ML20050D671
| ML20050D671 | |
| Person / Time | |
|---|---|
| Site: | 05000192 |
| Issue date: | 03/31/1982 |
| From: | Bauer T, Klein D TEXAS, UNIV. OF, AUSTIN, TX |
| To: | |
| Shared Package | |
| ML20050D619 | List: |
| References | |
| 10CFR-020.407B, 10CFR-20.407B, NUDOCS 8204120381 | |
| Download: ML20050D671 (60) | |
Text
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1 NUCLEAR REACTOR LABORATORY TECHNICAL REPORT t
THE UNIVERSITY OF TEX AS C O 1.I. E G E OF ENGINEERING DEPARTMENT OF MECil ANICAI. ENGINEERING I
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1981 Annual Report of The University of Texas at Austin Nuclear Engineering Teaching Laboratory January 1,1981 - Decerter 31, 1981 D. E. Klein, Director T. L. Bauer, Supervisor Taylor Hall 104 512-471-5136 March 1982 b
i
a TABLE OF CONTENTS Page i.
List of Figures......................
iii ii.
List of Tables iv I.
Introduction 1
II.
Laboratory Administration.................
5 A.
Organization B.
Personnel C.
Reactor Committee D.
Radiation Safety Committee III.
Laboratory Development 12 A.
Organization B.
Nuclear Engineering Teaching Laboratory C.
Nuclear Radiation Laboratory D.
Subcritical Facility E.
Neutron Activation Analysis Facilities i
IV.
Laboratory Operation and Utilization 16 A.
Reactor Facility B.
Facility Changes 24 l
V.
Laboratory Inspections A.
Inspection by the Nuclear Regulatory Commission on l
Operations and Procedures B.
A Visit by the Nuclear Regulatory Commission on Operating License Renewal C.
A Visit by the Nuclear Regulatory Commission on Special Nuclear Materials License Renewal VI.
Public Service Activities..............
25 i
A.
Summer High School Science Teachers Symposium l
B.
Lectures and Presentations l
C.
Tours and Radiation fionitoring VII.
Research Activities....
27 VIII.
Publications from the Nuclear Engineering Teaching 39 Labora tory ii
a O
i i
i l
List of Figures Figure No.
Page 1.
Floor Plan of Nuclear Reactor Laboratory 3
2.
Floor Plan of the Nuclear Engineering Teaching Laboratory 4
3.
Organization Chart of the Nuclear Engineering Teaching Laboratory 6
4.
Comparison Burn up vs year 20 5.
Comparison of number of samples irradiated vs year 21 s
iii
2 List of Tables Table No.
Page 1.
Reactor Scrans 17 2.
Comparison of Yearly Inadvertant Scrans 17 l
3.
Nuclear Engineering Teaching Laboratory Performance Data 1980 18 4.
Comparison of Previous Utilization Data 19 5.
Courses Utilizing the Reactor and Associated Facilities 22 6.
Statistical Summary of Radiation Exposure 26 7.
Research Funding 28 l
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iv
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I.
INTRODUCTION This report has been prepared by the staff of the Nuclear Engineering Teaching Laboratory (NETL), The University of Texas at Austin, to satisfy the reporting requirements of the U.S. Department of Energy Contract Nunber At-(40-1)-3919 and 10 CFR 50.59. This report covers the period f rom January 1,1981 to December 31, 1981.
i The NETL is presently equipped with a 250 kW TRIGA Mark I nuclear reactor, a 1400 curie Cobalt-60 irradiator, two 150 kV Cockcroft-Welton 14 MeV neutron generators, three Californium-252 neutron sources, a subcritical assembly, and a neutron activation analysis laboratory, with various radiation detection systens. The nuclear reactor laboratory i
is shown in Figure 1 with adjacent areas of the Taylor Hall engineering building shown in Figure 2.
The major events and/or changes made to the laboratory during this period include:
I 1.
The completion of the laboratory physical security upgrade.
2.
The interior of the laboratory was remodeled; including floor and wall refinishing, rearrangement of equipment, removal of the darkroom, 1
and reconstruction of the door and wall originally separating the radiochemistry room from the darkroom.
3.
A new neutron activation analysis system consisting of computing l
hardware and sof tware, data acquisition equipment, and radiation 1
detection equipment has been ordered to supplement existing facilities.
Some safety related equipnent, including a thermoluminescent dosimetry h
system,has also been ordered.
?
4.
The SNM-180 license renewal was approved and a new license was issued which will be effective thru February 1986.
5.
A review of all standard operating procedures for the facility has been initiated and many rewritten in a more easily executable form.
The intent of each procedure remained unchanged.
6.
The WRC R-92 license renewal is still pending. Also pending is NRC acceptance of the revised Safety Analysis Report, Environmental Impact Report, and Technical Specifications.
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II.
LABORATOR'Y ADMINISTRATION A.
Organization The present organizational chart of the Nuclear Engineering Teaching Laboratory is presented in Figure 3.
B.
Personnel The following is a list of personnel of the Nuclear Engineering Teaching Laboratory for the period January 1,1981 to December 31, 1981.
Laboratory Administration and Staff Klein, D.E., Director
+Bauer, T. L., Assistant Director / Supervisor
- Povio, N., Nuclear Technical Specialist
- Krause, M., Nuclear Technical Specialist Pradzynski, A.H., Radiochemist Garcia Morrison, M., Administrative Secretary Chapa, A., Smith, R., Secretary (temporary)
Sherwood, S., Anaya, P., Laboratory Assistants Hertel, N.E., Assistant Professor Davidson, J.W., Researcher Graduate Assistants Ally, M.
Gantt, B.
- Krause, M.
Kunimoto, Y.
Laucius, R.
Patterson, F.
Razzaque, M.
+ Sanders, T.
Yang, S.
+--Licensed Senior Operator
- --Licensed Operator 5
Dean of Engineering l
Chairman M. E. Department Director fluclear Engineering s
N Teaching Laboratory s
j Radiation N
Reactor
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Committee Sa fety Committee
's Reactor Supervisor f
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l Reactor Instructors Technicians Experimenters l
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l LINE OF RESPONSIBILITY
--- - - - - CONSULTATION AND VET 0 POWER
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r FIGURE 3 - ORGANIZATIONAL CHART 6
C.
Reactor Committee 1.
Committee Composition Regular Members:
(9/1/81)
Dr. Dale Klein l
Dr. Joe Ledbetter I
Dr. Harris Marcus (Chairman)
Dr. Nolan E. Hertel Mr. B. G. Williams (student) l Ex Officio Members:
1 Dr. H. G. Rylander, Chairman, Cepartment of Mechanical Engineering Mr. H. W. Bryant, University Radiation Safety Officer Dr. T. L. Bauer, Supervisor, Nuclear Er.gineering Teaching Laboratory 2.
Meeting Frequency The Reactor Committee met four times during the calendar year of 1981.
3.
The Nuclear Reactor Committee Annual Report for September 1980 to August 1981 as presented to the Dean of the College of Engineering is included in the following paragraphs.
Function, Activities, and Membership The Nuclear Engineering Teaching Laboratory staff and facility are administered through the Department of Mechanical Engineering of the College of Engineering at The University of Texas at Austin. The Nuclear Reactor Committee is a requirement of the Nuclear Regulatory Commission and its function is to ensure that the nuclear reactor and l
its associated facilities are operated in a professional and safe manner.
This objective is met primarily by regularly scheduled quarterly meetings of the Nuclear Reactor Committee. The Nuclear Reactor Commit-tee Charter was slightly modified during this year and a copy dated 10/14/80 is attached. This document serves as the basis of operation
(
of the committee. The committee does not involve itself with the day-1 f
to-day activities of the reactor facility, as these responsibilities h
7
lie with the associated faculty and professional staff af the Nuclear Engineering Teaching Laboratory.
Membership on the committee consists of two categories: members and ex officio members. The committee members are appointed by the Dean of the College of Engineering, usually af ter conferring with the Director of the Nuclear Engineering Teaching Laboratory and the Chairman of the Department of Mechanical Engineering. The members include faculty members having some knowledge of nuclear engineering and reactor opera-tion, but not necessarily with direct involvement in the operation of the reactor facility.
In recent years, one or two students have been added to the committee. The members of the committee during this year have been: Professors H.L. Marcus (Committee Chairman and on the t'echanical Engineering faculty), Joseph Ledbetter (Civil Engineering),
Nolan Hertel (Mechanical Engineering), Dale Klein (Director of the l
Nuclear Engineering Teaching Laboratory) and M. Krause (student in Mechanical Engineering). The ex officio members are: the Chairman of the Mechanical Engineering Department (H.G. Rylander), the Supervisor - Nuclear Engineering Teaching Laboratory (T.L. Bauer) and the University Radiation Safety Officer (W. Bryant).
Activities and Comments The recorded activities of the Nuclear Reactor Committee and those items of business pertinent to the committee are included in the minutes of the quarterly meetings. These include minutes for the meetings of July 31, 1980; October 13, 1980; December 18, 1980; March 24, 1981; and June 22, 1981.
