ML20248A097
| ML20248A097 | |
| Person / Time | |
|---|---|
| Site: | 05000192 |
| Issue date: | 12/31/1988 |
| From: | Bauer T, Klein D TEXAS, UNIV. OF, AUSTIN, TX |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 8904100138 | |
| Download: ML20248A097 (68) | |
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.--ee NUCLEAR REACTOR LABORATORY TECHNICAL REPORT v
THE UNIVERSITY OF TEXAS COLLEGE OF ENGINEERING DEPARTMENT OF MECHANICAL ENGINEERING
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8904100138 881231 PDR ADOCK 05000192
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1988 ANNUAL REPORT i
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of The University of Texas at Austin Nuclear Engineering Teaching Laboratory i
Taylor Hall Room 104 I
l January 1, 1988 - December 31, 1988 D. E. Klein, Directo 512/471-5136 T. L. Bauer, Supervisor 512/471-5787 January 1989 1
4
_____________~_______-__._w
1988
' TABLE OF CONTENTS
-l List of Tab 1es...................................
3 List of Figures..................................
4 a
I.
Introduction.................................s...
5 II.
Laboratory Administration........................
9 A.
Organization e
B.
Personnel C.
Committees
' 4 0.'.
College Report
]
III. Laboratory Development..........................
14 -
'I l
l l
A.
Organization
{
B.
Nuclear Engineering Teaching Laboratory C.
haclear Reactor Laboratory D.
Neutron Activation Analysis Laboratory E.
Nuclear Radiation Laboratory 1
l IV.
Facility Operations Summary.....................
17 1
A.
Operating Experience
~B.
Reactor Shutdowns I
C.
Reactor Utilization D.
Reactor Maintenance l
E.
Facilicy Changes F.
Area Radiation Surveys G.
Radioactive Effluents and Waste V.
Laboratory Inspections..........................
30 i
A.
NRC Inspections B.
TDH Inspections VI.
Public Service Activities.......................
31 l
VII. Research Activities.............................
32 VIII.
Publications from the Nuclear Engineering l
Teaching Program...........................
39 l
A.
Ph.D. Dissertations l.
B.
Masters Thesis l
C.
Reports and Papers 1
I l-2 t
1988 List of Tables Table No.
Page
~
1.
Administration and Committees 11 2.
Facility Personnel 12 3.
University Courses 16 4.
Reactor Safety System 18 5.
Safety System Events 18 6.
Performance Data 19 7.
Annual Utilization Dats 20 8
Summary of Personnel Radiation Exposures 25 9.
Radiation Exposure Groups 25 10.
Laboratory Radiation Levels 26 11.
Laboratory Contamination Levels 26 12.
Environmental Surveys 27 13.
Monthly Gaseous Waste Discharge 28 14.
Monthly Liquid Waste Discharge 29 15.
Monthly Solid Waste Disposal 29 16.
Research Funding 33 3
v 1988 List of Figures Figure No.
Page 1.
Site Location of Nuclear Engineering
. Teaching Laboratory 7
2.
Floor Plan of Nuclear Engineering Teaching Laboratory.
8 3.
Organization Chart of the Nuclear Engineering Teaching Laboratory.
10 4.
Annual Burnup versus Operntion Year 22 5.
Samples Irradiated versus Year 22
]
i 9
e 4
1988 I.
INTRODUCTION 1
The Nuclear Engineering Teaching Laboratory (NETL) at The University of Texas at Austin prepares an annual report to provide
~
information about program activities.
Information in this report satisfies the requirements of the U.S. Nuclear Regulatory Commission (NRC) docket number 50-192 and the U.S. Department of Energy contract number DE-Ac07-ER03919 Amendment A015. The report covers the period from January 1, 1988 to December 31, 1988.
Activities of the NETL program are part of the College of Engineering Department of Mechanical Engineering. Development of the nuclear program by the university began in the years prior to 1960, with the location of most of the program activities in one of the original engineering buildings. Building space in Taylor Hall provides classroom, laboratory and office areas.
By the year 1985 the nuclear program was the only engineering program still functional in the building that has become the location of the College of Natural Sciences Department of Computer Science. Building areas are also the location for parts of the University Computation Center and some other university groups.
Most NETL program laboratory activities are at two locations in Taylor Hall.
Floor plans of these two laboratory areas, a Nuclear Reactor Laboratory and an Activation Analysis Laboratory, are shown in Figures I and 2.
The Nuclear Reactor Laboratory is the site of a TRIGA Mark 1 reactor that operates in steady-state and pulse modes. Power operation of the reactor is at 250 kilowatts steady-state and approximately 250 megawatts pulse. At the time of initial facility acceptance the power level was at 10 kilowatts. The Activation Analysis Laboratory provides gamma spectroscopy systems for analysis of neutron activation reactions. These reactions are products of irradiation experiments in reactor experiment facilities. Data acquisition and analysis is done with high efficiency, high resolution detectors.
Intrinsic purity germanium detectors provide radiation detection with automatic control and acquisition systems run by microcomputers.
Other NETL program laboratory activities are at locations in the Engineering Science Building. This building provides a multipurpose facility for several engineering and science programs. A Nuclear Radiation Laboratory provides an experiment facility for flux and energy measurements of neutrons from fusion, fission, and other neutron production reactions. Three sources available are the D-T reaction from a Cockcroft-Walton type accelerator, spontaneous fission reaction from the isotope californium-252 and the alpha-neutron reaction from plutonium-beryllium. Activities of the laboratory include detection, measurement and analysis.
NETL program equipment and materials provide support for different types of facility activities.
Supplemental equipment and radioactive materials include a subcritical assembly, gamma irradiator, portable x-ray unit and various isotopic radiation sources.
Equipment, instrumentation systems and detection devices for monitoring, 5
a 1988 measurement and calibration of ionizing radiation are in routine use or available for special applications.
Radioactive material inventories contain radioisotope sources for gamma rays, neutron emissions, x-ray excitation, and reference standards for several types of experimental programs.
Developmental goals of university and engineering programs have been the major cause of change to the NETL program.
Initiation of a project to move activities of the NETL program to the Balcones Research Center (BRC) began,in October.1983 and should be completed in August 1989. The program move is in response to needs of the main campus for expansion of other educational programs, addition of research facilities, and the development of the research center into a major research site for science and engineering.
