4 .
formed.outside the: laboratory are;summarimod in Table 112..
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' -' SUM *4A'RY OF RADIATION EXPOSURE N:
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Range lof Exposure Number of Individuals
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Non-measurable exposure
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-hard Bi 20; mrem. fast ;n, or 10 : mrem therma 1 n Jduring each reporting period.-
4 Visitors Pocket ' dosimeter exposures at or below 10 mrem..
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. TABLE 9 RADIATION EXPOSURE ANALYSIS Average Radiation Greatest Radiation Exposure Per Individual Exposure Per Individual Group (mrem) (mrem)
Staff _< 10 20 Students . < 10 < 10(
Visitors < 10 < 10 *
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LABORATORY RADIATION LEVELS location Average (mR/hr) (1) Maximum (mR/h r) (2 )
-- (3) --
(3)
Wall Near Control Panel
-/ Wall Near Water Purification -2 System 1 x 10 0.8 3 -
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Ceiling Directly Above Reactor -2 g,- Pool 8 x 10 7.0
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. (1) Determined using results of fixed film badge monitors averaged over one year.
- (2) Annual f[lm measured exposure divided by effective annual reactor full power.
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TABLE 11 LABORATORY CONTAMINATION LEVELS Location Average Maximum Floor < 50 dpm < 100 dpm Work Surfaces < 50 dpm < 200 dpm
. Pool Water (1) -- (2) < 650 pCi/1 (1) Measured when reactor not operating (2) Not distinguishable from background
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i TABLE 12 ENVIRONiiENTAL SURVEYS I
Location Average (mrem /hr) Maximum (mrem /hr) 1 0.01 0.01 2 0.01 0.01 3 0.01 0.03 4 0.01 0.01 0
5 0.01 0.01 6 0.01 0.01 (3) 135 pCi/l Waller Creek --
(1) Monitoring locations shown in Figure 6. ,
(2) Water sample from stream flowing through campus approximately 0.25 miles from reactor facility.
(3) Measurements at'or below background.
o w
to 23 f-5 L :: b
1 6
1 127 "
5 e ~-
Nuclear Activation - huclear Analysis Laboratory Teaching '
^ Laboratory 2 12 5 -
, 12 9 .
t .T ..
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1318 Air Cond.
Dist. Room "
R E ACTOR LABORATORY --
f ------- 1 131 ,,
4 ,_
, Vestibule 14 w
Control T .
Room !
- " l31 A "
' sum m :T --
l .3 .
[33_.- 104
~
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i' 135 8 135 A -- --
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Fig. 6 TAYLOR HALL E!NIRO!DiENTAL I SURVEY IDCATIONS 24 l
H. Radioactive Effluents
~
- 1. Liquid Waste No liquid radioactive waste was discharged during the reporting period.
- 2. Gaseous Wastes Gaseous discharge during the reporting period is limited to leakage of Ar 41 from the reactor laboratory.
The total estimated amount of radioactivity released41 was calculated based on experimental equilibrium Ar concentration measurements (4 x 10-8 Ci/m3) adjusted by the number of full power hours operated during the period. Although air leakage from the laboratory is restricted on effective air change rate of two per hour - (.37 m3/ sec) is assumed with dilution at the re-lease point (.14 sec/m3). A summary of the calculated radioactive gaseous discharges during the reporting period is presented in Table 13.
- 3. Solid Waste The activity and amounts of solid waste discharged during the reporting period are summarized in Table
- 14. All solid waste materials were packaged and shipped, along with radioactive waste generated in other departments, by the University Safety Office.
4 O
' 25 -
- y . . . ,
TABLE 13 MONTHLY
SUMMARY
OF GASEQUS WASTE _ DISCHARGES -
1.__...-
Date of. . Total - , Total Estimated Average Percent of the ~ Total Estimated Average Estimated Average Percent of
' Din harge- Estimated , Estimated .. Atmospheric. Applicable Concentration Concentration of Quantity of NPC If the (Month & Vear) Radioactivity Quantity of . Diluted MPC for Diluted Radioactivity in of Radioactive Other Significant Estimated Released Argon-41 Concentration of Concentration Particulate Fom Particulates Radionuclides in Release was Releasedill Argon-41 at 'of Argon-41 at with Half-Life ' Released With Discharge if' >20% of the pCi Point of Release point of. Release >s Days (2) Naif.tife ,8 Days >20% of the Appitcabie pCi (Curies) (Curies) Applicable MpC MPC (pC1/cc) (1) (pCf/cc) an- -0 0 0' 0 None Not Applicable Not Applicable Not Applicable
- feb '87- 4.7-x 10-12' 1.1 x 10-2 None Not Applicable Not Applicable Not Applicable
,. _ ' 87 -
, ,o Mar. ._._158- 158 8.5 x 10 2.'l x 10-2 None Not Applicable Not Applicable Not Applicable Apr 4.lx 10-II~ 1.0 x 10~l Not Applicable
-757 757- None Not Applicable Not Applicable
_May, 163 163 8.7 x 10-12 2.1 x 10 None Not Applicable Not Applicable Not Applica June ~ 256L 256 ' l . 4 . x 10- U - '3.4 x 10-2 None Not Applicable Not Applicable Not Applicab
_.dkly' '430 ~ 430 2.3 x 10
~II 5.8 x 10-2 ' None Not Appiicanie not appiicani, not appi,cani, LAug- 267- 267 1.4 x 10~U 3.6 x 10-2 None Not Applicable Not Applicable Not Applicable Sept 1072 ~ 1072 '5.7 x 10~U l .4 x 10"l None Not Applicable Not Applicable Not Applicable Oct- -419~ 419- 2.2 x .10-ll - 5.6 x 10-2 None Not Applicable Not Applicable Not Applicable
, Nov 985 985 - 5.3' x 10- 3 ' 1.3 x 10~l None Not Applicable Not Applicable Not Applicable Dec :631 .631~ 3.4 x 10-II 8.5 x 10-2 None Not Applicable Not Applicable Not Applicable ANNUAL VALUE '5225 5225 2.3 x 10-U 5.8 x 10-2 3,,, ,,, ,ppi,,,,,,
,,, , ,,c,,,, ,,, ,p ,,c,,,,
I'
\; '
I' p
26 l.
I l'
1 L
TABLE 14 ANNUAL
SUMMARY
OF SOLID WASTE DISPOSAL Activity Volume Shipment Date 83pCi 8.5 ft April 26, 1983 8Ci 10.1 ft May 31, 1983 7.0 ft December 21, 1983 17pCi (1) All shipments made to Isotex in Triendswood, Texas.
(2) Majority of activity H target for neutret generator.
e 27 k
o y
t 4.
V. Laboratory Inspections
+ A. NRC Inspection February 28 - March 4, 1983 The inspection reviewed program and activities f' designed to protect against industrial sabotage and to safeguard special nuclear material as required by NRC Licenses R-92 and SNM-180. The inspection consisted of selective examination of procedures and representative records, interviews with per-sonnel, and observations by the inspector. Within the scope of the inspection, no violations or de-viations were identified.
B. NRC Inspection March 10-11, 1983 The inspection consisted of a review of activities authorized by NRC Operating License R-92. Principal areas examined during the inspection included: 1) or-ganization, logs, records, and personnel changes;
- 2) audit and review; (3) procedures; 4) surveillance;
- 5) experiments; (6) environmental protection; 7) emer-gency planning; (8) radiation control; (9) operation re-qualification; (10) cobalt 60 irradiatorWithin storage; and these areas,
- (11) proposed building modification.
the inspection consisted of selective examination of pro-
- cedures and represenatative_ records, interviews with personnel, and. observations by the inspectors. Within the scope of'the inspection, no. violations or devations
~
were identified.
- c. TDH Inspection February 7-8, 1983
' The inspection consisted of a review of activities and radioactive materials used at the University of Texas as authorized by TDH License.
i.
i --
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5
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' ~
1 _ _ _ _ _ _ _ __.I__b _.: . . . _ _ _ _ _ _ _ - .__.m m. _ m ___. . _ _ . _ _ _ _ _ .__m_ _ . .m .._. 2
VI. Public Service Activities A. Summer High School Science Teacher Symposium The NETL staff organizes and supervises an annual two week symposium designed to familiarize high school science teachers with the theory and technology associated with energy resources today. Graduate college course credit is given to all participants who successfully complete the course. The program is funded by various electric utility companies in Texas. Approximately thirty (30) teachers attend the symposium every year.
B. Lectures and Presentations On numerous occasions during 1983 the NETL staff talked to various organizations about subjects including but not limited to: " Nuclear Reactor Safety," " Nuclear Engineering and Society," "Research and Development of Energy Resources," " Energy and the Environment," and "What hap-
. pened at Three Mile Island."
C. Reactor Facility Tours During 1983, 1700. persons visited the laboratory. The two largest groups visiting the laboratory were 268 persons attending the Texas Energy Science Symposium and 258 persons attending the University of Texas Centennial Cele-bration activities. Numerous high school students also toured the facility during an event called The World of Engineering, designed to recruit students into the field of Engineering. Students from seven local-high schools and. students from six non-engineering related college courses visited the facility. . Numerous college engineering related classes and several student engineering organi-zations also toured the facility. Safety personnel with Austin Fire Department, UT Police Department, UT Safety Office ~and the Texas Department of Health also visited the laboratory to familiarize ~themselves with the laboratory and emergency' response procedures unique to the facility.