8
Specific items of interest include:
- 1) Upgrading of personnel and the management team of the Nuclear Engineering Teaching Laboratory.
- 2) Continued positive responses from NRC on-site inspections and reviews of reports.
- 3) Renovation to the physical structure of the building housing the reactor was performed to assist in reactor security and safety.
- 4) Equipment funds for safety related equipment was made available.
Other facility improvement funds are still required.
- 5) The nuclear engineering teaching laboratory activity is high in the teaching, research and service areas.
This past year has seen a great deal of positive activity take place in the Nuclear Engineering Teaching Laboratory.
4.
A review of the nuclear reactor committee charter was performed and amended 10/14/80 to read as follows:
Composition of this committee shall be a chairman plus three other members.
Appointment to or removal from this conrnittee shall be by the Dean of Engineering on the basis of qualifications and interests, and the members are responsible to him. A maximum of one person may belong to both the Reactor Committee and the Radiation Safety, provided that he not be chairman of both committees.
Functions of this committee are:
1.
To assist the Nuclear Engineering Teaching Laboratory Director in establishing operational procedures.
f 2.
To meet and receive a report at least quarterly from a designated committee member concerning his inspection 9
of the Nuclear Engineering Teaching Laboratory and the operation thereof.
3.
To meet as needed to approve or disapprove reactor i
experiments as submitted by the Nuclear Engineering Teaching Laboratory Director.
4.
To meet as needed to approve or disapprove proposed l
changes in nuclear laboratory procedures and proposed significant alterations to reactor instrumentation and proposed changes in the NRC utilization facility license.
5.
To order a reactor experiment to be stopped and/or the reactor not to be operated if in their opinion any significant hazard exists.
6.
To transmit to the Nuclear Engineering Teaching Laboratory Director or Supervisor whatever suggestions or comments they consider desirable.
7.
The chairman shall cause written records to be kept of all committee actions.
l 8.
At his discretion the chairman may declare any number of committee members to constitute a quorum.
l 9.
Items to be voted upon will pass by a majority vote f
of those present.
l Modifications of the above may be made with the written approval I
of all of the following:
Dean of Engineering Chairman, Mechanical Engineering Chairman, Reactor Committee Director, Nuclear Engineering Teaching Laboratory 10
D.
Radiation Safety Committee 1.
Committee Composition Dr. P. Riley, Chairman Dr. L. O. Morgan Dr. C. Desjardins Mr. H. W. Bryant, Ex Officio 2.
Meeting Frequency The Radiation Safety Committee net twice during the calendar year of 1981 (April 8 and November 18).
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III. LABORATORY DEVELOPMENT A.
Organization Dr. Dale E. Klein continued as the Director and Dr. Tom L. Bauer continued as Reactor Supervisor during the past year.
A. Pradzynski has resigned from the position of Radiochemist as of December 31, 1981; therefore, this vacancy has been posted and a new Radiochemist is being sought. All other university personnel remained unchanged.
B.
Nuclear Engineering Teaching Laboratory The Nuclear Engineering Teaching Laboratory is an important part of the Nuclear Engineering program at The University of Texas.
The Nuclear Engineering Teaching Laboratory's central feature is a Mark I TRIGA 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 few l
years and the research capabilities of the Laboratory are now quite diverse.
In 1968, the facility license was amended to allow the TRIGA reactor to operate at a steady state power level of 250 KW and pulsed power of 250 1
ftW which increased experimental capabilities tremendously. The acquisition of lithium drif ted silicon and germanium solid state radiation detectors with a data acquisition system composed of dual Nuclear Data 1024 channel multichannel analyzers linked to a Data General Nova 800 minicomputer provided facilities for analysis of large quantities of data.
Other experimental devices available at the Laboratory are a sub-critical assembly, a neutron bean irradiation facility, a multi-thousand curie cobalt-60 irradiator, several curie neutron sources, and two 14 MeV neutron generators. Radiation detection systens include sodium iodide k
12
3 crystals, u - 8 proportional counter, Geiger-Mueller tubes, BF3 r He neutron detectors, Ge(Li) and Si(Li) radiation detectors plus associated electronics for a variety of potential experimental arrangements.
The nuclear reactor and the associated laboratory equipment are also used to teach the fundamentals of reactor operation. Students from all over the state as well as other organizations and groups have toured the Nuclear Engineering Teaching Laboratory. Approximately 1000 persons tour the Laboratory each year.
The use, operation, regulation, security, and monitoring of the l
Nuclear Engineering Teaching Laboratory is controlled by the United States Nuclear Regulatory Commission, the Nuclear Reactor Committee of The Univer-sity of Texas, the Director of the Nuclear Engineering Teaching Laboratory, the Radiation Safety Committee and the Radiation Control Board of the State of Texas.
The use, operation, security and radiation monitoring of the Nuclear Radiation Laboratory is controlled by the Director of the Nuclear Engineer-ing Teaching Laboratory and the Radiation Safety Officer of The University of Texas at Austin, and the University Campus Police.
l C.
Nuclear Radiation Laboratory The Nuclear Radiation Laboratory at Balcones Research Center has been utilized by the students and staff of the Nuclear Engineering Program at l
The University of Texas at Austin for the past several years.
The primary use of the building was to house and operate a 14 MeV i
Texas Nuclear neutron generator. When the Nuclear Engineering Teaching Laboratory acquired three (3) Californium-252 sources from Louisiana State University in 1973, the Nuclear Radiation Laboratory became the 13
logical place for their storage and use due to the space and availability of the already installed neutron shielding around the neutron generator, 252 Thus, with the acquisition of Cf
, students and staff can perform experiments utilizing not only the high energy neutrons from the neutron 252 generator but fission spectrum neutrons from Cf In addition to the neutron generator and the Californium sources, other smaller radioactive sources are also used within the confines of the Nuclear Radiation Labora-tory.
Large amounts of neutron shielding material have been installed in and around the neutron generator cavity and at selected spots on the exterior of the building to protect other experimentalists and the environ-ment from abnormal radiation levels. Because of the possibility of high radiation doses within the confines of the neutron generator cavity, the Nuclear Radiation Laboratory is a limited access building and all generator cavity doors are wired into the controls of the generator so that any unwarranted entry automatically shuts down the machine.
D.
Subcritical Facility in association with the undergraduate nuclear engineering laboratory course (ME 361F) and the graduate nuclear engineering course (ME 389R),
the subcritical assembly has continued to provide a facility with which the student can perfonn reasurements that are related to fundamental reactor parameters. Such concepts as age, diffusion, and buckling are denonstrated in individual experiments performed by each student.
E.
Neutron Activation Analysis Facilities The Nuclear Analytical Laboratory has provided support for individual projects ranging fran student laboratory support for advanced classes in 14
chemistry, zoology, physics, and engineering to investigative porjects 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 journals and proceedines, and have been presented at conferences of the state, national and international level.
1 I
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LaboratorL peration and Utilization 0
IV.
A.
Reactor 1.
Operation During this reportinq period the reactor operated for a t otal of 258.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> while supporting numerous nuclear engineering and operation courses, research, and other related activities.
2.
Mintenance During 1981 nost maintenance was limited to routine repair and adjustments.
3.
Inadvertant Reactor Scrams _
During 1981 there were 7 inadvertant shutdowns (excludes intentional scrams) compared with 7 in 1980. Tables 1 and 2 itemize the " SCRAMS" and compare this year's data to previous years' data.
4.
Utilization _
Tables 3 and 4 and Figures 4 and 5 show the utilization of the reactor for the year and compare this data with that of previous years.
5.
Courses Offered llsing the Reactor Table 5 lists the courses offered at The University of Texas at Austin which utilize the reactor and associated facilities.
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TABLE 1 REACTOR SCRAMS l
Intentional
-- 10 Operator Error
-- 4 Instrument Error -- 2 Power Outage
-- 0 Safety
-- 1 Total
-- 17 TABLE 2 COMPARISON OF YEARLY INADVERTANT SCRAMS
'63
'64
'65
'66
'67
'68
'69
'70
'71
'72
'73 10 9
3 4
3 31 15 11 13 6
10 1
'74
'75
'76
'77
'78
'79
'80
'81 4
7 5
9 11 12 7
7
- The number of inadvertant scrams for the years 1978 thru 1979 were
)
amended this year to reflect a consistent definition of inadvertant,
)
being scrams from all sources other than intentional.
17
~
TABLE 3 NUCLEAR ErlGIflEERING TEACHIfiG LABORATORY l
PERFORMANCE DATA, 1981 Total Hours Total hurcber of Reactor In Burn-up Samples w
Operation *
(kW-hrs)
Irradiated First Quarter 46.7
?030 48 1980 Second Quarter 82.2 5316 10 1980 Third Quarter 86.3 7163 214 1980 Fourth Quarter 43.3 3656 58 1980 TOTAL 258.5 18165 330
- Iine Reactor Key on; includes certain experimental setup time, naintenance, etc.