A Dismantling and Decommissioning Plan (DDP, docket 50-192) for the Taylor Hall facility was submitted to the Nuclear Regulatory q
Commission (NRC) on May 3, 1985. An order to authorize the activities that will lead to the license termination was issued on March 9,1987.
Project plans indicate that the DDP activities will occur in the last quarter of 1989 or first quarter of 1990.
Project authorization to move NETL program activities to the Balcones Research Center (BRC) site was approved by The University of Texas System Board of Regents on October 13, 1983. A submittal for a i
construction permit and an operation license was made to the Nuclear Regulatory Commission on November 9, 1984.
Subsequent to a site visit on January 22 thru 24 a license amendment was requested on February 27, and responses to NRC questions were prepared. The construction permit l
was issued June 4, 1985.
Preliminary architectural and engineering plans were approved by The University of Texas System Board of Regents on August 8, 1985.
Final plans were approved on April 10, 1986 and the bid to a general contractor was awarded on December 4, 1986.
CIT Construction Inc. of Stafford, Texas, was specified as the general contractor and start of construction was recorded on February 10, 1987. Facility completion was scheduled for 16-18 months after start of construction. A project delay of approximately 8 months has occurred because of problems with the general contractor.
The Balcones Research Center facility will provide laboratories for the TRIGA reactor, a neutron generator, radiation measurement systems, preparation and processing of radioactive samples, and office space.
Although the facility will move the present TRIGA facility and other program activities into a single building at the Research Center, several improvements to the reactor facility will extend facility capability. These include above ground shield structure for access to horizontal beam tubes, and an increase of power and pulse parameters.
Plans are to utilize the present fuel and move some other components from the old to the new facility. A few components such as control rod drives will be subject to rework procedures to assure appropriate functional operation. Many components such as reactor structure, instrumentation, and control system will be new components.
6
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Figure 2 Floor Plan of Nuclear Engineering Teaching Laboratory 8
l 1988 II.
LABORATORY ADMINISTRATION A.
Organization The present organizational chart of the NETL program is presented in
~
Figure 3.
Budgeted NETL staff funding is provided for a Supervisor / Assistant Director, research associate, technician / operator, operator, and secretary. Budget support is divided into full time positions for supervisor, reactor operator, research associate; half time for a technician; and secretary.
B.
Personnel Personnel associated with the laboratory consist'of NETL staff, f
faculty, students, and certain other university personnel. The personnel involved in the NETL program during the past year are i
summarized in Table I.
C.
Standing Committees Two committees monitor the activities of the NETL programs. The Nuclear Reactor Committee functions through the College of Engineering and the Radiation Safety Committee functions through the Office of the President.
1.
Nuclear Reactor Committee The Nuclear Reactor Committee convened to review the activities related to facility operation during each quarter of the calender year.
Committee meeting dates were April 29, July 20, October 12 and January 31, 1989. The committee composition 10 shown in Table 2.
Committee responsibilities are the reactor operation, associated facility activities and engineering programs.
2.
Radiation Safety Committee The Radiation Safety Committee convened to review radiological safety practices at the university during each academic term. Committee meeting dates were April 12, 1988 and November 10, 1988. The committee composition is shown in Table 2.
Committee responsibilities are the activities of university research programs that utilize radiation source materials.
O 9
1988 i.
~
Office, President University of Texas at Austin Radiation Safety Committee j
l Executive Vice President I
and Provost Dean l
College of Engineering I
i l
Nuclear
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i Reactor l
Committee y
I i
Chairman j
Department of 1
l Mechanical Engineering i
I i
Director l
Nuclear Engineering.
l Teaching Laboratory i
I Supervisor Reactor Operations l
l Responsibility l
Communication Figure 3 Organization Chart of the Nuclear Engineering Teaching Laboratory
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10
-m.
1988 Table 1 Administration and Committees Administration
~
The University of Texas System Board of Regents Chairman Jess Hay.
.Vice Chairman R.B. Baldwin III Vice Chairman S.H. Ratliff Executive Secretary A.H. Dilly Member (1989)-
Member (1991)
Member (1993)
R.B. Baldwin III J.S. Blanton Sam Barshop j
Jess Hay S.H. Ratliff A. Beecharl Jr.
Mario Yzaguirre Bill Roden W.A. MoncrieffJr.
Chancellor Hans Mark The University.of Texas at. Austin
' President (app. 9/1/85)
William H. Cunningham Executive Vice President and Provost (app. 9/1/85)
Gerhard J. Fonken Dean of the College of Engineering Herbert H. Woodson (app:
9/1/87)
Chairman of Department of Mechanical Engineering John R. Howell (app:
9/1/87)
Nuclear Reactor Committee Chairperson:
H. L. Marcus (app: 9/1/77)
Member:
N. E. Hertel (app: 4/1/79)
Member:
D. E. Klein (app: 9/1/77)
Member:
J. O. Ledbetter (app: 9/1/71)
Member:
L. Rabenberg (app: 9/1/87) j Member, student:
R. D. Manteufel (app: 9/1/85,
)
8/31/88)
{
Member, student:
A.S. Heger (app: 9/1/88)
Ex officio member:
T. L. Bauer (app: 6/1/78)
Ex officio member:
H. W. Bryant (app:-11/1/73)
Ex officio member:
H. H. Woodson (app: 9/1/87)
Ex officio member:
J. R. Howell (app: 9/1/87)
Radiation Safety Committee Chairperson:
E. L. Sutton (app: 9/1/84)
Member:
K. J. Caskey (app:-9/1/83) mber:
G. W. Heffman-(app: 9/1/84)
Member:
D. E. Klein (app: 9/1/83)-
Member:
S. A. Monti-(app: 9/1/85)
Member:
L. O. Morgan (app: 4/1/75)'
Ex officio member:
H. W. Bryant (app: 11/1/73)
Ex officio member:
W. H. Cunningham (app: 9/1/85) i 11 3
1988 q
l
. Table.2 Personnel Facility Personnel J
1 Staff
(
Director D.E. Klein Assistant Director / Supervisor T.L. Bauer l
Research Associate F.Y. Iskander i
Nuclear Technical Specialist M.G. Krause Technical Secretary Sr. Office Assist.