29 a .
~'
VII. Research Activities The Nuclear Engineering Teaching Laboratory prusues research of both sponsored and unsponsored projects in several different areas. The following section lists research projects in which the laboratory has participated.
Major.research funding or grants are presented in Table 15.
The U.S. Department of Energy'has provided.research A.
support by providing reactor fuel cycle assistance for the currently operating reactor core at The University of Texas at Austin TRIGA reactor.
B. 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. Development of a Preconcentration Method for Field Samnlina'of Uranium
. - Personnel: Dale Klein, NETL Tom Bauer, NETL Mohammed Ally, NETL
~
~ Sponsored by: Nuclear Engineering Teaching Laboratory Descrintion:
Two-basic' techniques are used presently at the
- Nuclear Engineering Teaching Laboratory at The University of Texasiat' Austin for the determination'of trace elements
- (e.g.,-uranium). .These include neutron activation analysis tand-x-ray fluorescence.- When the elements to be' examined are':presentoin trace quantities,.either~a large: sample must There-be measured or_the sample.must be preconcentrated.-
- are several advantages of a preconcentrationsmethod and the-objective of-this project is to develop a suitable method' t
forfthe analysis of trace elements,-including: uranium, in
~
water. :The: project was concluded with Lthe measurement of Se,EV, Cu,'Mo, Zn, U'and Th. -An organic' reagent (APDC);was
- 'successfully applied' to obtain = ng/g measurements 'of t precon-
- .centrated water-samples.
\ f y
s
' ' 30
TABLE 15 RESEARCli FUNDING t
i Texas Atomic Energy Research Foundation S 28,400 5/1/83 - 4/30/84 ,
Department of Energy -- Fuel Program ----
Center for Energy Studies 25,000 9/1/82 - 12/31/83 National Science Foundation 76,376 2/81 - 7/84 E
University of Texas College of Engineering-Equipment Fund 9/81 26,400 Center for Fusion Engineering 21,000
- DOE rellowship Program (Institutional' Allowance) 6,000 TOTAL S183,176 I
31 t
D. Heat Transfer and Friction Factor Analysis for Artificially _Houghened Surfaces e
Personnel: Dale Klein, NETL J. Parker Lamb, Mechanical Engineering Mike Krause, NETL Gary Polansky, Mechanical Engineering sponsored by: Center for Energy Studies National Science Foundation
Description:
The proposed research is to determine the heat transfer and friction characteristics for surfaces with discrete roughness geometry. Two major aspects are to be examined in that thic is both an experimental and an anal-ytical 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 designed. 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 measurements. Analytical predictions will be made utilizing fundamental parameters in boundary layer theory coupled with the latest information on rough surfaces using integral techniques. Results from the experimental and analytical methods will be compared in order to gain insight as to the dominant mechanism involved for the use of discrete rough surfaces. Thic research has fundamental
, application for heat transfer augmentation.
O P
A 9
32 s
[
4 -
g
- E. Measurement of Vanadium in Egg White Diets Personnel: T.L. Bauer, NETL M. Ally, NETL Soonsored bv:
~ ~
J.H. Freeland, Home Economics Department, UT at Austin
Description:
Nutritional studies on takeup and retention of some trace elements in the human diet include the elements of V and Mn. Measurements were performed to determine the vanadium content of a test diet prepared primarily from egg whites.
F. Interlaboratory Comparison of Element Analysis of coal Personnel: T.L. Bauer, NETL F.Y. Iskander, NETL Sponsored by: C. Ho, Bureau of Economic Geology Several core samples containing coal materials and other rock material from Texas sites were analyzed by INAA. Thirty-eight (38) elements were determined in the samples and compared to analysis performed by alternate analytical laboratory methods.
G. Analysis'of Elements in cigarette Tobacco, Filter, Ash and Paper Personnelt F.Y. Iskander, NETL T.L. Bauer, NETL Sponsored byr NETL Descriptions Cigarettes from several countries and various domestic brands, including different brand types, were analyzed by INAA methods. Results were examined and.
. compared to' values reported in the literature. Approxi-mately thirty elements'were identified. Measurement de-termined the element content'in the unsmoked tobacco, the 33 i
residual ash after smoking, the residue in the filter and
, the paper from which the tobacco was removed. Presence of some elements indicative of additives at either the proces-sing or production stage were noted although evidence was
. not direct.
H. Calcium content in cereal Matter Personnelt F.Y. Iskander Sponsored by: Texas A&M University
Description:
Investigations to decrease production times of some cereal compounds require the measurement of Ca as indi-cations of the elemental cereal content. Samples were acti-vated and decay of Ca48 activity provided data for the calcium content.
I. Cadmium and Calcium Uptake Studies
. Personnel E. Sorenson, Pharmacy Dept. UT D. Acosta, Pharmacy Dept. UT T.L. Bauer, NETL i Sponsored by: John Hopkins Center for Alterna- ,
tives to Animal Testing
Description:
Radioactive tracers of Cd104, Ca45, and Cdll5 were employed in studies of binding and transport related '
to cell uptake mechanisms. Several experiments with cell cultures of rat hepatocyte cells were performed to determine the effect of calcium presence on the intake of the toxic element cadmium.
+
Y 34 .
J. Interlaboratory comparison of Air Particulate Filters Personnel: F.Y. Iskander, NETL T.L. Bauer, NETL J. Rhodes, Columbia Scientific Industries Sponsored by: CSI/NETL
Description:
Air particulates spiked with elements of interest were examined by several laboratories. Two sets of samples were analyzed each intended to be applied for XRF analysis types of measurements. The samples are intended to be used as standards and for quality assurance samples. INAA analysis was performed for elements V, Mn, As, Br, Ba, Co, Ni, Fe, Sb, Cr, Zn and Se in one set of samples. The second set of samples was analyzed for Al, C1 and Ca.
K. Fission Product Absorption in Continuously Processed Fission Suppressed Fusion Bybrid Reactor Blankets Personnel: Dale Klein, NETL J.W. Davidson, NETL Ann Patterson, NETL Sponsored by: Department of Energy Fellowship Center for Fusion Engineering Descri_p tion:
The effect on blanket performance of fission-product absorption in lithium / molten salt hybrid reactor blankets is being investigated. Neutron flux spectra in blankets of varying fuel and fission product compositions
- are being determined using the discrete ordinates codes, ANISN, and DOT-IV with multigroup cross section data from VITAMIN-C. Flux levels and spectra 11y weighted cross section libraries for the blanket materials, fuel, and fission products will be established for use in the depletion analyses. Generation and depletion of the 7
various isotopes in the blanket will be calculated using ORIGEN. A lumped fission product.model will be used in the transport calculations;.however, detailed information con-cerning the constituents of the lump will be included in the-depletion analysis.
35
In addition to full and partial reprocessing of the molten salt, alternative processing concepts will be investigated. A parametric study of the effects of processing performance will be carried out. This study will result in the characterization of the fission product concentration in the molten salt with respect to isotopics, neutron absorption, and the effects on blanket parameters such as the tritium and fissile breeding ratios.
L. Pressure Drop and Heat Transfer Measurements of Liquid Metal Flowing in a Packed Bed Under the Influence of a Magnetic Field Personnel: Dale Klein, NETL Tom Sanders, NETL Larry Grater, Mechanical Engineering Mike Crawford, Mechanical Engineering sponsored by: Center for Fusion Engineering Texas Atomic Energy Research Foundation
, neseription:
The flow of electrically conducting fluids through porous media.in the. presence of a magnetic field has recently begun to generate significant interest due to
' potential applications for fusion reactors.. This study is designed to examine the pressure drop and heat transfer from a liquid metal (NaK) flowing'through a packed bed of stainless steel spheres under the influence of a trans-verse 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.
. )
e 36
i l
l M. CQ2 Production for Enhanced Oil Recovery Using Texas I Lignite and Nuclear Process Heat Personnel: B. Kolda, NETL j
> Dale Klein, NETL Sponsored by: Center for Energy Studies
Description:
Carbon dioxide miscible displacement is one method of enhanced oil recovery which can increase ultimate production beyond that obtained from primary and secondary methods. Current sources of CO2 for this application are obtained from natural CO2 wells, by product CO2 and on-site generation of CO 2. This project is to examine the feasibility of obtaining CO2 and other valuable by-products i from Texas lignite using a high temperature gas-cooled nuclear reactor for process heat. An integrated concept will be developed to include the nuclear process heat and the valuable by-products converted from the Texas lignite.
N. Examination of Reversed-Field Pinch Reactor using_a Homopolar Generator as a Power Supply Personnel: Herbert Woodson, Electrical
. Engineering Dale Klein, NETL Erfan Ibrahim, NETL Sponsored by: Center for Fusion Engineering Texas Atomic Energy Research Foundation
Description:
The Reversed-Field Pinch (RFP) reactor is one of the conceptual designs under study for the production of electrical energy from fusion. Several reactor design evaluations have been undertaken at the Los Alamos National' Laboratory. The RFP is a toroidal shaped device that holds a plasma by the simultaneous presence of a toroidal field and a poloidal field. A. homopolar generator power supply has been developed by the Center for Electromechanics (CEM)
, at The University of. Texas at Austin. The goal of this study is to examine the RFP and the homopolar power' supply.
developed by CEM as a conceptual design. Parameters to be investigated include the physical size of the RFP, the power supply required and the fundamental plasma requirements'for ignition.