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TABl.E 4 COMPARIS0!10F PRE /IOUS OTI'.IZATI0t1 DATA l
Total Hours Total Number of Reactor In Burn-up Samples Operation *
(kW-nrs)
Irradiated Year 1965-66**
104.5 251 63 1966-67 150.0 595 202 1967-68***
342.6 28,168 2449 l
1968-69 260.8 49,985 1452 1
1969-70 222.0 36,477 1640 1970-71 262.5 53,912 2990 l
1971-72 222.8 38,624 1946 1973 318.6 45,794 1347 1974 226.1 27,641 778 1975 206.905 20,450 363 1976 135.74 11,312 468 1977 139.29 7,509 164 1978 171.9 26,870 178 1979 311.61 72,616 1568 1980 184.1 11,760.4 150 1981 258.5 18,165 330 l
- Includes experimental setup tire, maintenance, etc.
- 1905 was the first year the utilization data were maintained.
l
- ' Reactor upgraded from 10 to 250 kW during this academic year.
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o 67 68 69 70 71 72 73 74 75 76 77 78 79 80 81 YEAR FIGURE 4 TOTAL BURN UP PER YEAR l
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68 69 70 71 72 73 74 75 76 77 78 79 80 81 YEAR FIGURE 5 - nut'BER OF SA"PLES IRRADI ATED PER YEAR 21
TABLE 5 COURSES UTILIZING THE REACTOR AND ASSOCIATED FACILITIES Course Number Course Description ME 397 This course was a prefect ceurse in wh:ch the experiner.ts for ME 379M were documented for use as an aid to the students.
ME 361f Introductory Nuclear Laboratory Designed as an introduction to radio-active decay, activation, and raciation measurement.
ME S339R A special projects laboratory course for foreign nuclear engineers.
ME 379ft A reactor operations course, open to all students.
Designed to allow students with an interest in nuclear power to learn basic reactor theory and participate in actually operating a nuclear reactor.
ME 377K A special projects course whereby students can pursue special topics.
ME 389R A required laboratory course for students pursuing a Master of Science in the Nuclear l
Program.
CH 376K A senior level course in instrumental analytical methods which utilizes the Nuclear Engineering Teaching Laboratory Facilities to study Neutron Activation Analysis.
CE 390L This is a graduate course in environmental analysis for environmental health engineers.
Students use neutron activation analysis and energy dispersive X-ray emission spectro-netry to analyze samples for toxic contaminants.
s i
22
B.
Facility Changes 1.
Physical Security Several improvements of the physical boundaries of the laboratory were completed in 1981. The major 1
items include the replacement of windows on two I
sides of.the laboratory with concrete block and brick construction, the replacement of all entry doors to the laboratory with security hinged solid core doors and the installation of an intrusion 1
alarm system.
I 2.
Ventilation System A fan, exhaust stack, and control have been installed to increase control of room air pressure and air leakage rates. A pre-filter, high efficiency particu-late filter, and pneumatically controlled damper are incorporated into the system. The radiation monitor for the exhaust stack is on order and will be installed in 1982. Until the monitoring system is installed and license modifications allow operation, the exhaust system will not be operated.
3.
Remodeling The interior of the laboratory was physically upgraded considerably during this period. Major improvements consisted of floor and wall refinishing, rearrangement of portable equipment, removal of the darkroom, and re-construction of wall and door originally separating the 1
darkroom from the radiochemistry room. New carpet is on order for the control room and should be installed in 1982.
23
V.
LABORATORY INSPECTION A.
A visit by members of the NRC regarding activities authorized by NRC Licenses R-92 and Shri-180 occurred on May 6,1981 in which information regarding the protection against industrial sabotage and safeguarding of special nuclear material was obtained. No items of noncompliance were found.
B.
An inspection by members of the Nuclear Regulatory Commission of the activities authorized by NRC Operating License R-92 occurred during July 6-7, 1981 in which no items of noncompliance were found.
24 4
VI.
PUBLIC SERVICE ACTIVITIES These activities include those other than research projects or assistance provided in the pursuit of research which are covered in Section VII of this report.
In this section the subjects are symposiums, lectures, presentations, and tours.
A.
Summer High School Science Teachers Symposium Funded by the Electric Utility Companies of Texas, this program was designed to familiarize high school science teachers with the theory and technology of energy resources.
During the summer of 1981, teachers participated in the program.
B.
Lectures and Presentations On numerous occasions during 1981 the NETL staff gave talks on subjects including: " Nuclear Reactor Safety," " Nuclear Engineer-ing and Society," "Research and Development of Energy Resources,"
" Energy and the Environment," and "What Happened at Three Mile Island."
C.
Tours and Radiation Monitoring During the calendar year of 1981 over 1,450 persons visited the lab. Most of these persons represented educational, civic, or industrial organizations, while others were part of formal engi-neering laboratory groups. All persons working in or around the laboratory are provided with personal radiation monitoring devices while tour group members are randomly monitored. Measurable ex-posure to tour group members was in the non-measurable exposure range as indicated by pocket dosimeters. Persons employed by or working in the laboratory are issued film badges.
The annual statistical sunnary of those badges is found in Table 6.
25
TABLE 6 STATISTICAL
SUMMARY
OF RADIATI0ft EXPOSURE 1981 Range of Exposure fiumber of in R[M Individuals lion-ineasurable exposure 34 0.0 0.1 0
0.1
- 0.25 0
0.25 - 0.5 0
0.5 - 0.75 0
0.75 - 1.0 0
1.0 - 2.0 0
2.0 - 3.0 0
26
VII. RESEARCH ACTIVITIES The Nuclear Engineering Teaching Laboratory is pursuing research in numerous areas which are sponsored by the organizations listed below.
Major research funding is shown in Table 7.
The U.S. Departaent of Energy has provided research support A.
by providing reactor fuel for the operation of the University of Texas at Austin TRIGA reactor.
The Electric Utility Companies of Texas has sponsored Summer B.
High School Science Teachers Syir.posium, a program designed to familiarize these teachers with the theory and technology of energy resources.
Development of a Preconcentration Method for Field Sampling of C.
Uranium Personnel: Dale Klein, NETL Mohanned Ally, NETL sponsored _ by_: Nuclear Engineering Teaching Laboratory
==
Description:==
Two basic techniques are used presently at the Nuclear Engineering Teaching Laboratory at The University of Texas at Austin for the determination of trace elements (e.g. uranium). These include neutron activation analysis and x-ray fluorescence. When the elements to be examined are present in trace quantities, either a large sample nust be neasured or the sample must be preconcentrated. There are several advantages of a preconcentration method and the objective of this project is to develop a suitable method for the analysis of trace elements, in-cluding uranium, in water. In previous years a method was developed for transition elements in water. Experiments were extended to Cr, Mn, Th and s
U.
27
TABLE 7 RESEARCH FUNDING Texas Atomic Energy Research Foundation
$37,000 (5/1/81 - 4/30/82)
Department of Energy -- Fuel Program Center for Energy Studies 15,000 (9/1/81 - 8/31/82)
National Science Foundation (5/15/80 - 10/31/82) 39,975 f
(2/81 - 2/83) 76,373 University of Texas Safety Related Purchases-5/81 26,510 College of Engineering Equipment Fund-9/81 53,000 Institute of Nuclear Power Operations (9/1/80 - 5/31/82) 8,000 TOTAL
$255,858 I
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)
D.
Preconcentration of Trace Elements in water for X-Ray Fluorescence Analysis i
Personnel:
A. H. Pradzynski, flETL Sponsored by: fluclear Engineering Teaching Laboratory
==
Description:==
In cooperation with the University of fionterey, f4exico, samples of various types were prepared for analysis by X-Ray fluorescence Spectrometry and Neutron Activation Analysis for several elements. Ex-periments were performed by a group of students from the University of Monterey as survey work for several potential projects.
E.
Advanced Analytical Chemistry - CH 376K Personnel _:
J. Holcomb, Chemistry A. H. Pradzynski, NETL w
Sponsored by: Nuclear Engineering Teaching Laboratory
==
Description:==
Undergraduate students in chemistry performed qualitative and quantitative detenninations of several elements in samples by neutron activation analysis. The program of the class included: (a) sample pre-paration and encapsulation, (b) two irradiations in the TRIGA reactor, I
one for long half-life and another for short half-life radioisotopes, (c) measurements using a Ge-Li detector gamma spectrometer, (d) data processing using an on-line computer and (e) data evaluation and discussion of practical I
applications of NAA in analytical chemistry, t
29
F.
Determination of Selenium in Fish Personnel : Elsie Sorensen, F'emphis State University A. H. Pradzynski, flETL Thomas L. Bauer, flETL Sponsored by: fluclear Engineering Teaching Laboratory
==
Description:==
During experiments on As accumulation in fish from a con-taminated lake, another toxic element, Se has been found in the samples.
Determinations of Se were done by f{eutron Activation Analysis and Gamma Spectrometry.