D.L. Wood, J. Rawlings Laboratory Research Assistant L. Polchiopek Laboratory Research Assistant R. Manteufel Support Personnel l
Safety Personnel Safety Coordinator.
H.W.Bryant Radiation Safety Specialist L.W. Hamlin.
Researchers College of Engineering T.L. Bauer Nuclear Reactor Lab.
F.Y. Iskander Neutron Activation Lab.
Research Associate N.E. Hertel Nuclear Radiation Lab.
Assoc. Prof.
University Departments J.H. Freeland Home Economics Assoc. Prof.
l l
P. Schmidt Hech. Engineering Assoc. Prof.
Students Engineering University Graduate Assistants R. Hartley F. Behmardi D. Smith D. Durbin A. Patterson-Hine H. Lo R. Savage R. Manteufel l
A. Heger Student Assistants l
L. Polchlopek R. Manteufel
[ -
l 12
1988 D.
Report to the College of Engineering Each year the Reactor Committee provides a report to the Dean of the Co))ege of Engineering describing activities of the committee and a review or assessment of the operation of specific portions of the NETL program concerning the reactor and other radiation producing equipment.
Harris Marcus, Reactor Committee Chairman, summarized the activities I
during this period :
There are two sets of minutes for this years quarterly meetings.
Docket 50-192 deals with the ongoing operation in Taylor Hall and Docket 50-602 deals with the construction of the new facility at Balcones Research Center. The specific items of interest are the following:
1.
A major portion of the effort in the program continues to be associated with the development of a reactor facility at the Balcones Research Center as wc)) as for decommissioning arrangements of the existing facility. Plans have progressed in an orderly manner and have been coordinated with NRC personnel. A contract award for the new facility was made December 4, 1986. On March 9, 1987 authorization for dismantling the Taylor Hall facility was received from the Nuclear Regnlatory Commission.
2.
For another year the reactor remained operating efficiently while construction and destruction continued all around it.
The level of reactor activity for the year was comparable to previous years. Recently, additional neutron activation studies have been initiated with an increase in reactor usage. This was accomplished.
in spite of the very heavy additional work load associated with the new facility and setting up the dismantling of the old reactor.
It is imperative that the personnel involved with the Nuclear Engineering Teaching Reactor be given additional staff support during the construction phase and dismantling phases. With the larger amount of licensing activities a great deal more NRC contact will be required during this period and it is vital that we continue to proceed in an orderly manner.
Note: Bids for the facility at the Balcones Research Center were opened October 21, 1986 and award of the general contract was approved December 4, 1986. The University of Texas System Board of Regents entered into a contract with CIT Construction Inc. of Stafford, Texas. Total project cost for the proposed facility was
$5,452,560. An additional $408,140 is being held in reserve for dismantling activities at the Taylor Hall facility. Authorized total cost is $5,860,700.
4 13
-v 1988 III.
LABORATORY DEVELOPMENT A.
Organization Dr. Dale E. Klein continued as the Director and Dr. Thomas L. Bauer continued as Reactor Supervisor / Assistant Director during the past year.
I The changes made in the facility staff.during the 1988 calendar year were in the area of part time student research assistants, and' l
secretary support. Roger Manteufel was added as a part time Nuclear Technical Specialist I.
As a full time Senior Office assistant, Jan Rawlings, replaced Diane Wood to assist with preparation of license documents.
The Nuclear Reactor Committee remained unchanged with the exception of the appointment of one additional member.
Dr. H.H. Woodson has J
assumed the role of Dean of the College of Engineering.
Dr. J.R. Howell has remained as chairman of the Department of Mechanical Engineering.
Dale Klein has been appointed Associate Dean for Research in the College j
of Engineering and continues to function as Director of the NETL
)
program.
4 B.
Nuclear Engineering Teaching Laboratory The Nuclear Engineering Teaching Laboratory is part of the Nuclear l
Engineering Program at The University of Texas.
The Nuclear Engineering Teaching Laboratory'e central feature is a Mark I TRIGA thermal fission reactor. Originally licensed by the Atomic Energy Comm16sion to operate at 10 kw in 1963, the nuclear reactor and the associated laboratory equipment have been updated over the past years and the research capabilities of the Laboratory are now more diverse.
In 1968, the facility license was amended to allow the TRIGA reactor to operate at a steady state power level of 250 kw which increased experimental capabilities.
Routine operations of the reactor were terminated on April 30, 1988 in preparation to move facility operations.
Other radiation producing devices maintained by the Laboratory are a 750 curie Co-60 irradiator, vertical neutron beam tube, suberitical assembly, industrial x-ray source, 14 MeV neutron generator, and several isotopic neutron sources. Different types of radiation detection devices provide the capacity to monitor or analyze the various radiation sources.
I One of the functions of the nuclear reactor and its associated i
equipment has been to teach and demonstrate the fundamentals of reactor operation. Another function has been the demonstration of specific applications of nuclear technology.
Several organized classes routinely utilize the reactor facility and a few others use the facility on an infrequent basis. Courses utilizing the reactor and associated facilities are listed in Table 3.
Classes, organizations and groups are provided tours or demonstrations of the reactor and its associated experimental facilities. Approximately 815 persons were admitted into the reactor facility during the past year.
14
1988 The use, operation, regulation and inspection of the Nuclear Engineering Teaching Laboratory is controlled by the United States Muclear Regulatory Commission, the Nuclear Reactor Committee of The University of Texas, the Director of the Nuclear Engineering Teaching Laboratory, the Radiation Safety Committee and the Texas Department of Health Division of Radiation Control.
C.
Neutron Activation Analysis Laboratory l
t The Neutron Activation Analysis Laboratory has provided nuclear analytical support for individual projects ranging from student project i
support for classes to measurements for faculty research projects.
Student project support is in the areas of engineering, chemistry, physics, geology, biology, zoology, and other areas. Research project support includes elemental measurement f'or environmental and investigative research projects. Scientific articles based upon the results of sponsored and non sponsored research by this laboratory have been published or accepted for publication in several journals and proceedings, and have been presented at conferences at the state, national and international level.