37 I
O. Construction of a Large Benjamin Counter Personnel: Nolan E. Hertel, NETL Richard Savage, NETL sponsored by: Texas Atomic Energy Research Foundation
Description:
A large spherical proton-recoil proportional counter is being constructed for use in measuring neutron energy spectra below 2MeV. By differentiating proton-recoil spectra obtained with the detector filling gas (methane or hydrogen) at various pressures, an unknown neutron energy spectrum can be reconstructed. This de-tector will be used with an existing NE-213 spectrometry system to make possible neutron spectral measurements from 20 MeV down to approximately to 10 kev. The two detection systems will then be employed in fusion energy related ,
neutronics studies.
. P. Transient Analysis of Fissile and Fusile Fuel Trajec-tories for Hybrid and convertor Reactor symbioses Personnel: Nolan E. Hertel, NETL J. Wiley Davidson, NETL Yukitaka Kunimoto, NETL Sponsored by: Texas Atomic Energy Restarch Foundation
Description:
Fissile fuel bred in a hybrid fusion reactor blanket may be used to expand the fission convertor reactor economy. Similarly, fusile fuel (tritium) produced in the convertor reactors may'be used to expand the fusion economy. A model has been developed to predict the rate at which such a symbiotic economy could grow. The model allows the determination of time dependent fissile and fusile inventories for stockpiles, as well as for both hybrid and convertor reactor cores and blankets. This
+ transient analysis is being performed for a variety of fission convertor and anticipated fusion hybrid reactor concepts and fuel cycles. Such an analysis will allow the prediction of initial stockpile requirements in addition to providing a more accurate assessment of short term symbiotic system doubling times.
38 i
m _
j
Q. Heutron Transport Studies Neutron Multiplication by
. Beryllium Personnel: Nolan E. Hertel, CFE Sponsored by: Pending, National Science Foundation
Description:
The use of beryllium as a neutron multiplier is central to the current fusion breeder design. Recent measurements of beryllium neutron multiplication and re-evalutions of beryllium nuclear data indicate that the mul-tiplying performance of beryllium previously has been over-estimated, possibly by as much as 25%. If beryllium's per-formance as a neutron multiplier has indeed been overesti-mated even by as much as 10%, the direction of the fusion breeder program in the United States might well change. It is 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 proposed.
The beryllium experiment has been designed to measure multiplication resulting from DT, DD, PuBe, and 252 Cf neutron sources being placed in a spherical shell.
By doing so the sensitivity of the multiplication to spectral shape can be observed. In addition, the use of these four sources helps to simulate the effect of neutron source degradation in a fusion reactor. The neutron multi-plication will be obtained directly from summing weighted Bonner ball measurements of the neutron leakage. The neutron multiplication obtained in this manner will provide a number which tests the capability of the current beryllium nuclear data to calculate total neutron multi-plication.
9 39
o VIII. Publications From the Nuclear Engineering Teaching Laboratory
- 1. K.L. Gilbert, " Neutron Flux Mapping of a Subcritical Reactor Core with a Polyethylene Reflector", Masters Thesis, Physics Department, The University
- of Texas, 61 pp. , June 1961.
- 2. T.T. Doss, " Neutron Density Distribution in and Unreflected Subcritical Reactor Core", Masters Thesis, Physics Department, The University of Texas 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 Department, The University of Texas, 75 pp.
June, 1962.
- 4. R.W. Reed, "Effect of a Cadmium Control Rod on the Neutron Density in a Subcritical Reactor", Masters Thesis, Physics Department, The University of Texas, 85 pp., August 1962.
- 5. P. Berananda, " Neutron Flux Distribution of a Subcritical Reactor Core with a Graphite Reflector", Masters Thesis, Physics Department, The University of texas, 40 pp., January 1962.
- 6. T.A. Fredericks, " Thermal Neutron Flux Distribution Due to a Plane Wave Source in and Unreflected Reactor Assembly", Masters Thesis, Physics Department, The University of Texas,107 pp. , August 1963.
- 7. D.G. Martin, " Film Detector for a Neutron Spectrometer", Masters Thesis, Physics Department, The University of Texas, June 1963.
- 8. M.L. West II, " Flux Decay Rate in a Reflected Subcritical Reactor",
Masters Thesis, Physics Department, The University of Texas, 55 pp., August 1963.
- 9. R.I,. O' Dell, "The Angular Thermal Neutron Spectrum in the Vicinity of the Interface Between Two Media", Ph.D. Dissertation. The University of Texas,
.186 pp. , January 1965.
- 10. B.E. Thompson, Sr., " Cryogenic Neutron Spectra Measurements Across a Discontinuity in Temperature and Properties",_Ph.D. Dissertation, The Univer-sity of Texas, 149 pp., January 1965.
- 11. R.S. Kolflat, "An Experimental Approach to the Study of Nucleonic Funda-mentals",' Masters Thesis, Mechanical Engineering Department, The University of
~
Texas, 190 pp., May, 1965.
~ 12. D.G. Anderson, "A Technique for Recoil Fission Fragment Range Measurements",
Health Physics, Vol .12, No. 4, 558, April 1966.
40
- 16. M.G. Stevenson, " Investigations on the Macroscopic Nodal Approach to Space-dependent Nuclear Reactor Kinetics", Ph.D. Dissertation, The University of Texas, 203 pp. , August 1968.
- 17. F.H. Antunez-Castillo, " Gamma Radiation Dosimetry Techniques and Appli-cation to Mapping of The University of Texas Cobalt-60 Irradiation Facility",
Masters Thesis, Physics Department, The University of Texas, 60 pp. , September 1968.
- 19. P.J. Rodriguez and D.H. Nguyen, " Time Decay Constants in Pulsed Multi-plying Media", Trans. Amer. Nucl. Soc. 11:1_, 289 (June 1968).
. 20. P.J. Rodriguez and D.H. Nguyen. "The Maximum Eigenvalue in the Pulsed-Neutron Initial-Value Problem", Trans. Amer. Nucl. Soc. 11:2, 578 (November 1968).
- 21. P.J. Rodriguez and D.H. Nguyen, " Contribution of the Continuum to the Neutron Transient Behavior in a Pulsed Multiplying Cylinder", Trans. Amer.
'Nucl. So_c., 11:2, 582 (November 1968).
- 22. G.D. Bouchey and S.J. Gage, " Neutron Radiography with a Small Subcritical Reactor", Trans. Am. Nuc1. Soc., 12, 462-463, 1969.
- 23. 'G.D. Atkinson, Jr.,'W. Coltharp, R. Cramatges, E. Oelkers, D.A. Roberts, K.R. Waid, S.H. Gage, and B.V. Koen, " Project Atlantis: A Design of the Nuclear Power Supply for an Undersea City", Proceedings _ of the Offshore Technology Conference, Dallas,-Texas (1969).
- 24. J.A. Villalobos, "A Study of Gamma Radiation Dosimetry Techniques and
' Application to Radiation Field. Mapping", Masters Thesis,' Physics Department
-(Nuclear Engineering)', The University of Texas, January 1969.
- 25. M. A. Zuniga, " Delayed Neutron Counting Technique for Uranium Determination",
- Masters Thesis, Physics Department (Nuclear Engineering), The University of Texas, January 1969.
126; 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.
~ 41 a
. 27. M. Gallardo, S.J. -Gage, and D.F. Barker, " Trace Elements in Quartz by Nondestructive Neutron Activation Analysis", 1969.
- 28. G.D. Atkinson, Jr., " Investigation of the Dynamic Behavior of a Two-Region Subcritical Reactor", Masters Thesis, Mechanical Engineering (Nuclear Engineer-
-ing), The University of Texas, January 1969.
- 29. M. Gallardo, " Trace Elements in Six Quartz Samples by Nondestructive Neutron Activation Analysis Technique," Masters Thesis, Physics Department (Nuclear Engineering), The University of Texas, January 1969.
- 30. F. A. Rodriguez, S.J. Gage, and K.M. Ralls, " Nondestructive Neutron Activation Analysis for Trace Impurities in Niobium". Seventh Symposium on Nondestructive Evaluation of Components and Materials in Aerospace, Weapon Systems, and Nuclear Applications, San Antonio, Texas (1969).
- 31. S.J. Gage and M. Zuniga, " Uranium Trace Analysis by Pulsed Reactor Irra-diation", Radiation and Isotope Technology in Latin American Development, American Nuclear Society Topical Meeting, San Juan, Puerto Rico, May 4-6,-1969.
~32. R.H. Richardson, " Migration, and Enzyme Polymorphisms in Natural Popula-
.tions of Drosophila", Jap. J. Gen., (in press), 1969.
- 33. R.H. Richardson, R.J. Wallace, Jr., S.J. Gage, G.D. Bouchey, and Margaret Denell, " Neutron Activation Techniques for Drosphila in Natural Populations",
Studies- in Genetics, Marshall R. Wheeler Ed. , The University of Texas Press,
~
' Austin, Texas 1969.
- 34. G.D. Bouchey and S.J. Gage, " Development and Potential Utilization of a Neutron Radiography Facility at The University of Texas NuclearReactor Laboratory",
Seventh Symposium on Nondestructive Evaluation of Components and Materials.in Aerospace, Weapons Systems, and Nuclear Applications, San Antonio, Texas (1969).