Results were prepared for publication. Further experiments l
will be performed.
G.
Construction of a Large Benjamin Counter Personnel: fiolan E. Hertel,tir.TL Richard Savage, f4ETL Sponsored by: Texas Atomic Energy Research Foundation Desc r_i pti on :
A large spherical proton-recoil proportional counter is being constructed for use in measuring neutron energy spectra below 2 fieV.
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 detector will be used with an existing fiE-213 spectrometry system to rake possible neutron spectral measurements from 20 l'eV down to approximately 10 kev. The two detection systems will then be employed in fusion energy related neutronics studies.
l 30
H. lieasurerent of Gamma-Ray Spectra Resulting in Tissue from Bombardment with Neutron Radiotherapy Beams Personnel: Nolan E. Hertel, NETL James B. Smathers, UCLA Robert G. Graves, University of Rochester Sponsored by: National Institutes of Health: Public Health Service Grant CA12542 from the National Cancer Institute l
l Mechanical Engineering Department
==
Description:==
Measurements of gamma-ray spectra produced in tissue-equivalent liquid when bombarded by 50-MeV d*-Be and 42 MeV p+-Be neutron beams have been performed. These measurements were done at the Texas A&M University variable Energy Cyclotron using an NE-El3 spectrometer. Analysis of the measurenents will help to determine gamma-ray spectral distribution in tissue during radiotherapy treatment. These spectral distributions are currently being used to calculate the average gamna-ray energy as well as the average ganna-ray mass-energy-absorption coefficient.
I.
High-Energy Neutron Transport Studies Personnel: Nolan E. Hertel, NETL Regina Laucius, NETL Sponsored by: National Science Foundation
==
Description:==
The principal thrust of this project is to develop the cap-ability to routinely and accurately measure high-energy neutron spectra from 1 to 50 million electron volts (MeV). An effective means of per-i forming such measurecents is to utilize the recoil pulse-height data from an organic scintillation detector. The reconstruction of the unknown neutron spectrum from the recoil data requires the use of a matrix describing I
31
the detector's response to monoenergetic neutrons over the energy range of interest. To meet this need, a neutron response matrix from I to 50 MeV is being constructed f rom recent neutron time-of-flight data. The resulting unnormalized experimental pulse-height distribution data will be used in conjunction with various computer codes to form the matrix.
This matrix can then be applied with existing unfolding codes to recon-struct unknown energy spectra. High-energy spectral measurements could be made using this technique at neutron radiotherapy facilities and intense neutron source facilities such as fusion materials radiation daFk190 facilities.
J.
An Analysis of the High-Level Waste Streams from Fuel Cycles Using Fissile-Fuel Producing Fusion Reactors Personnel:
fl.E. Hertel, flETL J.W. Davidson,flETL Sponsored by: Texas Atomic Energy Research Foundation
==
Description:==
Fissile fuel may be produced or bred in fusion reactors by surrounding the fusion neutron source with a blanket containing a fertile material such as Th.
The end product of neutron absorption in this material is the fissile nuclide U which may be used to fuel fission power reactors. A by-product of breeding this fuel is the accompanying fission of the fertile and fissile materials. Both neutron capture and fission reactions produce radionuclides which would constitute a high-level waste stream similar to that from fission reactors. The fission level can be maximized by appropriate blanket designs to increase the power of the fusion reactor; such a device is called a fusion-fission i
hybrid. The fission level could be minimized to reduce fission product 1
32
waste; this type of device would be a syfai9 tic fusion reactor. The fuel bred in either of these devices could be used to fuel existing fission reactors. The high-level waste streams from fuel cycles incorporating a fissile-fuel producing fusion reactor and its client fission reactors 2
are being investigated for the Th -
U fuel cycle.
K.
Transient Analysis of Fissile and Fusile Fuel Trajectories for Hybrid and Convertor Reactor Syn,bioses Personnel: Nolan E. Hertel, NETL J. Ililey Davidson, NETL Yukitaka Kunimoto, NETL sponsored by: Texas Atomic Energy Research 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 stock-piles, as well as for both hybrid and convertor reactor cores and blankets.
This transient analysis is being performed for a variety of fission con-vertor and anticipated fusion hybrid reactor concepts and fuel cycles.
Such an analysis will allow the prediction of initial stockpile require-1 ments in addition to providing a more accurate assessment of short term synbiotic systen doubling times.
)
l 33 l
l
L.
Modification of COBRA-4 Personnel: Dale Klein, NETL Tom Sanders, NETL Sponsored by: General Atonic Company Center for Energy Studies
==
Description:==
The transient version of the thermal-hydraulic computer code COBRA-4 was modified.
Considerable modifications were made to COBRA-4 to enhance its application for analyzing Gas Cooled Fast Breeder Reactor (GCFR) transients. This includes new numerical techniques to speed up calculations. The model is now capable of analyzing transient events for reactor safety studies. This is the final year of a three-year project.
M.
Thermal Analysis of a Spent Fuel Shipping Cask in an Engm'.fing Fire Personnel: Dale Klein, NETL l
James E. Hamann, NETL Sponsored by: Sandia Laboratories
==
Description:==
A thennal analysis using the computer code HEATING 5 was performed to predict the temoerature distribution in a nuclear fuel shipping cask. Results from this detailed model are compared with data from a full scale thermal test conducted by Sandia. The Sandia test involved a full-scale shipping container in an engulfing fire for more than 120 minutes. The HEATING 5 rodel enables thermal analysis for a 3-dimensional transient system where a change in phase occurs. Although this project is directly applicable for a spent-fuel shipping cask, other heat transfer systems can be exanined. This is the final year of a two-year study, i
l l
34
N.
Heat Transfer through Random Packed Beds by Using the Monte Carlo Method Personnel:
Dale Klein, NETL John R. Howell, Mechanical Engineering Sam Yann, NETL Sponsog d J : Center for Energy Studies Descri g on:
This study examines the constricted heat flow in packed beds of spherical particles. The packing pattern is obtained by a nucerical simulation that provides the bulk solid fraction, the contact-number f requency function and the angular distribution of contacting spheres.
The contact resistance is calculated by the Holm formula based on the packino sinulation. The effective conductivity can be determined by statistical methods. Results from this investigation will be applied to a thermal analysis of a pebble bed nuclear reactor core.
Heat Transfer and friction Factor Analysis for Artifically O.
Rouqhened Surfaces Personnel: Dale Klein, NETL J. Parker Lanb, Mechanical Engineering Mike Krause, NETL Gary Polansky, Mechanical Engineering Sponsored bv: Center for Energy Studies l
National Science Foundation l
l 35
==
Description:==
The proposed research is to determine the heat transfer and friction characteristics for surfaces with discrete roughness geocetry.
Two cujor 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 artifically roughened surfaces is being designed.
In addition, a new analytical method has also been developed to determine l
R(h') and G(h') values without making detailed velocity and temperature profile measurements. Analytical predictions will be made utilizing funda-l mental parameters in boundary layer theory coupled with the latest informa-tion on rough surfaces using integral techniques. Results from the experi-mental 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.
Primary application includes heat exchangers and the Gas Cooled Fast Breeder Reactor (GCFR). The modeling will be directed towards the GCFR I
l design conditions. This is the fourth year of a seven year study.
P.
Finite Elements in Radiative Heat Transfer in Asborbing/ Emitting Medium Personnel: Dale Klein, NETL Muhammad Razzaque, NETL Sponsored by: Texas Atomic Energy Research Foundation l
l k
36
==
Description:==
An exact analysis of radiative heat transfer coupled with conductive and/or convective modes was performed to predict the tempera-ture distribution inside a medium and the heat flux distribution at all bounding surfaces of an enclosure with a medium having absorbing-emitting properties.
The Galerkin finite element technique was employed to solve numerically the resulting highly nonlinear partial integro-differential energy equation utilizing isoparametric, quadrilateral elements with Lagrangian tensor product biquadratic shape functions. The walls were assumed to be either gray or black with any given temperature distribu-tions and the medium was assumed to be gray.
Internal heat generation within the medium can also be included. One often encounters such physical situations in practical engineering problems, particularly in a high temperature system where radiation plays an important role in the heat transfer process such as fusion reactors.
Q.
Pebble Bed Breeding Blanket for a D-T Fusion Reactor Personnel:
J.W. Davidson, NETL Dale Klein, NETL Brian Gantt, NETL Sponsored b,v_:
Texas Atomic Energy Research Foundation
==
Description:==
An analysis is underway to examine the feasibility of incor-porating an advanced fuel handling schere to the blanket region of a hybrid 37
fusion reactor. The fuel is that used in a Pebble Bed Reactor (PBR) and both initial enrichment and regeneration of the fuel is being considered.
The Th-232/U-233 fuel cycle used in the PBR would require a fresh or spent thorium feed to the hybrid blanket. The fertile material would be circulated 3
through the blanket, renoved, and returned to a position determined by both the current U-233 concentration and the available neutron spectra and flux levels in the blanket.