Radiation measurement systems available include gamma ray spectroscopy with two HpGe detectors coupled co a microcomputer controlled acquisition and analysis system, Si(Li) detector and multichannel analyzer for X-ray measurements, alpha-beta proportional counter, scintillation detectors, neutron detectors and associated electronic modules to accomplish several types of standard nuclear measurements. An important function of the laboratory is to support various research applications with the neutron activation analysis method or other techniques related to nuclear radiation measurements.
D.
Nuclear Radiation Laboratory The Nuclear Radiation Laboratory is utilized by staff and students of the Nuclear Engineering Program at The University of Texas at Austin.
The laboratory is located in an area of the Engineering Science Building. A 14 MeV Texas Nuclear neutron generator is the main feature of the laboratory. Three californium-252 neutron sources are also available for use.
The facility, with installed shiciding, provides an area where students and staff can perform experiments utilizing not only the high energy neutrons from the neutron generator but fissicn 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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I 15
1988 Tabic 3 Courses Utilizing the Reactor and Associated Facilities Course Number Course Description Mechanical Engineering Department l
ME 361F Introductory Nuclear Laboratory - studias in radioactive decay, activation, detection and measurement.
ME 361G Reactor Operations - studies in nuclear reactor parameters, instrumentation characteristics and l
regulation.
ME 377K Projects in Mechanical Engineering - individual study and experiment projects for undergraduates.
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 studies as a summer course for foreign students.
ME 397 Current Studies in Engineering - special projects course for graduate 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 in civil engineering 16
1988 IV.
Facility Operations Summary A.- Operating Experience During the period no significant deviations from normal operating conditions were observed. Pulse reactor operation remained suspended.
Established operating procedures and other required procedures remained unchanged.
Routine reactor operation was terminated at the end of.the first calender quarter of the year. No power operation was performed in-the last 3: quarters of the year. -Fuel was subsequently removed'from the B-E rings of the core.
During this period until fuel is removed from the docket 50-192 facility to the docket 50-602 facility fuel is to'be j
stored in pool storage racks and the.F-ring of the reactor pool.
Estimates and measurements of the reactivity establish the configuration j
to be a Keff < 0.8.
Control rod drives have been removed for complete repairs and refurbishment. These. drives are still insta11able in the docket 50-192 facility although the intention is to transfer them to the docket 50-602 f
installation.
Licensed activities were performed by two persons with Senior Operator Permits, T.L. Bauer and M.G. Krause. Operating. activities were in support of reactor operations, nuclear engineering, sample irradiations, research and education or demonstrations. No new i
experiments were proposed or approved.
Excluding operation for demonstration, instruction, routine surveillance, or isotope production, the major experiment performed was neutron activation to support various j
research activities. Maintenance during the period consisted primarily 4
of routine equipment repair and adjustments.
11 Reactor Shutdowns Keactor shutdowns (scrams) occurring during the reporting period are cummarized in Table 4, categorized according to the type of initiating event. Safety system scrams are protective actions to shutdown the reactor that are caused by the proper operation of the safety system but are not the result of an operator error or an intentional action of the operator. Operator error scrams are the result of judgement errors or procedural errors.
Instrument and power failure scrams are protective actions that result from loss of safety system function.
Intentional scrams are operator initiated scrams such as tests. Manual action scrams are classified either safety or intentional as determined by the cause of the manual scram actio'n.
Inadvertent scrams are all i
unintentional shutdowns of the reactor by the~ protective action of the safety system. Table 5 compares the number of inadvertent shutdowns during this reporting period to previous reporting periods.
6 k
17
1988 Table 4 Reactor Safety System (scrams)
Safety System 0
Operator Error 0
Instrument Error 1
Power Failure 0
Subtotal 1
Intentional 3
Total 4
I l
1 1
Table 5 l
Safety System Events (inadvertent) 1 1971 13 1981 7
1 1972 6
1982 6 1963 10 1973 10 1983 6
{
1964 9
1974 4
1984 5 i
1965 3
1975 7
1985 2 1966 4
1976 5
1986 9 1967 3
1977 9
1987 2 1968 11 1978 11 1988 1 1969 15 1979 12 1970 11 1980 7
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18
v 1988 Table 6 j
Performance Data 1988 Reactor Operation Hours, Fuel Burn-up and Irradiated Samples Quarter Reactor Total Burn-up Samples Operation Fuel Irradiated (hours)
(kwhrs)
(number)
First 78.6 15872 407 Second 58.9 8385 534 i
Third 5.3 0
0 Fourth 4.3 0
0 Total 147.1 24257 941
{
1 l
Notes:
(1) Reactor operation hours record the console key on time or the l
time power is applied to the rod control system. Third and Fourth l
greater operation time attributed to fuel movement activities this l
reporting period.
l (2) One full power hour is 250 kilowatt-hours.
(3) Samples that are irradiated in the experimental facilities of the reactor such as the RSR, PNT or CT.
l 19
v
-o 1988-1 Table.7 Annual Utilization Data Year
' Reactor Total Burn-up Samples
. Operation Fuel.
Irradiated i
(hours)
(kwbrs)
(number)
-l
~-
1967 154.5 846 265 1968 342.6
-28168 2449 1969 260.8 49985 1452 1970 222.0 36477 1640 1971 262.5 53912 2990
'1972 222.8 48389' 1946 1973.
318.6-
'45794 1347 1974-226.5 27641 778-1975 207.0 20450 363 j
1976 135.7 11312 468-1977 139.3 7509 164 1978 171.9 26870 178 1979 311.6 72616 1568 1980 184.1 11760 150
~
1981 258.5 18165 330 1982 247.6 16150 294 1983 260.2 24028 477-1984 179.6 24806 667 1985 139.9 18607 473 1986 183.1 18660 633 1987 293.9 43786 1394 1988 147.1 24257 941 Total 4869.8 630188 20967 j
J Note:
(1) Data for 1967 includes all data recorded for previous operation i
at.10 kW from 1963-1967.-
(2) Operation power of 250 kilowatts was initiated in 1968.
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_ _ _ _ _ _ _ - _ - - _ _ _ - _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ~
y 1
1988 C.
Utilization I
Reactor utilization data for this reporting period is 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'are shown in Figures 4 and 5.
D.
Maintenance During this reporting period maintenance consisted primarily of routine repair and adjustment.
E.