- 35. G.D. -Bouchey and S.J. Gage. ." Utilization of the University of Texas -TRIGA Reactor for Neutron Activation Analysis Service", ANS/CNA Transactions (11)
.p. 287, 1968.
- 36. G.D. Bouchey and G. Gjerstad, " Chemical Studies of Aloe-Vera_ Juice --
11'Inor No. 4 1969).
(ganic Ingredients", Quarterly Journal _ of Crude Drug Research,
-37. S.J. Gage, R.H. Richardson, and G.D. Bouchey, " Neutron Activation Tech-niques for Labelino.of. Insects with Stable Elements". Trans. Am. Nuc1'. Soc.,
~
12,.495-496,(1969).
- 38. F.G. Pasosi"Nondispersive X-Ray Fluorescence Analysis Using a Lithium-Drifted Germanium ~ Detector" .Mastert Thesis, Physics Department, The University
~
'of Texas,.54 pp., January 1969.
42 U' -__.-.___--_--._._-...A
- 39. P.J. Rodriguez, " Time and Energy Dependent Neutron Distribution in a i
Pulsed Multiplying Medium", Ph.D. Dissertation- The University of Texas, 205 pp., January 1969.
- 40. G.D. Bouchey, B.V. Koen, C.S. Beightler, "The Optimal Allocation of Energy in Industrial and Agro-Industrial Complexes Using Dynamic Programming",
Nucl. Sci. and Engr., Vol. 41, 70-78 (1970).
- 41. G.F. Malan and B.V. Koen, "A Nonlinear Programming Approach to Optimal Control of Nuclear Reactors", Trans. Am. Nuc._1. Soc. , November 1970.
- 42. M.G. Stevenson and S.J. Gage, " Application of a Coupled Fission Mode Approach to Modular Reactor Kinetics", Jou_rnal of Nucl. Energy, Vol. 24, pp.1-10. Pergamon Press 1970. Printed in Northern Ireland.
- 43. G.D. Bouchey and S.J. Gage, " Neutron Radiography at The University of Texas Nuclear Reactor Laboratory", Isotopes _ and Radiation Technology 1, 294-296 (Spring 1970).
44.. 0.G. Jopling, "The Politics of Nuclear Reactor Siting", Masters Thesis, Mechanical Engineering, The University of Texas, December 1970.
- 45. A.H. Urdaneta, "A Programmed Associative Analyzer" Masters Thesis, ,
Mechanical Engineering (Nuclear. Engineering), The University of Texas, December '
1960. '
- 47. G.D. Bouchey and S.J. Gage, " Neutron Radiography with a Small Subcritical Assembly", International Journal of Nondestructive Testing, (1970).
- 48. G.DJ Atkinson, Jr., J.B. Whitworth, and S.J. Gage, "NAACOL--A Spectrum-
. Analysis Routine for.the Small Laboratory", 21st Mid-America Symposium on Spectroscopy, Chicago . Illinois (1970).
- 49. S.J. Gage, G.D. Atkinson, Jr., J.B. Whitworth, and A.H. Pradzynski,
" Computer-Aided Multielement Ganma Ray Analysis with a Compton Suppressed Ge(Li) Radiation Source", Ninth National of the Society of Applied Spectros-
' copy, New Orleans, Louisiana, October 5-9, 1970.
- 50. -K.R. Waid, " Solid State Radiation Detection Devices: Fabrication, Techniques i
and Application to Nuclear Engineering", Masters' Thesis, Mechanical Engineering (Nuclear Engineering) The University. of Texas, January 1970.
- 51. V.li. Chanto, " Neutron Activation Analysis' of Chlorine and Bromine in.Some Haliburton-Bancroft Rocks and Minerals", Masters Thesis, Physics (Nuclear' 'r
~ Engineering) The University of Texas,' January 1970. '
L 43 1'
- 52. J.J.' Chromik and E.L. Draper, Jr., " Energy Integral Tests of Differential Fission Cross Section Data", Trans. Am. Nucl . Soc. , Vol .13, No. 2, p. 755
= (1970).
- 53. R.J. Gramatges-Figueras, " Neutron Waves in Cylindrical Geometries for a Subcritical Reactor", Masters Thesis, Mechanical Engineering Department, The University of Texas, 98 pp., May 1970.
- 54. E. Oelkers, Jr., "A Learning Method for identification of Nuclear Reactor Point Dynamics", Masters Thesis, Mechanical Engineering Department. The Uni-versity of Texas, pp.165, August 1970.
August 1970.
- 56. J.R. Deen, " Calculation of-Resonance Integrals Using the Intermediate Resonance Approximation", Masters Thesis, Mechanical Engineering Department, The University of Texas,140 pp., January 1970.
- 57. C.T. Rombough, " Application of Queueing Theory to Closed-Loop Computer-Reactor Control Systems", Masters Thesis, Mechanical Engineering Department, The University of Texas, 78 pp. , December 1970.
- 58. A.H.U. Bohorquez, "A Programed Associative Analyzer", Masters Thesis, Mechanical Engineering Department, The University of Texas, 98 pp. December 1970.
- 59. S.J. Gage and D.G. Jopling, The Nuplex Concept: Potential for the SINB Region, Southern Interstate Nuclear Board, 250 pp., March 22, 1971.
, .60. G.F. Malan and B.V. Koen, " Application of Nonlinear Programing to the Optimal Control of a Point Model Nuclear Reactor" Nucl. Sci. and Engr.,
(1971).
'61. .G.D. Bouchey, B.V. Koen, and C.S. Beightler, " Optimization of Material Safeguards Sampling System". Trans. Am. Nucl . - Soc._, Winter. Meeting, (1971).
- 62. A.H. Pradzynski and S.J. Gage, " Nondestructive ~ Identification of Material by Nondispersive X-Ray Fluorescence Spectroscopy Using Si(Li) Detectors and Radioisotopic Sources", Proc. Eighth Symposium on Nondestructive Evaluation in Aerospace Weapons Systems, and Nuclear Applications, San Antonio, Texas .
~
(1971 ) . ~
c 63. .G.D. Atkinson, Jr., and S.J. Gage," Uranium Assay'by Delayed Gamma Ray Analysis Following Cf-252 Neutron Interrogation". Proc. Twelfth Annual Meeting institute of Nuclear Materials' Management, Plam Springs, Florida (July 1971),
44'
- 64. 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 Applications, CONF-710402, Vol . 2, Proc. of ANS Topical Meeting, Augusta, Georgla, April 19-21, 1971.
- 65. =D.G. Jopling and S.'J. Gage, "Public Resistance to Nuclear Reactor Siting",
N!aclear News, 14:3, 32-35 (March 1971).
- 66. J.B. Whitworth, G.D. Atkinson, and S.J. Gage, "Some Recent Applications of Nuclear Analysis Techniques to Typical Forensic Evidence" 23rd Annual Pro-gram American Academy for Forensic Sciences, Phoenix, Arizona (February 25,
'1971).
- 67. 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. Am. Nucl . Soc. , Vol .1,4,:2, pp. 667-668, (October -
1971).
- 68. G.D. Bouchey, B.V. Koen, and C.S. Beightler, "The Optimization of Nuclear -
Systems by Geometric Programming, Nucl. Sci, and Engr. 44, 267-272 (1971).
.69. G.D. Bouchey, B.V. Koen, and C.S. Beightler, " Optimization of Nuclear
~*
Materials Safeguards Sampling Systems' by Dynamic Programing", Nuclear
-Technology 12, 18-25 (1971).
~
- 70. S.J. Gage, G.D. Atkinson, Jr. and G.D. Bouchey, " Cyclic Neutron Activation
' Analysis with a Cf-252 Neutron Source", _ r_ans.
T Am. Nucl . Soc. , -(October 1971).
- 71. E. Linn Draper, Jr., '" Integral: Reaction Rate ' Determination Part 1:
~ Tailored Reactor Spectrum Preparation and Measurement", Nuclear' Science
'and Engi_neering,- 46,22,(1971).
- 12. E. Linn Draper, Jr., " Integral Reaction Rate Determinations Part II:
Fission Rate Measurements", Nuclear Science and Engineering, 4_6, 31', (1971).
- 73. G.D. Bouchey and S.J. . Gage, " Detection and Location of Leaking TRIGA Reactor Fuel Elements", Nuclear Technology 10, 211-214 (1971).
74.: - G.D. Bouchey and S.J. Gage, " Neutron Radiography with a Small~Subcritical
' Reactor". . Int. - J. of ~ Nondestructive Testing. . 2,335-353,(1971).
. 75. G.D. Bouchey and S.J.' Gages "The Economics of Subcritical Radiography",
.Trans. Am. Nucl. Soc., 14,,;123 (1971). ,
-* '76. G.D. Bouchey, E. Linn Draper, ~Jr. , and S.J. Gage, " Neutron Radiography
'wi th . Cf-252: The Effect'of-Tailoring Neutron Energy Spectra on Pnotogrpahic-Images", Neutron Sources and Applications, CONF-210402, 'Vol . 3, Proc. ANS :
' Topical Meeting, Augusta, Georgia, April. 19-21, 1971..