Problems involve integrating a pebble bed blanket to currently envisioned fusion reactor designs and determination of optimum recirculation schemes.
Detailed neutronic analysis for the various blanket concepts will be made using computer codes presently available in the Nuclear Engineering Teaching Laboratory.
l R.
Neutronic and Heating Analysis of Accelerator Targets and Blankets l
Personnel:
J.W. Davidson, NETL Sponsored by: Texas Atonic Energy Research Foundation Center for Energy Studies
==
Description:==
Both the breeding of fissile material and the transnuation of high-level nuclear waste appear to be attractive uses for neutrons produced with accelerators. Neutrons produced through spallation reactions in an accelerator target offer potentially high source strengths at a modest energy input. Recent advances in accelerator technology should allow con-struction of snaller, lower cost accelerators with increased bean currents.
Calculation of the neutron transport in the target and surrounding blanket for incident particle enernies of several hundred GeV require a conplex computational ability. This research involves the developtrent of a conputa-tional package with which neutron and charged particle transport in tarcets and neutron transport in blankets nay be accurately determined in a coupled mode along with heat deposition rates in both regions.
38
Vill. Publications from the Nuclear Engineering Teaching Laboratory K.L. Gilbert, " Neutron Flux Mapping of a Subtritical Reactor Core with 1.a Polyethylene Reflector", Masters Thesis, Physics Department, The University of Texas, 61 pp., June 1961, T.T. Doss, " Neutron Density Distribution in and Unreflected Subcritical 2.
l Reactor Core", Masters Thesis, Physics Department, The University of Texas i
63 pp., June 1961.
J.M. Norwood, "The Point Source Transport Solution for the Position and 3.Velocity Dependent Neutron Distribution in a Spherical Body of Non-Multiplying Material" Masters Thesis, Physics Department, The University of Texas, 75 pp.
June,1962.
R.W. Reed, "Effect nf a Cadmium Control Rod on the Neutron Density in a 4Subcritical Reactor", Masters Thesis, Physics Department, The University of Texas, 85 pp., August 1962.
P. Berananda, " Neutron Flux Distribution of a Subcritical Reactor Core 5.with a Graphite Reflector", Masters Thesis, Physics Department, The University of texas, 40 pp., January 1962.
T. A. Fredericks, " Thermal Neutron Flux Distribution Due to a Plane Wave 6.Source in and Unreflected Reactor Assembly", Masters Thesis, Physics Department, The University of Texas,107 pp., August 1963.
D.G. Martin, " Film Detector for a Neutron Spectrometer", Masters Thesis, 7.
Physics Department, The University of Texas, June 1963.
M.L. West II, " Flux Decay Rate in a Reflected Subtritical Reactor",
8.Masters Thesis, Physics Department, The University of Texas, 55 pp., August 1963.
R.D. O' Dell, "The Angular Thermal Neutron Spectrum in the Vicinity of the 9.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 P_hysics, Vol.12 No. 4, 558, April 1966.
- 13. J.B. Whitworth, "A Cryogenic Irradiation Device for the TRIGA Mark I Nuclear Reactor", Masters Thesis, Mechanical Engineering Department, The Uni-versity of Texas, 52 pp., January 1967.
D. A. Pullen, " A Rod Oscillator Design and Zero Power Transfer Function 14.
Measurement for a TRIGA Mark I Reactor," Masters Thesis, Mechanical Engineering (Nuclear Engineering), The University of Texas, January, 1967.
G.F. Malan, " Transfer Function Analysis of Temperature and Xenon Feedback 15.
in Coupled-Core Nuclear Reactor Systems", Masters Thesis, Mechanical Engineering Department, The University of Texas, 69 pp., August 1967.
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.
18.
R. Valiente, " Neutron Radiography with the University of Texas TRIGA Nuclear Reactor", Masters Thesis, Physics (Nuclear Engineering), The University of Texas, August 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. Soc _., 11:2, 582 (November 1968).
22.
G.D. Bouchey and S.J. Gage, " Neutron Radiography with a Small Subcritical Reactor", Trans. Am. Nucl. 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 Gama 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.
26.
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.
27.
M. Gallardo, S.J. Gage, and D.F. Barker, " Trace Elements in Quartz by liondestructive Neutron Activation Analysis", 1969.
G.D. Atkinson, Jr., " Investigation of the Dynamic Behavior of a Two-Region 28.
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-l 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.
G.D. Bouchey and S.J. Gage, " Development and Potential Utilization of a 34.
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 Inorganic Ingredients", Quarterly Journal of_ Crude Drug Research, Vol.
9_,
No. 4 (1969).
37.
S.J. Gage, R.H. Richardson, and G.D. Bouchey, " Neutron Activation Tech-niques for Labelina of Insects with Stable Elements", Trans. Am. Nucl. Soc.,
l_2, 495-496 (1969).
38.
F.G. Pasos, "Nondispersive X-Ray Fluorescence Analysis Using a Lithium-Drifted Germanium Detector", Masters Thesis, Physics Department, The University of Texas, 54 pp., January 1969.
39.
P.J. Rodriguez, " Time and Energy Dependent Neutron Distribution in a 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 Progranming",
N_u_c l. Sc i. and Engr., Vol. 41, 70-78 (1970).
41.
G.F. Malan and B.V. Koen, "A Nonlinear Progranming Approach to Optimal Control of Nuclear Reactors", Trans. Am. Nucl. Soc., November 1970.
42.
M.G. Stevenson and S.J. Gage, " Application of a Coupled Fission Mode Approach to Modular Reactcr Kinetics", Journal 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", Is_otopes and Radiation Technology 1,,
294-296 (Spring 1970).
44.
D.G. Jopling, "The Politics of Nuclear Reactor Siting", Masters Thesis, l
Mechanical Engineering, The University of Texas, December 1970.
45.
A.H. Urdaneta, "A Programed Associative Analyzer", Masters Thesis, Mechanical Engineering (Nuclear Engineering), The University of Texas, December 1960.
46.
G.D. Bouchey and S.J. Gage, " Detection and Location of Leaking TRIGA Reactor Fuel Elements", GA Publication T-il7, Papers and Abstracts, TRIGA Reactor Owners' Seminar, February 19-20,1970 (Denver, Colorado) p. 43.
47.
G.D. Bouchey and S.J. Gage, " Neutron Radiography with a Small Subcritical Assembly", International Journal of Nondestructive Testing, (1970).
48.
G.D. 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.
5.J. Gage, G.D. Atkinson, Jr., J.B. Whitworth, and A.H. Pradzynski,
" Computer-Aided Multielement Gama 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 and Application to Nuclear Engineering", Masters Thesis, Mech 3nical Engineering (Nuclear Engineering), The University of Texas, January 1970.
51.
V.H. Chanto, " Neutron Activation Analysis of Chlorine and Bromine in Some Haliburton-Bancrof t Rocks and Minerals", Masters Thesis, Physics (Nuclear Engineering), The University of Texas, January 1970.
52.
J.J. Chromik and E.L. Draper, Jr., " Energy Integral Tests of Differential fission Cross Section Data", Trans. Am. Nucl. Soc., Vol. l_3_, 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.
55.
F. A. Rodriguez-Gonzalez, " Application of Neutron Activation Analysis to the Study of Interstitial Solid Solution of 0xygen in Niobium and in Niobium-Titanium Alloys", Ph.D. Dissertation, The University of Texas,131 pp.
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, l
The University of Texas, 78 pp., December 1970.
58.
A.H.U. Bohorquez, "A Prograrmed 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 AFclear Boarci, 250 pp., March 22, 1971.
60.
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).
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).
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).
S.J. Gage, E. Linn Draper, Jr., G.D. Bouchey, and R.R. Day, " Design 64.
and Construction of a Versatile Cf-252 Source Shield and Experimental Facility",
Neutron Sources and Applications, CONF-710402, Vol. 2, Proc. of ANS Topical Reeting, Augusta, Georgia, Aprif 19-21, 1971.
D.G. Jopling and S.J. Gage, "Public Resistance to Nuclear Reactor Siting",
65.
Nuclear News, 14:3, 32-35 (March 1971).
J.B. Whitworth, G.D. Atkinson, and S.J. Gage, "Some Recent Applications 66.
of Nuclear Analysis Techniques to Typical Forensic Evidence" 23rd Annual Pro-gram American Academy for Forensic Sciences, Phoenix, Arizona (February 25, 1971).
G.D. Bouchey, E. Linn Draper, Jr., B.V. Koen, and C.S. Beightler, 67.
" Multiple Foil Activation Spectrum Determination Using a Numerical Direct Search Technique", Trans. Am. Nucl. Soc., Vol.14:2, pp. 667-668, (October 1971).
G.D. Bouchey, B.V. Koen, and C.S. Beightler, "The Optimization of Nuclear 68.
l Systems by Geometric Prog-aming, Nucl. Sci. and Entr. 44, 267-272 (1971).
G.D. Bouchey, B.V. Koen, and C.S. Beightler, " Optimization of Nuclear 69.