Facility Changes Operation of the reactor in the pulse mode remains discontinued until the operation characteristics of the compensated chamber as related to pulsing is established. This evaluation is not planned since current activities of the facility do not require-pulsing and no pulsing.
is planned before moving to the new facility at BRC.
No other facility changes tere made during this reporting period.
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21
m p-l 1988 BuPnuP o
(themsenJsl Total Year so-so-3 a-Fl o n m
i a-nnnonnn n
l s, se e, n n n n n n n n n n u n : nnesunu Annual Burnup versus Operation Year Figure 4
+
P Samples I
a retai rea, j
35ee-3eGe-1 25M 4 i
gue.
1 15M.
sese-i I
n n r, r, n n n fl n fl n
9 47 se 69 7e 7 72 n 74 7s M n 7e 79 es et et 83.4 es es 1 es I
1 Figure 5 q
l Samples Irradiated versus Year 22
1988 F.
Fadiation Exposures A summary of radiation exposures during this reporting period to facility personnel, students, and visitors is shown in Table 8.
The average exposure per individual and the greatest exposure per individual for each group is summarized in Table 9.
No exposures in excess of the
~
limits of 10CFR20 occurred during this period.
G.
Area Radiation Surveys An annual summary of the normal radiation levels measured in the laboratory is shown in Table 10.
The results of routine surface and pool water contamination surveys are summarized in Table 11.
Environmental surveys performed outside the laboratory are summarized in Table 12.
11 Radioactive Effluents 1.
Gaseous Wastes Gaseous discharge during the reporting period is limited to leakage of Ar41 from the reactor laboratory. The total estimated amount of radioactivity released was calculated based on experimental data.
A summary of the calculated radioactive gaseous discharges during the reporting period is presented in Table 13.
An estimate of the release volume is calculated from the product of I
the monthly number of full power hours operated during the period end the effective air leakage rate. Although air leakage from the laboratory is restricted, an effective air change rate of two per 3
j hour (.36 m /sec) is assumed. The total activity released is I
calculated as the product of the volume released and the equilgbriumcogeentrationofAr41inthelaboratory,measuredat 4x10 pCi/cm.
I The release point concentration is determined as the product of the equilibrium Ar41 concentration in the Igboratory, the effective air leakage rate, release point (0.14 sec/m ), and the actual full power hours operated divided by the total number of hours in the reporting period. The percent of the maximum permissible 1
concentration (MPC) is_ghe releage point concentration divided by j
the MPC for Ar41 (4x10 pCi/cm ) in unrestricted areas.
2.
Liquid Waste No liquid radioactive waste was discharged during the reporting j
period. Efforts are made to avoid liquid waste disposal by l
i appropriate evaporation or absorption techniques for small volumes l
and purification by resin treatment for large volumes.
)
l 3.
Solid Waste The activity and amounts of solid waste discharged during the reporting period are summarized in Table 14.
All solid waste i
23
m 1988
. materia!s were packaged and shipped, along with radioactive vaste generated in other departments, by the Safety Office. Waste shipments are performed by Texas Nuclear, Austin, Texas.
O l
l l
l O
e 1
l 1
l l
24
- - v 1988-Tab]c 8 Summary of Personnel Radiation Exposures Range of Exposure in REM Number of Individuals Staff Students
. Visitors No measurable exposure 6
17 782 Measurable exposure less than 0.1 3
0 37-l 0.1 - 0.25 0
0 0
0.25 - 0.5 0
0-0 0.5 - 0.75 0
0 0
0.75 - 1.0 0
0-0 l
l l
Table 9 Radiation Exposure Groups Exposure per Individual in mrem Group Average
. Greatest Staff 8
50>
Students 10 10 Visitors
< 10 10 25
t 1988 1'
Table 10 l
Laboratory Radiation Levels L'
Location.
Average (mR/hr)
Maximqm (mR/hr)'
-3
-2, Control Console Area 5x10 1x10 10 ft. from core axis 6 ft. above pool
~I
~
Water System Area 2x10 4x10 12 ft. from core axis 4 ft.-above pool Above Core 1x10 "I'4x10-~I 0 ft. from core axis
.16 ft.'above pool Table 11 l
Laboratory Contamination Levels I
i l
Location Average Maximum-Floors 17 dpm 50 dpm Surfaces 18 dpm 54 dpm' l
1 I
Pool Water 112 pCi/1 338 pCi/1 1
i
)
J 26
v 1988 Table 12 Environmental Surveys Location Average Maximum 1
.01 mR/hr
.01 mR/hr 2
.01 mR/hr
.01 mR/hr 3
.02 mR/hr
.04 mR/hr 4
.01 mR/hr
.01 mR/hr 5
.01 mR/hr
.01 mR/hr 6
.01 mR/hr.01'mR/hr 7
6 pCi/1 27 pCi/1 o
27
1988 Table 12 Environmental Surveys s
Location Average Maximum 1
.01 mR/hr
.01 mR/hr
_3L 2
.01 mR/hr
.01 mR/hr 3
.02 mR/hr
.04 mR/hr 4
.01 mR/hr
.01 mR/hr 5
.01 mR/hr
.01 mR/hr 6
.01 mR/hr
.01 mR/hr 7
6 pCi/1 27 pC1/1
)
e 27
- rc:
1 1988 Table 14 i
Monthly Liquid Waste Discharge Month Isotope Total Point of Release Percent of
( Ci)
(m 3)
Concentration Maximum Release (pCi/m )
(%) -
Jan.
Feb Mar l
Apr May 1
-Jun 1
Jul Aug Sep Oct Nov Dec i
Table 15 i
Monthly Solid Waste Disposal ~
]
Month Isotope Total Form Remarks i
Release Chemical / Physical (pC1)
(ft )
Jan Feb Mar Apr May Jun Jul Aug
.Sep Oct
_Nov Dec 29
1988 V.-
Laboratory Inspections A.
NRC Inspections Several license inspections for the R-92.11 cense and activities of
~
the CPPR-123 construction permit took place during the 1988 calender year. Inspection dates were February 9-10, March 9-11, July 22nd and September 22-23. Activities of the construction permit were subject to inspection on each of these dates. Inspections of R-92 activities occurred only on the first 2 dates. Two violations of severity level IV were identified during the first R-92 inspection. A report was' filed in response to the violations and changes made to correct the deficiencies.