~
45 o
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- 77. G.D. Atkinson, Jr., J.B. Wnitworth, and S.J. Gage, " Computer-Assisted Analysis of Ganma-Ray Spectra", Computer Phyyics Conmunications, 2, 40-46 (1971).
- 78. 5.J. Gage, E. Linn Draper, Jr. , and G.D. Bouchey, "Recent Developments in Radioisotopic Source Neutron Radiography" Proc. Eighth Symposium on Non-destructive Evaluation in Aerospace, Weapon $ystems, and Nuclear Applica-tions, San Antonio, Texas (1971).
- 80. G.D. Bouchey, "The Optimization of Nuclear Systems", Ph.D. Dissertation. .
The University of Texas, 231 pp. , August 1971.
- 81. J.B. Whitworth, "The Development and Application of a Systematic Approach' \
to Elemental Analysis in Forensic Investigations", Ph.D. Dissertation - The '
s University of Texas, 223 pp. , December 1971.
'[.
1971. s x -
t
- 83. E. Linn Draper, Jr., Mary Elizabeth Foster and G.D. Bouchey, "Y-Ray Fluroescence Analysis and Neutron Activation Analysis in an Analytical Cbemistry' !'
Laboratory", presented at the Combined Meeting of the Texas Association fr.r * ' ' '
Radiation Research and South Central Photobiology Group, flouston, Texas. , ,
November 5-6, 1971. .
.84. E. Linn Draper, Jr. and G.D. Bouchey, " Utilization of a Portable Cali- ;s fornium-252 Source for Neutron Activation Analysis and Neutron Radiography", '
Presented at the Combined Peeting of the Texas Association for Radiation Research and South Central Photobiology Group, Houston, Texas, November ,
s 5-6, 1971. .
.c w -
1 E. Linn Draper, Jr. ar.d J.J. Chromik, " Production and Measurement of a \
85.
Reference Spectrum in a Versatile Experimental Facility", Trans. Am. Nucl . ~ Y('
Soc. , Volume 15,:1, p.157,1972.
e
.86. E. Linn Draper, Jr. ani Andrzej H. Pradzynski, " Identification of Alldy> t '
by Energy Dispersive X-Ray Spectroscopy", Ninth Symposium on Nondestructive.
s.
Evaluation (1972).
. 87. M.B. Owen, " Fuel Management Using Dynamic Progranming" Masters Thesis $w, ' *.
Mechanical Engineering Department The University of Texas, 59 pp. ,May 1972. .
- 88. C.E. Brauer, " Thermal Neutron Radiography with a Lithium-Lead Collimator- ;'
Filter". Masters Thesis, Mechanical Engineering Department, The University of Texas, 64 pp. , May 1972. .
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i \ s 89. J.L. Macdonald, " Heuristic Learning Control for Nuclear Reactors", Masters
.. Thesis,Mecha'nical Engineering Department, The University of Texas, 131 pp.
. s [*x j.
~
Augteljl2.
- 90. J. Freim,:" Theoretical and Experimental Evaluation of Nuclear Data and talcu h tion 'echniques for Fusion Reactor Blanket Design", Ph.D. Dissertation, lhe Dnicersity of Texas, 210 pp., December 1972.
- H. S.G. Barbee, "Neutronic Calculations in a Simulated Fusion Reactor Blanket", Masters Thesis. Mechani. cal Engineering Department, The University
~ of Texas, 259 pp. , November 1972.
D.G. Anderson, " Fission Product Mass-Yield Measurements from Intermediate
(' 92.
Energy Neutron Fission of Plutonium-239 and Plutonium-241", Ph.D. Dissertation, The Univerpity of'Te' xas,125 pp. , Decenicer 1972.
c
- 94. G.D. Atkins6n, Jr,-E. Linn Draper, Jr., and G.D. Rouchey, "Subcritical
-1RIGA Reactivity Measurements Using the Source Jert Technique, TRIGA Owner's
-. -Conference II, College Station, Texas (1972).
- 95. G.D. Atkinson, Jr., and E. Linn Draper, Jr., " Transient Rod Failure in a
- 96. G.D.lAtkinson,oJr., "A' Safeguards Minicourse", 18th Annual Meeting of qthe American ' Nuclear Society, Las Vegas, Nevada (1972).
s,. .
J5/. G.D. Atkinson,' Jr. , L. L inn Uroper, Jr. , G.11. I!aut. hey, . and s' .J. Gotje,
" Radioisotopic Source Amplification Using a lieterogeneous Subcritical Assembly",
jroca18th Annual Meeting of the American Nuclear Society, Las! Vegas, Nevada n1972).
.~
198J E. Linn Draper, ,Jr. , and G.D. Atkinson, Jr. , "I'ransient Rod Failure'in a "Fulsing TRIGA Mark I Reactor", published in proceedings .of' 2nd TRIGA Owner's Conference, February 1972.
- 99. Ee Unn Drapg, Jr. , John W. Davidson, S.J. Gage, G.D. Bouchey, "A System -
for.Reducti'on'of A Release from a Research Reactor-Facility", Trans. Am.
. Nucl. Soc., Vol. 15:1, p. 4-5, (1972)..
U,. a .
~~
n., <10001E. Linn Draper, Jr., et.al., " Standard for the Development of Technical C_ p .Tpg p Ls ifications for Research Reactors", Trans. Am. Nucl. Soc.,-(1972).
y 'EyNf06.N U LinnDrdper, Jr., G.D. Atkinson, Jr. , and B.B.)Tomlin, "A Radiography and Capture Gamma. Ray Facility for Californium-252" Proceedings of -the American Applications of Californium-252" National Topical Meeting, u NuclearSociety!1972..
September 11-13' y ,. .
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102. E. Linn Draper, Jr., G.D. Bouchey, G.D. Atkinson, Jr., and S.J. Gage.
"A Versati!e Subcritical Assembly for Undergraduate Nuclear Engineering 5 Instruction", Proceedings of the knerican Nuclear Society " Applications of 1 Californium-252" National Topical Meeting, September 11-13, 1972-103 E. Linn Draper, Jr., and S.J. Gage, "The Fusion-Fission Breeder: Its P. ential in a Fuel Starved Thermal Reactor Leonomy", 93rd Annual Meeting of the ASME, New York, New York (1972).
104. E. Linn Draper, Jr. , " Technological Innava uon and Assessment: A Novel '
Course-for Nuclear Engineerinq". Winter Meeting of the American Nuclear Society, November 12-16, 1972.
105. D.T. Hall, E. Linn Draper, Jr. , and P.S. Schmidt, " Management of tha Transition to Nuclear Power Generation", Technical Report ESL-3, Energy Systems Laboratories, College of Engineering, The University of Texas at Austin, December 1972.-
106. P.S. Schmidt and G.G. Park, " Heat Dissipation in a Power ylant Cooling Bay", ASMEc Paper No. ' 72-WA/ilT-61, November 1972. ,
107. P.S. Schmidt and G.P. D' Arch, " Entry Region Effects on Flow and Pressure - >-
, Drop of Lithium in Fusion Reactor Blankets",- Proceedings of the Texas Symposium on Technology of Controlled Thermonuclear _ Fusion Experiments and. Engineering Aspects of Fusion Reactors, Austin, Texas (November 20-22,1972).
108. .E. Linn Draper, Jr., Charles Brauer, " Lithium-lead Collimator. Fabrication s-for Radioisotopic Source Neutron Radiography, ' Trans. Am. Nucl . Soc. , Vol .15:1,
~~
p.1142-143,()972). a z109. E. Linn Draper, Jr., James B, Freim, " Theoretical and ExperimentalsEval -
.uation of' Nuclear Data and Calculation Techniques for Fusion Reactor-Blanket
-Design",-Texas Symposium on the Technology of Controlled Thermonuclear Fusion Experiments and the Fngineering Aspects of Fusion Reactors,- November 20-22. - .
1972.
110i E. Linn Draper.1Jr.','" Status of CTR Related' Integral Experiments" pre- .
sented at the conference on " Nuclear Data 'and Neutronics of CTR Blankets" held '
- in Seattle, Washington ~ September 19-21,1972. ,
111. E. Linn Draper. Jr.,J" Fusion Reactor; Engineering in the Nuclear Engineering 4
. Curriculum'at The University of Texas-at' Austin",; Trans. Am. Nucl . : Soc. <
f(1972).
112' : E. . Linn ' Draper, ihK , S.J s Gage, "The Fusion-Fission Breeder: rIts' Potential
, 'in; a Fuel.~ Starved Thennal Reactor. Economy", presented at the : Texas-. Symposium - '
Jon the Technology of Controlled : Thermonuclear Fusion- Experiments' and th'e H (Engineer!ing. Aspects of Fusion Reactors, November 20-22, 1972' .
~
, 1113.-: James 48. Freim, E. L' inn' Draper,?Jr.',3" Experimental' Determination,0f the
~ '
< ! Fusion ~ Spectrum in Graphite",' Transr Am. Nucl. Soc' , (1972).
- 48 -1 d g 4
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114. G.D. Atkinson, Jr. , S.J. G qe, G.D. Unu: hey, "Cyclir Activation with a Californium-252 Source", Nucle ir Technology (19/2).
115. G.D. Atkinson, Jr. . "What you Alway , Wanted to Know About Californium Source Facilities', invitad Ppaer, National Topical Meeting on the Applications of Californium-25?, Austin, Texas (1972).