Materials Safeguards Sampling Systems by Dynamic Programing", Nuclear _
Technology _ 12, 18-25 (1971).
S.J. Gage, G.D. Atkinson, Jr. and G.D. Bouchey, " Cyclic Neutron Activation 70.
Analysis with a Cf-252 Neutron Source", Trans. Am. Nucl. Soc., (October 1971).
71.
E. Linn Draper, Jr., " Integral Reaction Rate Determination Part I:
Tailored Reactor Spectrum Preparation and Measurement" Nuclear Science and Engineering, 46,22,(1971).
72.
E. Linn Draper, Jr., " Integral Reaction Rate Determinations Part II:
Fission Rate Measurements", Nuclear Science and Engineering, 46_,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).
G.D. Bouchey and S.J. Gage, " Neutron Radiography with a Small Subcritical 74.
Reactor", Int. J. of Nondestructive Testing, 2_, 335-353, (1971).
G.D. Bouchey and S.J. Gage, "The Economics of Subcritical Radiography'#
75.
Trans. Am. Nucl. Soc., 14, 123 (1971).
76.
G.D. Bouchey, E. Linn Draper, Jr., and S.J. Gage, " Neutron Radiography with Cf-252:
The Effect of Tailoring Neutron Energy Spectra on Photogrpahic Images", Neutron Sources and Applications, CONF-210402, Vol. 3, Proc. ANS Topical Meeting, Augusta, G'e'orgia, ApTiT~19-21,1971.
~ ~
77.
G.D. Atkinson, Jr., J.B. Whitworth, and S.J. Gage, " Computer-Assisted Analysis of Gamna-Ray Spectra", C_omputer Physics Communications, 2 40-46 2
(1971).
78.
S.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 Systems, and Nuclear Applica-tions, San Antonio, Texas (1971).
79.
G.D. Atkinson, Jr., " Nondestructive Urar,ium Assay by Delayed Gama Ray Analysis Following Californium-252 Neutron Interrogation", Ph.D. Dissertation, The University of Texas, 183 pp., August 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 University of Texas, 223 pp., December 1971.
82.
J.J. Chromik, " Experimental Determination of the Neutron Flux in the University of Texas Californium-252 Irradiation Facility", Masters Thesis, Mechanical Engineering Department, The University of Texas, 85 pp. December 1971.
83.
E. Linn Draper, Jr., Mary Elizabeth Foster and G.D. Bouchey, "X-Ray Fluroescence Analysis and Neutron Activation Analysis in an Analytical Chemistry Laboratory", presented at the Combined Meeting of the Texas Association for Radiation Research and South Central Photobiology Group, Hcuston, Texas, November 5-6, 1971.
84.
F. Linn Draper, Jr. and G.D. Bouchey, "Util ization of a Portable Cali-fornium-252 Source for Neutron Activation Analysis and Neutron Radiography",
Presented at the Combined Meeting of the Texas Association for Radiation Research and South Central Photabiology Group, Houston, Texas, November 5-6, 1971.
85.
E. Linn Draper, Jr. and J.J. Chronik, "Prodaction and Measurement of a Reference Spectrum in a Versatile Experimental Facility", Trans. Am. Nucl.
Soc., Volume 15:1, p. 157, 1972.
86.
E. Linn Draper, Jr. and Andrzej H. Pradzynski, " Identification of Alloys by Energy Dispersive X-Ray Spectroscopy", Ninth Sy posium on Nondestructive Evaluation (1972).
87.
M.B. Owen, " Fuel Management lising Dynamic Programning", Masters Thesis 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.
89.
J.L. Macdonald, " Heuristic Learning Control for Nuclear Reactors" Masters Thesis, Mechanical Engineering Department, The University of Texas,131 pp.
August 1972.
40.
J. Freiri, " Theoretical and Experimental Evaluation of Nuclear Data and (alculation 'echniques for Fusion Reactor Blanket Design", Ph.D. Dissertation, lhe University of Texas, 210 pp., December 1972.
(; l.
S.G. Barbee, "Neutronic Calculations in a Simulated Fusion Reactor Blanket", Masters Thesis, Mechanical Engineering Department, The University of Texas, 259 pp., November 1972.
92.
D.G. Anderson, " Fission Product Mass-Yield Measurements from Intermediate Energy Neutron Fission of Plutonium-239 and plutnnium-241", Ph.D. Dissertation.
The University of Texas, 125 pp., December 19/2.
93.
D.M. Williams, " Identification of Thermal feedback Parameters for a 1RIGA Mark I Reactor", Masters Thesis, Electrical Engineering Department, The University of Texas, 53 pp., December 1972.
94.
G.D. Atkinson, Jr. E. Linn Draper, Jr., and G.D. Bouchey, "Subcritical TRIGA Reactivity Measurer'ents Using the Source Jerk 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 Pulsing TRIGA Mark I Reactor", TRIGA Owner's Conference II, College Station, Texas (1972).
l 96.
G.D. Atkinson, Jr., "A Safeguards Minicourse", 18th Annual Meeting of the American Nuclear Society, Las Vegas, Nevada (1972).
E7.
G.D. Atkinson, Jr., L. Linn Draper, Jr., G.D. Bouchey, and S.J. Gage,
Radioisotopic Source Amplification Using a Heterogeneous Subcritical Assembly",
Froc.18th Annual Meeting of the American Nuclear Society, Las Vegas, Nevada (1972).
98.
E. Linn Draper, Jr., and G.D. Atkinson, Jr., " Transient Rod Failure in a Iulsing TRIGA Mark I Reactor", published in proceedings of 2nd TRIGA Owner's Conference, February 1972.
99.
E. Linn Drapy, Jr., John W. Davidson, S.J. Gage, G.D. Bouchey, "A System f or Reduc tion of A Release from a Research Reactor Facility", Trans. Am.
Nu_cl. Soc., Vol. 15:1, p. 4-5, (1972).
100.
E. Linn Draper, Jr, et.al., " Standard for the Development of Technical I
l Specifications for Research Reactors", Trans. Am. Nucl. Soc., (1972).
c l
(
101.
E. Linn Draper, Jr, G.D. Atkinson, Jr., and S.B. Tomlin, "A Radiography and Capture Gamma Ray Facility for Californium-252" Proceedings of the American Nuclear Society "Applicat ions of Californium-252" National Topical Meeting, September 11-13, 1972.
1
102.
E. Linn Oraper, Jr., G.D. Boucney, G.D. Atkinson, Jr., and S.J. Gage, "A Versatile Subtritical Assembly f or Undergraduate Nuclear Engineering Instruction", Proceedings of the American Nuclear Society " Applications of Californium-252" National Topical Meeting, September 11-13, 1972.
103.
E. Linn Draper, Jr., and S.J. Gage, "The Fusion-Fission Breeder:
Its Potential in a fuel Starved Thermal Reactor Ltonomy", 93rd Annual Meeting of the ASME, New York, New York (1972).
104.
E. Linn Draper, Jr., " Technological Innovatton and Assessment: A Tiovel Course for Nuclear Engineering", Winter Meeting of the American Nuclear Society, November 12-16, 1972.
105.
D.T. Hall, E. Linn Draper, Jr., and P.S. Sc hmidt, " Management of the Transition to Nuclear Power Generation", inhnica' Report ESL-3 Energy Systems Laboratories, Colleqe of Engineering, The University of Texas at Austin, December 1972.
106.
P. S. Sc hmid t a nd G.G. Pa r k, "Hea t Dissipat un in a Power ylant Cooling Bay", ASMF, Paper No. /2-WA/Hl-61, Lvew.ber 1972 107.
P.S. Schmidt and G.P. D' Arch, " Entry Region Fftects on Flow and Pressure Drop of Lithium in fusion Reactor Blankets", Proceedings of the Texas Symposium on Technology of Controlled Therronuclear Fusion Experiments and Engineering Aspects of Fusion Reactors, Austin, Texas (Noverber 20-22,1972).
108.
E. l inn Draper, Jr., Charles Brauer, "L ithium-Lead Collima tor Fabrication for Radioisotopic Source Neutron Radiography,' Trans Am. Nucl. Soc., Vol. 15:1,
~
- p. 142-143,(1972).
109.
E. Linn Draper, Jr., James B. Frein.
Irroretical and Experimental Eval-uation of Nuclear Data and Calculation ii thniquos for Fusion Reactor Blanket Design", Texas Spposium on tho Trrhnolom of Controlled Thermonuclear Fusion Experiments and the Engineer mg Aspects of lusion Peactors, November 20-22, 19/2.
110.
F. l. inn Draper, Jr., "St atus of LIR 4 elated Integral Experiments" pre-sented at the conference on " Nuclear Data and Noutronics of CTR Blankets" held in Seattle, Washington, Septemt1er 19-21, 1972 111.
- f. Linn Draper, Jr "Funion Reactor F ng meering in the Nuclear Engineering Curriculum at The University nt Texas at Austin", Trans. An. Nucl. Soc, (1972).