No NRC inspections took place during the calender. year for the SNM-180 special nuclear material 116,... a.
B.-
TDH Inspection November 23-24, 1988 The Texas Department of Health Bureau of Radiation Control inspection consisted of a review of activities and radioactive materials used at The University of Texas at Austin'as' authorized by TDH License.
30
=
1988 VI.
Public Service Activities A.
Summer High School Science Teacher Symposium The NETL staf f 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 1988 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," and " Energy and the Environment."
C.
Reactor Facility Tours During 1988, 815 persons visited the laboratory. The largest group visiting the laboratory were persons attending the Texas Energy Science Symposium. Numerous high school students also toured the facility during an event called The World of Engineering, designed to recruit students into the field of Engineering.
Special activities have also been provided in the efforts to recruit minority students into the engineering fields. Students from several local high schools and students from several non engineering related college courses visited the facility. Numerous college engineering related classes asi several student engineering organizations also toured the facility.
Safety personnel such as Austin Fire Department, UT Police Department, UT Safety Office and the Texas Department of Health also visited the facility to remain familiar with the laboratory and emergency response procedures unique to the facility.
D.
Fuel Transfer Cask Loan A three element transfer cask was obtained as part of the fuel element acquisition from the Northrup Corporation. The donated cask is designed for standard elements of TRIGA fuel and is to be available for loan to other university reactor programs. A container to ship the empty cask is also available. Charges for the cask use will apply only to shipment costs.
31 I
m 1988 1
VII. Research Activities j
i l
The staff and users of the Nuclear Engineering Teaching Laboratory j
perform research, as both sponsored and non sponsored projects, in
]
several different areas. Equipment and personnel are provided by the
]
laboratory to supplement the research efforts of facility users, that include students, faculty and others. The following section lists j
research projects active during the calendar year. Major research
]
funding or grants are presented in Table 16 for users of the facility.
i I
A.
Fuel Assistance Sponsor:
U.S. Department of Energy Personnel:
Dale Klein, NETL Thomas L. Bauer, NETL j
==
Description:==
The U.S. Department of Energy has provided research support by providing reactor fuel cycle assistance for the currently operating reactor core at The University of Texas at Austin TRIGA reactor.
B.
Summer Science Teachers Symposium Sponsor: Electric Utility Companies of Texas Personnel:
Dale Klein, NETL Steve Nichols, ME Dept.
The Electric Utility Companies of Texas have sponsored Summer High School Science Teachers Symposium, a program designed to familiarize these teachers with the theory and technology of energy sources.
C.
Texas Energy Science Symposium Sponsor: Texas Atomic Energy Research Foundation Personnel:
Dale Klein, NETL Orlan Ihms, Texas Utilities Electric Company The Texas Atomic Energy Foundation has sponsored a symposium for outstanding high school science students for over 25 years. The program is intended to encourage students to pursue careers in the sciences or engineering. Yearly attendance for the 4 day symposium consists of about 250 students and 150 high school science teachers.
32
1988 Table 16 Research Funding Department of Energy Fuel Assistance Program New Nuclear Engineering Teaching Laboratory (includes D&D for existing facility) 5,860,700 Electric Power and the Environment 21,000 6/88 - 8/88 I
Texas Energy Science Symposium 6/88-8/88 23,000 Sandia National Laboratories 90,000 2/82 - 9/88 Sandia National Laboratories 131,000 4/87 - 1/90 Texas Parks and Wildlife Departmeuc 20,000 8/31/89 Texas Advanced Technology Program 344,110 6/88 - 5/1990 Texas Low-Level Radioactive Waste Disposal Authority 6/1/88 - 8/31/89 194,035 Subtotal 823,145 6,683,845 TOTAL 4
33
1988 Heat Transfer and Friction Factor Analysis for Artificially 1
Roughened Surfaces j
l Sponsor: Center for Energy Studies National Science Foundation
]
1 University Research Institute
\\
Personnel:
Dale Klein,'NETL I
J. Parker Lamb, Moch. Eng.
Mike Krause, NETL i
Michael Michael, Mech. Eng.
David Glebe, Mech. Eng.
1
==
Description:==
1 The proposed research is to determine the heat transfer and friction characteristics for surfaces with discrete roughness geometry. Two major aspects are to be examined in that this is both an experimental and an analytical investigation. Values of R(h+) and G(h+) in the 1
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 s
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. This research has fundamental application for heat transfer augmentation.
Pressure Drop and Heat Transfer Measurements of Liquid Metal
)
Flowing in a Packed Bed Under the Influence of a Magnetic Field Sponsor: Center for Fusion Engineering Texas Atomic Energy Research Foundation Personnel:
Dale Klein, NETL Mike Crawford, Mech. Eng.
Jon McWhirter George Avlonitis, Mech. Eng.
N 34
1988
==
Description:==
The flow of electrically conducting fluids through porous media in the presence of a magnetic field has recently begun to generate significant interest due to potential, applications for fusion reactors. This study is designed to examine the pressure drop and heat transfer from a liquid
~
metal (NaK) flowing throug,h a packed bed of stainless steel spheres under the influence of a transverse magnetic field, Results of this investigation should have direct applications on the design of fusion breeder blankets using liquid metal flowing around spheres of fertile material.
Thermal Analysis of Nuclear Shipping Containers Sponsor: Sandia National Laboratories Personnel:
Randy Manteufel Dale E. Klein
==
Description:==
The thermal analysis of shipping containers to be used in the transport of spent nuclear fuel is an important safety issue. Sandia 1lllll National Laboratories has been involved in safety issues for the
]
transport of nuclear material for many years. The University of Texas at Austin (NETL) has been involved in the specific issues of thermal analysis of these containers for several years. The current project is intended to benchmark a thermal analysis computer code (Q/TRAN) and pre and post processing software PATRAN-G using four standard model problema. Comparisons were made with other applicable codes currently available at UT (including HEATING 5).
Sensitivity studies will be performed to further evaluate Q/TRAN's suitability for thermal analysis.
Enhancements, if any, that will increase the current capabilities of the software will be suggested and developed if feasible.