116. T.L. Bauer, G.D. Atkinson, Jr. , "Discr b h..: tion Between Plutonium and Uranium by Ganina Ray Analysis following C. -N interrogation", National Topical Meeting on the Appl kations of Californium-B '. Austin, Texas (1972).
117. E. Linn Draper, Jr.. Editor, Proceedinos of Texas Synposium on the Tech-
~
nolg ofControlledThermonuclear'FusionL$~~r'imentsandtheEngineering Aspe,c_y,[
t oTWs~iliiQiGHors, published by USAl C.'
118. E. Linn Draper, Jr. , Editor, P_roceedings of the Implicattor.s of Nuclear Power in Texa< , published by the Texas Atcmic Enerqy Research Foundation.
119. E. Linn Draper, Jr., J.R. Deen, J.J. Chromik. " Measurement of the Integral Fission Cross Section of Th-232 in a Cf-252 Fission Neutron Spectrum,"
Trans. Am. Nucl. Soc. (1973).
, 120. D.G. Anderson, E. Linn Draper, Jr., " Fission Product Mass-Yield Measure-ments From Intermediate Energy Neutron Fission of Plutonium-239 and Plutonium-241", Trans. Am. Nucl. Soc., 1973.
121. E. Linn Draper, Jr. , and James B. Freim, "Fxperimental Determination of the Fusion Spectrum in Graphi te". Trans. Am. Nucl . Soc. , 16,9,(1973).
177. E. ' inn Graper, Jr., " Fusion Reactor Engineering in the Nuclear Engineer-ing Curriculum at The liniversity of Texas at Austin", Trans. Am. Nucl. Soc.,
16, 16 (1973).
123. E. Linn Draper, Jr. , Theodcre A. Parish, and Brian J. 'McArdle, "A Neu-tronic-Photonic Comparison of Vanadium and Niobium Containing Fusion Reactor Blankets" Trans. Am. Nucl . Soc. , (November 1973).
124. John H. Vanston, Jr., "Use of Partitive Analytical Forecasting (PAF)
Techniques for Fusion Development Analysis", Trans. Am. Nucl . Soc., (November
-1973).
125. Theodore A. Par mh and E.1. inn Draper, Jr. , "Neutronic and Photonic Analyses of Fusion Reactor Blankets Containing Thorium," Fifth Symposium on Engineering
- Problems of Fusion Research, Princeton, New Jersey, November 5,1973, 126. C.E. Locke and D.R. Paul, "Graf t Copolymer Modification of Poly-ethylene-Polystyrene Blends. I. Graft Preparation and Characterization".
Journal 'of Applied Polymer Science, Vol. _1_7_, pp. 2597-2617 (1973.)
49 1
h
127. C.E. Locke and D.R. Paul, "Graf t Copolyner Modification of Poly-ethylene-Polystyrene Blends. II. Properties of Modified Blends", Journal of Applied Polymer Science, Vol.17, pp. 2791-3800 (1973).
128. J.R. Deen, " Measurement of Fission Product Yields from Thorium-232 in a Californium-252 Fission Neutron Spectrum". Ph.D. Dissertation, The Uni-versity of. Texas at Austin,141 pp., (May 1973)
.129. L.D. Hansborough, 'Overall Tritium Considerations for Controlled Ther-nonuclear Reactors", Masters Thesis, The University of Texas at Austin, 154 pp. (May 1973).
130. "M.E. Senglaub, " Cross Section Studies Based on the Statistical Model",
Masters Thesis, The University of Texas at Austin,109 pp. , (August 1973).
131. E. Linn Draper, Jr. , M.J. Voltin, Jr. , J.L. Macdonald, C.T. Rombough, L.D. Hansborough, S.G. Barbee, and J.H. Vanston, Jr. , "A University's In-volvement in Municipal . Decision-Making on Nuclear Power", Trans. Am. Nucl.
Soc.,;(1973).
132. E. Linn Draper, Jr., J.L. Macdonald, and M.J. Voltin, Jr., " Nuclear vs.
Coal: An Economic Comparison of Power Plant Economics in Texas", Trans. Am.
Nucl. Soc., (1973).
133. 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 9-10. 1973.
I'34. G.D. Atkinson,' Jr., ' Applications.of Neutrcn Activation Analysis to th'e Life Sciences", presented at the Combined Meeting of the Texas Association for Radiation Research and South Central Photobiology Group, San Marcos, Texas,
. November 9-10,1973.
'135. S.P. Nichols, " Experimental Detennination of Neutron Fermi Age from
~
Californium-252 Fission Spectrum to Cadmium' Covered Indium Resonance in a-EGraphite Medium" Masters Thesis, The University of Texas at Austin,101 pp.,
January.'1974.
136. T. A. Parish, "Neutornic and Photonic - Analyses of -Simulated Fusion Reacter Blankets Containing Thorium and-Natural Uranium"',;Ph'.D. Dissertation, The University. of Texas at Austin,:329: pp. ' January 1974.
3 '137. J.H. Vanston, 'Jr. , "Use of; the Partitive Analytical : Forecasting'(PAF)'
. Technique for-Analysis of-the Effects of Various Funding'and Administrative:
-Strategies .on Nuclear Fusion Power -lant ' Development"; L Ph.D. Dissertation.
~
~*- iThe University of Texas: at Austin', 459. pp. ,. January 1974.-
l138. .E.M.LB.lSorensen, " Thermal Effects on the Biological Magnification of:
. Arsenic in Green. Sunfish M epomis Cyanellus",'Ph.D; Dissertation,The.:Univer :
6 -sity.;of Texas at' Austin, 233 pp., May.1974.
7
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r 139. E. Linn Draper, Jr. , and J.R. Deen, " Measurement of Fission Product Yields from Thorium-232 in a Californium-252 Fission Neutron Spectrum", Trans._Am_.
Nucl. Soc., 17, 531 (1973).
140. E. Linn Draper, Jr. , fi. 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).
141.. E. Linn Draper, Jr., and T.A. Parish, "Neutronic and Photonic Analyses of
. Fusion Reactor Blankets Containing Natural Uranium", CONF-740 42 0 , USAEC, (April 1974).
142. G.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 SYMPOSIUM, San Francisco, California (1973).
143. _ G.D. Atkinson, Jr. , and R.E. Henri, " Neutron Activation Analysis:
Envirormental and Biological Applications", Sixth Annual Meeting of the Texas Association for Radiation Research, San Marcos, Texas (1973).
144. : M. Etzion, R.G. Spangler, E. Linn Draper, Jr., " Multiple Foil Activation Measurement of the Californium-252 Fission-Neutron Spectrum, Trans. Am. Nucl.
Soc. -(October 1974).
.- 145. .A. H. Pradzynski, " Determination of Selenium in Water on' the ppb Level" presented before the Texas Association for Radiation'Research, Dallas, Texas .
-(November 22,1974).
146. Thomas L. Bauer, " Discrimination of Uranium-235 and Plutonium-239 by
' Cyclic Activation 1and Delayed. Gamma Ray Analysis _Using Californium-252 as a- ~
Neutron' Interrogation Source", Masters Thesis, Mechanical Engineering De- -
- partment, The' University of Texas-at Austin,178.pp. (August 1974).:
147. OlanLD." Thompson, " Optimization of' Shipping. Containers for Radioisotopic.
Neutron Sources",' Masters: Thesis.. Mechanical. Engineering Department. The Uni-
. versity of.. Texas at Austin, 30' pp. , (August 1974).
148. '.J.R.' Deen,,E. Linn Draper .Jr., " Mea'surement of the: Fission Product Yields and the' Energy Integral Fission Cross Section of Thorium-232 in a Cali-- '
fornium-252 Fission-Neutron Spectrum",. Nuclear Technology', 25,:416 (1975).
1 149. .E. Linn. Draper, Jr. ,- T. A. Parish,' M. .Etzion, " Utilization of a 'Small' .
l Accelerator:for: Fusion = Reactor Blanket Design",.Proce. dings of the Third Smail:
a ; Accelerator Conference, USAEC, CONF-741021.(1974).
- - c150. TR.G fSpangler, E.:Linn1 Draper, Jr., T.A.' Parish, "14 MeV Cross Section-
- - ~ Measurements of Threshold Reactions-for Seven-Metals" .Trans.-Am.--Nucl. Soc., ,
22,,.818 (November 1975).
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- 151. W.R. Smith, Jr. , E. Linn Draper, Jr. , " Measured and Calculated Fast Neutron Spectra in a Graphite Medium", Trans. Am. Nucl . Soc. , 22, 800
-. (November 1975).
152. J.W. Davidson, E. Linn Draper, Jr., " Costs for Partitioning Strategies Involved in High-Level Nuclear Waste Management". Trans. Am. Nucl . Soc. , ~22,
- 348 (November 1975).
153. M.J. Voltin, Jr. , E. Linn Draper, Jr. , " Sensitivity of Total Fuel Cycle Cost to Variations in Enrichment Tails Assay Strategies", Trans. Am. Nucl. Soc.,
22, 322 (November 1975).
154. T.A. Parish, J.W. Davidson, E. Linn Draper, Jr., " Transmutation of Fission Products in Fusion Reactor Blankets", Trans. Am. Nucl. Soc., 22,
~ (November 1975). ,
155. T.A. Parish, J.W. Davidson, 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 18-21,1975).
156. A.H. Pradzynski, R.E. Henry, J.L.S. Stewart, " Determination of Selenium c in' Water on the ppb Level by Coprecipitation and Energy Dispersive X-Ray
. Spectrometry",_Radiochem. Radioanal. Letters, 21(5) 277-285 (1975).