112 E. 1 inn Draper, Jr., S.J. Gage, "The Fusion-Fission Breeder:
Its Potential in a f uel Starved Thermal Reactor Economy", presented at the l'exas Symposium on the Technology of Controlled Thermonuclear Fusion Lxperiments and the En'lineering Aspec ts of fusion Reactors, November 20-22, 1972.
113. Jares B. Frein, L Linn Dreper, Jr., " Experimental Determination of the fusion Spectrum in Graphite", Trans._Am._Nucl. _ Soc., (1972).
114.
G.D. Atk inson, Jr., 5.J. Gage, G.D. Bouchey, " Cyclic Activation with a Californium-252 Source", Nuclear fechnology (1972).
115.
G.D. At6 inson, Jr., "What Ynu Alwy'. Want ed to Know About Californium Source facilities", invited Ppaor, Natinnal Topical Meeting on the Applications of Californium-252, Austin, Texas (1972).
116.
T.I. Bauer, G.D. Atkinson, Jr., 'Discriminat ion Between Plutonium and Uranium by Gamma Ray Analysis Following Cf-N' Interrogation", National Topical Meeting on the Applications of Californium-i , Mtin, Texas (1972).
117.
E. I inn Draper, Jr., Ed i tor, Proceedinns of lexas_, Symposium on the Tech-nology, of_ Controlled Thennonut lear f usion Exper inwnts and the Engineering Aspects of Iusion Reactors, published by USAIC 118.
E. Linn Draper, Jr., Editor, Proceedinos of the Implications of Nuclear _
Power in Texar, publisned by the Texas Atomic Inergy 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 R Freim, "E sperirental Determination of the Fusion Spectrum in Gr aphite", frans Am um' Soc.,16,9,(1973).
122.
F. Linn Draper, Jr, " fusion Reattor Frqi">ering in the Nuclear Engineer-j ing Curriculun at The University of Texa ; a: Aa;-in", Trans. Am. Nucl. Soc.,
_16, 16 (1973).
123.
E. Linn Draper, Jr., Theodore A. Pari-o, ind drian J. McArdle, "A Neu-tronic-Photon ic Comparison of Vanadium and Niobiun Containing Fusion Reactor Bl ankets", T rans. Am. Nucl. Soc., (Novmber 1973).
124. John H. Vanston, Jr "Use of Partitive Analytical Forecasting (PAF)
Techniques for Fus ion Development Anal ysis", T. r..an.s. Am. Nucl. Soc., (November 125.
TheoJore A. Par
,h and E. Linn Draper, Jr.,
Neutronic and Photonic Analyses of Fusion Reactor Blanket 3 Containing Thorium," Fif th Synposium on Engineering Problems of Fusion Research, Princnton, New Jersey, November 5, 1973.
12h.
C.E. locke and D.R Paul, 'Graf t Copolymer Modification of Poly-ethylene-Polystyrere Cier h I. Gratt Freparation and Characterization".
Journal of Applied Polymer Science, Vol. 17, pp. 2597-2617 (1973. )
12/.
C.E. Locke and D.R. Paul, "Graf t Copolyr,er 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 f ission Product Yields f rom 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 Cora iferations for Controlled Ther-monuclear Reactors", Mast ers Thesis, The Ur'iver nity of Texas at Austin, 154 pp. (May 1973).
130.
"M.E. 5englaub, " Cross Section studies Based on the Statistical Model".
Masters Thesis, The University of Texas at Austin, 109 pp., (August 1973).
131.
E. Iinn Draper, Jr, M J. Voltin, Jr.,
i.!
Mautona ld, C.T. Rombough, I.D. llansborough, 5.G. Itir bee, and J.II. Vans ton, Jr.,
"A University's In-volvement in Mun ic ipa l D. c i s inn-Mal. inq on Notlear Power", Tra ns. Am. Nucl.
' _o_c._, (19/3).
132.
E. Linn Uraper, Jr., J.l Macdonald, and M.J. Vol t in, Jr., " Nuclear vs.
Coal: An Economic Comparison of Power Plant Econunics in Texas", Trans, Am.
Nucl. Soc., (1973).
133.
R.f llenry, " Forensic Applications of Neutrnn Activation Analysis",
presented at the Combinod Meeting of the Texas As',oc iation for Radiation Research and South Central Photobiology Group, San Marcos, Texas, November 9-10, 1973.
134.
G.D. Atkinson, Jr.,
'Tipplications of Neutron Activation Analysis to the Life Sciences", presented at the Con,bined 9eet inq of the Texas Association for Radiation Research and South Cent ral Photchiology Group, San Marcos, Texas, November 9-10, 1973, lE.
5.P Nichols, "l x per nwnla l bt eno inat ion ot' Neutron fermi Age from Calif or nium-262 F iss ion Spectron t o Cadmium Covered Indium Resonance in a Gra phi te Med i um" Ma s te rs Thes i s, The linivers i t y or Texas at Austin,101 pp.,
January 1974.
136.
T.A. Parish, "Neutornic and Pnnt.ome Anal yse, of Sinulated Fusion Reactor Blankets Containing Thorir and Natural Uranium". Ph.D. Dissertation, The University of Texas at Austin, 3P9 pp. January 1974 137.
J.H. Vanston, Jr., "Use of the Part i tive Analyt ical Forecasting (PAF)
Technique for Analysis of the Ef f ect s of Various Fundin(; and Administrative Strategies on Nuclear f usion Power -lant Developr"ent", Pn.D. Dissertation, The Unive+mity of Texas at Austin, 459 np., January 1974 130.
E.M. B. Sorensen, "Thernal f f f ortr on the Biological Magnification of Arsenic in Green Sunfish, lej omis Cyanyl his" Ph.D. Dissertation, The Univer-sity of Texas at Aust in, 233 pp., Ma y 1974.
139.
E. Linn Draper, Jr., and J.R. Deen, " Measurement of Fission Product Yields frmi Thorium-232 in a Californium-252 Fission Neutron Spectrum", Trans. Am.
Nucl. Soc., 17, 531 (1973).
140.
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).
141.
E. Linn Draper, Jr., and T.A. Parish, "Neutronic and Photonic Analyses of Fusion Reactor Blankets Containing Natural Uraniun", CONF-740402, 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", PRDC. IEEE 1973 NUCLEAR SCIENCE SYMPOSIUM, San Francisco, California (19B T -
143.
G.D. Atkinson, Jr., and R.E. iienry, " Neutron Activation Analysis:
Envirorunental and Biological Applications", Sixth Annual Meeting of the Texas Association for Radiation Research, San Marcos, Texas (1973).
144.
M. Etzion, R.G. Spangler, L. 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 and 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. Olan D. Thompson, "Uptimizat ion of Shipping Containers for Radioisotopic Neutron Sources", Masters Thesis, Mechanical Lngineering Department, The Uni-versity of Texas at Austin, 30 pp., ( August 1974).
148.
J.R. Deen, E. Linn Draper, Jr., " Measurement of the Fission Product Yields and the Energy Integral Fission Cross Section of Thorium-232 in a Cali-fornium-252 Fission-Neutron Spectrtr., Nuclear Technology, 25, 416 (1975).
149.
E. Linn Draper, Jr, i. A. Parish, M. Etzion, " Utilization of a Small Accelerator for Fusion Reactor Blanket Design", Proceedings _o_f the Third Small Accelerat_or Conference, USAEC, CONF-741021 (1974).
ISD.
R.G. Spangler, E. Linn Draper, Jr., T.A. Parish, "14 MeV Cross Section Measurements of Threshold Reactions far Seven Metals", Trans. Am. Nucl, Soc.,
~ ~ ~
22, 818 (November 1975).
l 1
1
W.R. Smith, Jr., E. Linn Draper, Jr., " Measured and Calculated fast 151.
fleutron Spectra in a Graphite Medium". Trans. An. Nucl. Soc., 2_2, 800 2
(November 1975).
J.W. Davidson, E. Linn Draper, Jr., " Costs for Partitioning Strategies 152.
involved in High-level Nuclear Waste Management", Trans. Am. Nucl. Soc., 22, 348 (Noven.ber 1975).
M.J. Voltin, Jr., E. Linn Draper, Jr., " Sensitivity of Total Fuel Cycle 153.
Cost to Variations in Enrichment Tails Assay Strategies", Trans. Am Nucl. Soc.,
_22, 322 (November 1975).
T. A. Parish, J.W. Davidson, E. L inn Draper, Jr., " Transmutation of 154.
fission Products in fusion Reactor Blankets", Tr,ans.. Am. Nucl. Soc._, 22, (November 1975).
T.A. Parish, J.W. Davidson, E. Linn Draper, Jr., "The Effects of the 155.
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).
Pradzynski, R.E. Henry, J.L.S. Stewart, " Determination of Selenium 156.
A.H.
in Water on the ppb Level by Coprecipitation and Energy Dispersive X-Ray Spectrometry", Radiochem. Radioanal. Letters, 21(5) 277-285 (1975).