Application of COBRA for shipping Cask Analysis Sponsor:
Sandia National Laboratories Personnel:
Randy Manteufel, Mechanical Engineering Dale Klein, NETL Shawn Burns, NETL e
3.-
1988 l
l
==
Description:==
A thermal hydraulic computer code, COBRA, has been applied for both steady state and transient analysis. Previous research at The University of Texas at Austin involved the modification of the COBRA code and created a new version COBRA *GCFR 4P/UT. The current rescarch is directed towards modifying COBRA *GCFR 4P/UT so that ir may be applied to transient conditions for shipping cask analysis. One speciific modification will be to develop a more sophisticated model for analyzing radiation heat transport. Results using this code will be compared with the results from Q-TRAN and HEATING-6 where possible.
In addition, l
recommendations will be made regarding the development of a new code for
{
thermal analysis.
)
l Neutron Transport Studies: Neutron Multiplication by
)
I Beryllium I
Sponsor: National Science Foundation Personnel:
Nolan E. Hertel, Center for Fusion Engineering
==
Description:==
l The use of beryllium as a neutron multiplier is central to the j
current fusion breeder design. Recent measurements of beryllium neutron l
multiplication and reevaluations of beryllium nuclear data indicate that the multiplying performance of beryllium previcusly has been overestimated, possibly by as much as 25%.
If beryllium's performance as a neutron multiplier has indeed been overestimated even by as much as 10%, the direction of the fusion breeder program in the United States l
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.
l The beryllium experiment has been designed to measure multiplication resulting from DT, DD, PuBe, and 252Cf neutron sources I
being placed in a spherical shell. By doing so the sensitivity of the l
multiplication to spectral shape can be observed.
In addition, the use i
l of these four sources helps to simulate the effect of neutron source j
degradation in a fusion reactor. The neutron multiplication will be i
obtained directly from summing weigbted Bonner ball measurements of the i
neutron leakage. The neutron multiplication obtained in this manner l
will provide a number which tests the capability of the current l
beryllium nuclear data to calculate total neutron multiplication, i
l 1
i 1
I l
i 36 i
1988; 1
Measurement of Nutrional and Other Elements in Bread Sponsor: Nuclear Engineering Teaching Laboratory Food Research center, University of Idaho
-)
Personnel:
F.Y. Iskander K.R. Davis j
I
==
Description:==
Egyptian bread samples were collected from several locations across the country. Cereal and other components'used for bread making depend on location (city, village or nomad). The objective of the study is.co j
determine the concentration of nutritional elements in the different bread samples and to study a possible correlation between the iron content of bread and cases of iron-deficient anemia.
y Comparison Between Imported and Locally Manufactured Baby Food in Nigeria Sponsor: Nuclear Engineering Teaching Laboratory Dept. of Chemistry, University of IFE, Nigeria Personnel:
F.Y. Iskander l
0.I. Asubiojo I
1 1
==
Description:==
1 l
)
The concentration of nutritional, probably nutritional and. toxic trace elements in baby food locally produced in Nigeria were' compared to imported brands. Based on the total element content no significant d
difference was observed between local and imported baby foods. However, mineral bio-availability from the different brands may vary.
New Method for the Determination of Iodine Value by, Instrumental Neutron Activation Analysis Sponsor: Nuclear Engineering Teaching Laboratory Personnel:
F.Y. Iskander I
l 37 m
1988
==
Description:==
1 Measuring the degree of unsaturation for. oils and fats, as expressed by f
iodine value (I.V.), is an important step in the production of shortenings and margarine fats. Measuring I.V. is also of great importance to detect adulteration of vegetable oils with highly
)
saturated animal fats and mineral oils.
Early methods for the i
determination of 1.V. depend on mixing a halogenating agent with the oil sample for a certain period of time, then titrating the residual unreacted halogenating agent. Most of these methods require preparation of special reagents, large sample size, and handling of corrosive or toxic chemicals.
In addition, a long time (up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />) is required to prepare fresh reagents before starting the analysis.
A new microanalytical method has developed to measure the I.V. of oils and fats. Bromine vapor was used to saturate the ethylenic double bond in the oil samples. The quantity of Br reacted was determined by instrumental neutron activation analysis (INAA).. The analysis of 50 samples was completed in 75-100 minutes (compared to several days by other methods).
Determination of Selenium. A quality assurance project to evaluate the minimum detection limit.
Sponsor: Department of Parks and Wildlife, State of Texas Personnel:
T. L. Bauer F.Y. Iskander
==
Description:==
]
1he Department of Parks and Wildlife for the State of Texas is interested in determining the concentration of selenium, in fish, in several lakes across the state. To evaluate the quality of analysis, the department requested the participant laboratory to analyze a number of biological material for selenium content. No significant variation was observed between the results reported from NETL and the certified values (except for one sample). Results of the analysis were intended to provide quality assurance information to the department on the measurement methods performed by several laboratories.
a 38
1988
-Selenium and Other Metals in Fish Tissues Sponsor: Department of Parks and Wildlife, State of Texas Personnel:
T.L. Bauer F.Y. Iskander
==
Description:==
Tissue from muscle and liver of fish asmples from several Texas lakes are analyzed for several elements known to be toxic. Elements of interest are selenium, arsenic, mercury and zinc. This measurement is part of an environmental program for the State to examine the conditions of waters subject to certain types of power plant or industrial effluent releases.
l W
l e
39 I
VIII.
Publications From the Nuclear Engineering Teaching Laboratory Ph.D. Dissertations 1.
R.D. O' Dell, "The Angular Thermal Neutron Spectrum in the Vicinity of the Interface Between Two Media", Ph.D.
Dissertation, The University of Texas at Austin, 186 pp.,
January 1965.
2.
B.E. Thompson, Sr., " Cryogenic Neutron Spectra Measurements Across a Discontinuity in Temperature and Properties", Ph.D.
Dissertation, The University of Texas at Austin, 149 pp.,
January 1965.
3.
M.G. Stevenson, " Investigations on the Macroscopic Nodal Approach to Space-dependent Nuclear Reactor Kinetics", Ph.D.
Dissertation, The University of Texas at Austin, 203 pp.,
August 1968.
4.
P.J. Rodriguez, " Time and Energy Dependent Neutron Distribution in a Pulsed Multiplying Medium", Ph.D. Dissertation, The University of Texas at Austin, 205 pp., January 1969.
5.