157_.
B.E. Bulla, E. Linn Draper, Jr. , R.E. Henry, M.J. Vol tin, Jr. , et.al . ,
Texas Nuclear Power Policies:
A Study of Alternatives,~ Volume II: Methodology.
The University of Texas at Austin Center for Energy St6 dies, Policy Alternative Study No. 1'(1975).
~
158. . A.H. Pradzynski, R.E. Henry, J.L.S. LStewart " Determination of Transition ~
Metals'by Radioisotope-Excited Energy Dispersive X-Ray Spectrometry",
Trans. Am. Nucl.. Soc.,.21,_.No.-3 34-35'(1975).
-159. A.H.!Pradzynski,.'R.E. Henry, J.L.S.IStewart, " Nondestructive Determination
- of Toxic Elements in-Toys", Proc. of 10th Symposium on Nondestructive Elements,-
San Antonio, Texas,L257-265 (April 23-25, 1975).
160. R.E. Henry, _" Determination ofl ppb Levels of. Selected Elements. in Natural
< Water Using Radiosiotope-Excited Energy Dispershe' X-Ray l Fluorescence Analysis",
at .the Eighth Annual- Meeting of' the Texas Association' for Radiation
_Research, presented' Austin, Texas:(October 31 -- November 1, 1975).
~
>' 161. . S.P. Nichols, _" Application of the P'artitiv'e Analytical Forecasting (PAF)
Technique to the United States Controlled Thermonuclear Research-Effort,"
y Ph.D. Dissertation,iThe University of. Texas at Austin (December 1975).' '
162. _ ;C.T. Rombough, "The Total _ Energy Investment in' Nuclear' Power Plants", .
Ph.DT Dissertationi Tne University .of Texas at Austin, .(January 1975).
152 ..
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- 163. J.L. Macdonald, " Investigation of Pattern Recognition Techniques for the Identification of Splicting Surfaces in Monte Carlo Particle Transport Cal-culations", Ph.D. Dissertation, The University of Texas at Austin (August 1975).
164. J.W. Davidson, "A Cost-Benefit Analysis for Partitioning Strategies In-volved in High-Level Nuclear Waste Management", Masters Thesis, The University of Texas at Austin, (May 1975).
165. 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 Amerimn Nuclear Society, 23., 59, June 1976.
166. T. A. Parish, " Fusion-Fission Hybrid Studies at The University of Texas,"
U.S.-U.S.S.R. Symposium on Fusion-Fission Reactors, Lawrence Livermore Labora-tory, July 1976.
167. T. A. Parish, J. W. Davidson and E. Linn Draper, Jr., "Neygronic Perfor-mance of Graphite Fusion Reactor Blankets Containing Sr 90 and Il 9," Second ANS Topical Meeting on the Technology of Controlled Thermonuclear Fusion, Richland, Washington, September 1976.
168. T. A. Parish, J. W. Davidson and J. B. Cornwell, "The Effectiveness of a Sr90 Fusion Reactor Transmutation Waste Management Program," Transactions
~
of the American Nuclear Society, 24, November 1976.
. 169. A. H. Pradzynski and J. R. Rhodes, " Development of Synthetic Standard Samples for Trace Analysis of Air Particulates," ASTM Special Technical Publication No. 598,1976, pp. 320-336.
170. A. H. Pradzynyi, R. E. Henry and J. S. Stewart, "Detennination of PPB Concentrations of-Transition Metals by Radioisotope-Excited Energy-Dispersive X-Ray Spectrometry, Journal of Radioanalytical Chemistry, 32, 1976, p. 219-28.
171. A. H. Pradzynski, R. E. Henry and E. L. Drger, Jr. , "Detennination of PPB Concentrations of Uranium, Thorium and Molybdenum in Water using APDC Preconcentration and Radioisotope Excited X-Ray Emission Spectrometry,"
Proceedings of EPDA Symposium on X- and Gamma-Ray Sources and Applications, Ann Arbor, Michigan, May 19-21,1976, pp.175-177.
172. A. H. Pradzynski, R. E. Henry and E. L. Draper, Jr. , "Detennination 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. Transactions of Am. Nuclear Society, H, 1976, p.119.
! 173. R. R. Gay, G. F. Brockett and R. T. Johnson, "Two-Phase Flow Measurement L 'a Techniques for Nuclear Safety Research," Two-Phase Flow and Heat Transfer Symposium-Workshop, Miami Beach, Florida (1976).
174. C. W. Savery and R. R. Gay, "Effect of Entrained Droplet Phase Upon Predicted Compartmental Pressures in Nuclear Containments," Two-Phase Flow and Heat Transfer Symposium-Workshop, Miami Beach, Florida (1976).
53
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175. Rodney R. Gay, " Reactor flydrodynamics During the Reflood Phase of a loss-of-Coolant Accident," Nuclear Technology, Vol. 36, No. 2, Dec. 1977, pp. 229-237.
- 176. D. E. Klein, S. R. Bull, and J. B. Miles, " Flow Visualization Around GCFR Fuel Rod Roughness Elements," Trans. Am. Nuclear Soc. , 28, June,1978.
177. D. E. Klein, S. R. Bull, and J. B. Miles, " Pressure Drop for GCFR Fuel
- Rod Roughness Elements," Trans. Am. Nuclear Soc., 30, November 1978.
-178. . E. M. B. Sorensen, R. E. Henry and R. Ramirez-Mitchell, " Time Dependent
' Localization of Arsenic in Subcellular Hepatocyte Fractions," J. of Patholoay and Toxicology, Vol. 2, No. 4, 1979, pp. 1161-1171.
179.' E. M. B. Sorensen, R. E. Henry, and R. Ramirez-Mitchell, " Arsenic Accumula-tion, Tissue Distribution, Cytotoxity in Teleosts following Indirect Aqueous 21, 1979, Exposure," Bulletin of Environmental Contamination and Toxicology, Vol.
. pp. 162-169, 180. J. W. Davidson and T. A. Parish, " Fission Product Toxicity Reduction via Transmutation Using D-T Fusion Neutrons," Eight Symposium on Engineering Problems of Fusion Research, San Francisco, California, November 1979.
181. J. W. Davidson and T. A. Parish, "An Evaluation of the Requirements and
- -Performance of a Transmutation Waste Management System, Trans. Am. Nuclear Soc.,
33, November-1979.
182. S. A. Hodge, J. P. Sanders, and D. .E. Klein, " Determination of Friction -
Factors and Heat Transfer Coefficients.for Flow Past Artifically Roughened Surfaces, Oak Ridge National Laboratory Report,~ ORNL-5599,_ November 1979.
183. D. E. Klein,L" Nuclear Problems and Prospects," National Energy Policy Issues, Council on Energy Resources, The University of Texas at- Austin, May L1979.
184. D. E. Klein, H. H.- Woodson,j and J. W. Davidson, " Commercial Nuclear Power-Generation," Council on Energy Resources, The University of Texas at Austin,
~
- June _1979.
185. E. H. B. Sorensen, R. R. Mitchell, A. Pradzynski, T.' Bauer and L. Graham, "Morphometric Analyses of Arsenic-Induced Histopathological Changes in Parenchynial
- Hepatocytes," Tennessee Academy of--Science Annual Meeting, Nashville, TN,
. November 16-17,:1979.
_ _186.
A. H. Pradzynski,:" Determination of V and Ba in Marine Sediments and -
Biota'," Internal Report, Nuclear: Engineering Teaching' Laboratory,1The University:
of Texas.at~ Austin,-Department.of Mechanical Engineering'(1979).
xi~ 3187; N. E.~. Hertel, .B. .W. Wehring, and J. J. Dorning, " Integral Test of :
ENDF/B-IV: High-Energy Neutron Cross' Section Data _ for Tungsten," Trans. Am.
Nucl. Soc.- 32,631::(1979).
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l 188. R. H. Johnson, K. R. Koch, B. W. Wehring, and N. E. Hertel, "TDL Measure-l 'nents in an Iron Sphere Containing a DT Source," Trans. Am. Nucl. Soc. 32, 632(1979).
i
- 189. D. W. Wehring, J. J. Dorning, N. E. Hertel, D.T. Ingersoll, R. H. Johnson,
" Benchmark Shielding Problems Obtained from Integral Tests of Neutron Cross
~ Sections," Trans. Am.__Nucl. Soc. 33, 666 (1979).
190. N. E. Hertel , R. H. Johnson, J. J. Dorning, and 8. W. Wehring, " Measure-nents and Analyses of Neutron Transport Through Iron," Proc. Conf. Nuclear Cross Sections and Technology, Knoxville, TN, Oct. 22-26, 1979, NBS Special Publication #594, pp. 568-571.
191. N. E. Hertel, B. W. Wehring, ." Absolute Monitoring of DD and DT Nuetron 4 . Fluences Using the Associated-Particle Technique," Nucl. Instr. Meth. 172, .
'501(1980).
!192. . 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, Vol . 23, February 1980, pp.135-149.