B.E. Bulla, E. Linn Draper, Jr., R.E. Henry, M.J. Vol tin, Jr., et.al.,
157.
Texas Nuclear Power Policies: A Study of Alternatives, Volume II: Methodology.
The UnTvir~sity of"TW as at Austin Center for Energy Studies, Pol icy Alternative
~
~
~
Study No.1 (1975).
A.H. Pradzynski, R.E. Henry, J.L.S. Stewart " Determination of Transition 158.
Metals by Radioisotope-Excited Energy Dispersive X-Ray Spectrometry",
Trans. Am. Nucl. Soc., 21, No. 3 34-35 (1975).
A.H. Pradzynski, R.E. Henry, J.L.S. Stewart, " Nondestructive Determination 159.
of Toxic Elements in Toys", Proc. of 10th Symposium on Nondestructive Elements, San Antonio, Texas, 257-265 (April 23-25, 1975).
R.E. Henry, " Determination of ppb Levels of Selected Elements in Natural 160.
Water Using Radiosiotope-Excited Energy Dispersive X-Ray Fluorescence Analysis",
presented at the Eighth Annual Meeting of the Texas Association for Radiation Research, Austin, Texas (October 31 -- November 1, 1975).
Nichols, " Application of the Partitive Analytical forecasting (PAF) 161.
S.P Technique to the United States Controlled Thermonuclear Research Effort,"
Ph.D. Dissertation, The University of Texas at Austin (December 1975).
162.
C.T. Rombough, "The Total Energy Investment in Nuclear Power Plants",
Ph.D. Dissertation, The University of Texas at Austin, (January 1975).
J.L. Macdonald, " Investigation of Pattern Recognition Techniques for the 163.
Identification of Splitting Surfaces in Monte Carlo Particle Transport Cal-culations", Ph.D. Dissertation, The University of Texas at Austin ( August 1975).
J.W. Davidson, "A Cost-Benefit Analysis for Partitioning Strategies In-164.
volved in liigh-Level Nuclear Waste Management", Masters Thesis, The University of Texas at Austin, (May 1975).
T. A. Parish, J. W. Davidson, and E. Linn Draper, Jr., "The Minimization 165.
of the Hazard Resulting f rom Transmutation of Fission Products," Transactions of the American Nuclear Society, 23_, 59, June 1976.
T. A. Parish, " fusion-Fission liybrid Studies at The University of Texas,"
166.
U.S.-U.S.S.R. Symposium on Fusion-Fission Reactors, Lawrence Livermore Labora-tory, July 1976.
T. A. Parish, J. W. Davidson and E. Linn Draper, Jr., "Neutronic Perfor-167.
90 and 1129," Second mance of Graphite Fusion Reactor Blankets Containing Sr ANS Topical Meeting on the Technology of Controlled Thermonuclear Fusion, Richland, Washington, September 1976.
T. A. Parish, J. W. Davidson and J. B. Cornwell, "The Effectiveness of 168.
fusion Reactor Transmutation Waste Management Program," Transactions _
a Sr90 of the American Nuclear Society, 2_4, November 1976.
A. H. Pradzynski and J. R. Rhodes, " Development of Synthetic Standard 169.
Samples for Trace Analysis of Air Particulates," ASTM Special Technical l
Publication No. 598, 1976, pp. 320-336.
A. H. Pradzynski, R. E. Henry and J. S. Stewart, "DeterTaination of PPB 170.
Concentrations of Transition Metals by Radioisotope-Excited Energy-Dispersive 3_2,1976, p. 219-28.
2 X-Ray Spectrometry, Journal of Radioanalytical Chemistry, A. H. Pradzynski, R. E. Henry and E. L. Draper, Jr., " Determination of 171.
PPB Concentrations of Uranium, Thorium and Molybdenum in Water using APDC Preconcentration and Radioisotope Excited X-Ray Emission Spectrometry,"
Proceedings of ERDA Symposium on X-and Gamma-Ray Sources and Applications, Ann Arbor, Michigan, May 19-21, 1976, pp. 175-177.
A. H. Pradzynski, R. E. Henry and E. L. Draper, Jr., " Determination of 172.
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, 24,
~~
1976, p.
119.
173.
R. R. Gay, G. 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).
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).
Rodney R. Gay, " Reactor Hydrodynamics During the Reflood Phase of a loss-of-Coolant Accident," f;uclear Technology, Vol. 36, No. 2, Dec.1977, pp. 229-237.
175.
D. L. Klein, S. R. Bull, and J. B. Miles, " flow Visualization Around GCFR 1/6.
f uel Rod Roughness Elements," Trans. Am. Nuclear Soc., 28_, June,1978.
D. E. Klein, S. R. Bull, and J. B. Miles, " Pressure Drop for GCFR Fuel 177.
Rod Rouqhness Elements," Trans. Am. Nuclear Soc., 30, November 1978.
E. M. B. Sorensen, R. E. Henry and R. Ramirez-Mitchell, " Time Dependent 178.
localization of Arsenic in Subcellular Hepatocyte fractions," J. of Pathology and Toxicology, Vol. 2, No. 4, 1979, pp. 1161-1171.
E. M. B. Sorensen, R. E. Henry, and R. Ramirez-tiitchell, " Arsenic Accumula-1/9.
tion, Tissue Distribution, Cytotoxity in Teleosts following Indirect Aqueous 21, 1979, Exposure," f,ulletin of Environmental Contaninatipn and Toxicology _, Vol.
pp. 167-169.
" fission Product Toxicity Reduction via 180.
J. W. Davidson and T. A. Parish, Transmutation Using D-T Iusion Neutrons," Eight Symposium on Engineering Problems of Fusion Research, San Francisco, California, fiovember 1979.
J. M. Davidson and T. A. Parish, "An Evaluation of the Requirements and 181.
Perf ormance of a Transmutation Uaste Managerent System, Trans. Am. Nuclear Soc.,
33, November 1979,
- 5. A. Hodge, J. P. Sanders, and D. E. Klein, " Determination of Friction 182.
f actors and Heat Transfer Coef ficients for flow Past Artifically Roughened Surfaces, Oak Ridge National Laboratory Report, OPNL-5599, November 1979.
D. E. Klein, " Nuclear Problens and Prospects," National Energy Policy 183.
Issues, Council on Energy Resources, The University of Texas at Austin, May 1979.
D. f. Klein, H. H. Woodson, and J. U. Davidson, "Corrercial Nuclear Power IM.
Generation," Council on Energy Resources, The University of Texas at Austin, June 1979, E.11. B. Sorensen, R. R. Mitchell, A. Pradzynski, T. Bauer and L. Graham, 185.
I "Morphometric Analyses of Arsenic-induced Histopathological Changes in Parenchymal Hepatocytes," Tennessee Academy of Science Annual Meeting, Nashville, TN, November 16-17, 1979.
A. H. Pradzynski, " Determination of V and Ba in Marine Sediments and 186.
Biota," Internal Report, Nuclear Engineering Teaching Laboratory, The University of Texas at Austin, Departrient of Mechanical Engineering (1979).
N. E. Hertel, B. W. Wehring, and J. J. Dorning, " Integral Test of 187.
ENUf/B-IV High-Energy Neutron Cross Section Data for Tungsten," Trans. Am.
Nucl. Soc. 32, 631 (1979).
l 188.
R. H. Johnson, K. R. Koch, B. W. Wehring, and N. E. Hertel, "TDL Measure-l cents in an Iron Sphere Containing a DT Source," Trans. Am. Nucl. Soc. 32, 632(1979).
189.
B. 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 B. 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 EbTication #594, pp. 568-571.
191.
N. E. Hertel, B. W. Wehring, " Absolute Monitoring of DD and DT Nuetron 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 Dinensionless Velocity Profiles for Artificially Roughened Surfaces, I_nt. 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 bbasured in a Tissue-Equivalent Medium Irradiated with Neutron Radiotherapy Sources," Trans. Am. Nucl. Soc. 35, 457 (1980).
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 21-26, 1981.
195.
D. E. Klein, S. R. Bull and J. B. Miles, 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., 34, June 1980 (invited).
197.
R. B. Pope, H. R. Yoshimura, J. E. Hamann, and D. E. Klein, "An Assessnent of Accident Therral Testing and Analysis Procedures for Radioactive Materials Shipping Package," ASME 80-HT-38, April 1980.
198.
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 Ra ilcar/ Cask System, " Paper #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.
200.
J.W. Davidson and D. E. Klein (co-editors), Proceedings of the International Conference on Nuclear Waste Transmutation, University of Texas Press, March 1981.
w-e-
wi-
+
y-m-r r-
l l
l 201.
M. A. Ross and D. E. Kleir., " Synthetic Fuel Production Using Texas Lignite and a VHTR for Process Heat," Number 3, March 1982, Nuclear Technology, Vol. 56, 202.
T. L. Sanders and D. E. Klein, "A Modified Numercial Schene 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," accepted for publication in AIAA Journal.
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