193. N. E. Hertel, J. B. Smathers, and R.G. Graves, " Gamma-Ray Spectra
- Measured.in a Tissue-Equivalent Medium Irradiated with Neutron Radiotherapy j Sources," Trans. Am. Nucl . Soc. 35, 457 (1980).
c 194. 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 l-21-26, 1981.
195. D. E. Klein, S. R. Bull and J. B. iiiles, " Pressure Drop Measurements and Flow Visualization Surrounding Roughness Elements," Journal of Energy, Vol . 4, No. 3,. May-June 1980,. p. ~ 112-119.-
~
196. D.-.E. Klein, "ANS Student ' Involvement 'in Public' Information-The University of . Texas at Austin," Trans. Am Nuclear Soc., jp[, . June 1980 (invited).
197. R. -8. Pope, H.- R. Yoshimura, J. E. Hamann, and D. E Klein,- "An- Assessment
-of; Accident Thernal . Testing-and Analysis Procedures for: Radioactive Materials Shipping Package," ASME 80-HT-38, April 1980.
s198. f 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,E" Paper 1#147, PATRAM-80, West Berlin, FRG. . -Nov. -1980.
199. M. A. Ross and:D. E. Klein " Synthetic -Fuel Production Utilizing Texas Lignite .and a VHTR for Process . Heat," Trans. Am. Nuclear Soc. , 35,' Nov.1980.
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200. 'J.W._Davidson.Lan'd D.'E.'Klein.(co-editors) -Proceedings of'the International-
~
- E Conference on Nuclear Waste Transmutation, University:of . Texas Press, March 1981.
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201. M. A. Ross and D. E. Klein, " Synthetic Fuel Production Using Texas Lignite and a VHTR for Process Heat," Number 3, March 1982, Nuclear Technology, Vol. 56.
e 202. T._ L. Sanders and D. E. Klein, "A Modified Numercial Scheme for GCFR
.. _ Flow Transient Analysis," Trans. Am. Nuclear Soc., 39, November 1981.
203. M. A. Ross and D. E. Klein, " Synthetic Fuel Production Using Texas Lignite and A Very High Temperature Gas Cooled Reactor for Process Heat and Electrical Power Generation," Center for Energy Studies, The University of Texas at' Austin, Research Report No. 13, May 1981.
-204. M. M. Razzaque, J. R. Howell and D. E. Klein, " Finite Element Solution of Heat Transfer for Gas Flow Through a Tube," AIAA Journal, Vol. 20, ;io. 7,
.1olv .1982.
205. S. Yang, J. R. Howell and D.E. X1ein, " Radiative Heat Transfer Through a Randomlv 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, 206. .D.E. Klein and J. Andersen et al., " Peer Review of the Preliminary Design and Program Interfaces for the Transuranic Waste Package Transporter (TRUPACT)," Sandia Report, SAND 81-240F June 1982.
207. T. 'L. Sanders and D. E. Klein, " Transient Thermal-Hydraulic Analysis Using a Modified Version of COBRA IV," _7th International Heat Transfer
, Conference, Munich, Germany 82-IHTC-104, September 1982.
208. S. Yang, J. R. Howell and D. E. Klein, " Monte Carlo Simulation of Thermal' Conduction Through a Randomly Packed Bed of Spheres," 7th Interna-tional Heat Transfer Conference, Munich, Gemany, 82-IHTC-91, September 1982.
209. T. L. Sanders and D. E. Klein, " Comparison Analysis' of Severe Flow Blockages for Computational Efficiency Using COBRA," Proceedines from Gas-Cooled Reactors Today~ Conference,' British Nuclear Energy . Society, London, England, September 1982.
'210. M. LM. Razzaque,- J. R. Howell and D. E.' Klein,. " Finite Element Solution - ,
of' Radiative Heat Transfer in a Two-Dimensional P,ectangular Enclosure with '
Gray _ Participating Media,",82-WA/HT-51,: ASME Annual Meeting, Phoenix, Arizona, fNovember.1982. .
~ 211. J. B. Smathers, N. E. - Hertel, R. G. Graves, "In' Phantom Photon Spectra l Measurements for High-Energy Neutron Therapy Sources," Proceedings: Fourth ;
JSymposium.on Neutron Dosimetry: Beam Dosimetry, 1-5 June 1981,7 Neuherberg/Munchen',
Fe'deral Republic of Gemany, EUR 7448en -(1981)~. .
..- l212.-.N.E. Hertel, B. W.'Wehring and J. J. Dorning, " Measurements and. Analyses.
of High-Energy Neutron Transport Through Tungsten," (accepted _for publication-subject to revision in Nuclear Science and' Engineering, November ;1981).
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213. Y. Kunimoto, J. W. Davidson, and N. E. Hertel, "A Core Inventory Model for Fuel Trajectory Analysis in Fusion-Fission Symbiotic Systems," Trans. Am.
Nucl. Soc., 4_1_, 1978, June 1982.
214. N. E. Hertel and W. E. Murphie, "The Use of Neutron and Gamma-Ray NE-213 s Spectral Measurements and Calculations to Obtain Dosimetric Information for DT Neutrons," Medical Physics 10,66,(1983).
215. R. Laucius, J. W. Davidson, and N. E. Hertel, " Calculation of the Differential Efficiencies of Organic Scintillators to Neutrons Above 10 MeV,"
Trans. Am. Nucl. Soc., 4_3, 625, November 1982, 216. 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.
217. N. E. Hertel, J. W. Davidson and R. M. Laucius, "NE-213 Response Matrix for Neutron Spectrometry Up to 50-MeV," Health Physics Society Annual Meeting, Baltimore, Maryland.
218. N. E. Hertel, J. W. Davidson, and R. M. Laucius, "An NE-213 Response Matrix to 50 MeV," Trans. Am. Nucl. Soc., 4_5, 5 607 (1983).
219. J. W. Davidson and N. E. Hertel, "An Equal Probability Neutron Detection System Using Bonner Spheres," Trans. Am. Nucl. Soc. , 45, 609 (1983).
220. D.' E. Klein, " Coupled Radiative and Conductive Heat Transfer in a Two Dimensional Rectangular Enclosure with Gray Participating Media Using Finite Elements," ASME/JSME Thermal Engineering Joint Conference, ASME-H-35, Honolulu, Hawaii,' March 1983.
221. S. Yang, J. R. Howell, D. E. Klein, " Radiative Heat Transfer Through a Randomly Packed Bed of S heres by the Monte Carlo Method," (submitted to the Journal of Heat-Transfer .
222. M. M.- Razzaque, J. R. Howell, D. E. Klein, " Finite Element Solution of Radiative' Heat Transfer in a Two Dimensional Rectangular Enclosure with Gray Participating Media," (submitted to Journal of Heat Transfer).
223. M. M. Razzaque, 'J. R. Howell, D.- E. Klein, " Coupled Radiative and Con-ductive Heat-Transfer in a Two Dimensional Rectangular-Enclosure with Gray Participating Media Using. Finite Elements,"'(submitted to Journal of Heat '
Tra'nsfer) .
224. Sorensen, E. -M. B. , C. W. . Harlan, M.D. , T. L. Bauer and A. Pradzynski.
. Hepatocyte changes-following selenium accumulation in a freshwater teleost.
- The American Journal of Forensic Medicine and Pathology 3(3) 8p.,1982.
225. Sorensen, E. M. B. , and T. L'. ' Bauer. Selenium-induced Condition Factor
.and Organ: Weight Changes in Naturally-exposed Redear Sunfish. (Submitted to
-- Tox icol ogy) . ~
, ~ ,
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'226. Sorensen,' E. M. B. , T. L. Bauer, J. S. Bell, and C. W. Harlan. Selenium 3 Accumulation and Cytotoxicity in Teleosts Follcding Chronic, Environmental Exposure. (Accepted by Bulletin of Environmental Contamination and Toxicology).
227. Sorensen, E. M. B. and T. L. Bauer. Selenium Induced Hematological Dyscrasia in Teleosts. (Accepted by Archives Environmental Contamination and Toxicology).
228. 'Sorensen, E. M. B. , P. M. Cumbie, T. L. Bauer, J. S. Bell, and C. W. Harlan.
-Histopathological, Hematological, and Other Changes Associated with Selenium Ac-
. cumulation in Fish from Belews Lake, North Carolina. (Ready for submission to Archives Environmental Contamination and Toxicology).
229.. Sorensen, E. - fl. B., R. R.' Mitchell, A. Pradzynski, T. L. Bauer, and L.
Graham. Stereological Analyses of Hepatocyte Changes Parallel Arsenic Ac-
- cumulation in the Livers of Green Sunfish. (Accepted by The Journal of Environ-mental Pathology, Toxicology,andOncology_).
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THE UNIVERSITY OF TEX AS COLLEGE OF ENGINEEklNG AUSTIN TEX AS 78712 liepartment of AfechanicalEngineering Nuclear Engineering Program '
1/2 - 171 3136 April 13, 1984 Director of Inspection and Enforcement U.S. Nuclear Regulatory Commission
-Washington, D.C. 20555
Dear Sir:
Enclosed are twelve -(12) copies of the calendar year 1983 annual report. required according to CFR 10 Section 50.59.
Sincerely yours,
$ (. W T..-L. Bauer
- Reactor Supervisor:
S0P #3664 y .
y.- /,)
/
' Dale Klein, Director
-Nuclear Engineering Teaching Laboratory 1TLB:DK:bb-
Enclosures:
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