F.A. Rodriguez-Gonzalez, " Application of Neutron Activation Analysis to the Study of Interstitial Solid Solution of Oxygen in Niobium and in Niobium-Titanium Alloys", Ph.D. Dissertation, The University of Texas at Austin, 131 pp., August 1970.
6.
G.D. Atkinson, Jr., " Nondestructive Uranium Assay by Delayed Gamma Ray Analysis Following Californium-252 Neutron Interrogation", Ph.D. Dissertation, The University of Texas at Austin, 183 pp., August 1971.
7.
G.D. Bouchey, "The Optimization of Nuclear Systems", Ph.D.
Dissertation, The University of Texas at Austin, 231 pp.,
. August 1971.
8.
J.B. Whitworth, "The Development and Application of a Systematic Approach to Elemental Analysis in Forensic Investigations", Ph.D. Dissertation, The University of Texas at Austin, 223 pp., December 1971.
9.
J. Freim, " Theoretical and Experimental Evaluation of Nuclear Data and Calculation Techniques for Fusion Reactor Blanket Design", Ph.D. Dissertation, The University of Texas at Austin, 210 pp., December 1972.
10.
D.C. Anderson, " Fission Product Mass-Yield Measurements from Intermediate Energy Neutron Fission of Plutonium-239 and Plutonium-241", Ph.D. Dissertation, The University of Texas at Austin, 125 pp., December 1972.
11.
J.R. Deen, " Measurement of Fission Product Yields from Thorium-232 in a Californium-252 Fission Neutron Spectrum",
39
Ph.D. Dissertation, The University of Texas at Austin, 141 pp.,
May 1973.
~
T.A. Parish, "Neutronic and Photonic Analyses of Simulated 12.
Fusion Reactor Blankets Containing Thorium and Natural Uranium", Ph.D. Dissertation, The University of Texas at Austin, 329 pp., January 1974.
13.
J.H. Vanston, Jr., "Use of the Partitive Analytical Forecasting (PAF) Technique for Analysis of the Effects of Various Funding and Administrative Strategies on Nuc1 car Fusion Power Plant Development",
Ph.D. Dissertation, The University of Texas at Austin, 459 pp., January 1974.
14.
E.M.B. Sorensen, " Thermal Effects on the Biological Magnification of Arsenic in Green Sunfish, Lepomis Cyanellus",
I Ph.D. Dissertation, The University of Texas at Austin, 233 pp.,
May 1974.
15.
S.P. Nichols, " Application of the Partitive Analytical Forecasting (PAF) Technique to the United States Controlled Thermonuclear Research Effort," Ph.D. Dissertation, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, December 1975.
16.
C.T. Rombough, "The Total Energy Investment in Nuclear Power Plants", Ph.D. Dissertation, The University of Texas at Austin, January 1975.
17.
J.L. MacDonald, " Investigation of Pattern Recognition Techniques for the Identification of Splitting Surfaces in Monte Carlo Particle Transport Calculations", Ph.D.
Dissertation, The University of Texas at Austin, August 1975, 18.
S.A. Hodge, " Determination of Friction Factors and Heat Transfer Coefficients for Flow Pzmt Artificially Roughened Surfaces", Ph.D. Dissertation, Me 'hanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, December 1979.
19.
Y. Yang, " Heat Transfer Through A Randomly Packed Bed of Spheres by the Monte Carlo Method" Ph.D. Dissertation, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, December 1981.
20.
M.M. Razzaque, " Finite Element Analysis of Combined Mode Heat Transfer, Including Radiation in Gray Participating Media",
Ph.D. Dissertaticin, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, May 1982.
21.
G.F. Polansky, "A Finite Element Analysis of Incompressible Laminar and Turbulent Flow with Heat Transfer past Irregular Surfaces", Ph.D. Dissertation, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, May 1983.
40
22.
T.L Sandern, "Magnetohydraulic Flow Through a Packed Bed of Electrically Conducting Spheres", Ph.D. Dissertation, Mechar.ical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, May 1985.
23.
R.D. Smith, " Routing and Scheduling of Radioactive Material Shipments", Ph.D. Dissertation, Mechanical Engineering Department, The University of Texas at Austin, August 1987.
Masters Thesis 1.
K.L. Gilbert, " Neutron Flux Mapping of a Suberitical Reactor Core with a Polyethylene Reflector", Masters Thesis, Physics (Nuclear Engineering) Department, The University of Texas at Austin, 61 pp., June 1961.
2.
T.T. Doss, " Neutron Density Distribution in an Unreflected Suberitical Reactor Core", Masters Thesis, Physics (Nuclear Engineering) Department, The University of Texas at Austin, 63 pp., June 1961.
3.
J.M. Norwood, "The Point Source Transport Solution for the Position and Velocity Dependent Neutron Distribution in a Spherical Body of Non-Multiplying Material", Masters Thesis, Physics (Nuclear Engineering) Department, The University of Texas at Austin, 75 pp. June 1962.
4.
R.W. Reed, "Effect of a Cadmium Control Rod on the Neutron Density in a Suberitical Reactor", Masters Thesis, Physics (Nuclear Engineering) Department, The University of Texas at Austin, 85 pp., August 1962.
5.
P. Berananda, " Neutron Flux Distribution of a Suberitical Reactor Core with a Graphite Reflector", Masters Thesis, Physics (Nuclear Engineering) Department, The University of Texas at Austin, 40 pp., January 1962.
6.
T.A. Fredericks, " Thermal Neutron Flux Distribution Due to a Plane Wave Source in an Unreflected Reactor Assembly", Masters Thesis, Physics (Nuclear Engineering) Department The University of Texas at Austin, 107 pp., August 1963.
7.
D.G. Martin, " Film Detector for a Neutron Spectrometer", Masters Thesis, Physics (Nuclear Engineering) Department, The University of Texas at Austin, June 1963.
8.
M.L. West II, " Flux Decay Rate in a Reflected Suberitical Reactor", Masters Thesis, Physics (Nuclear Engineering)
Department, The University of Texas at Austin, 55 pp., August 1963.
l l
9.
R.S. Kolflat, "An Experimental Approach to the Study of Nucleonic Fundamentals", Masters Thesis, Mechanical Engineering (Nuclear 41
Engineering) Department, The University lof Texas at Austin, 190-pp.
May 1965.
10.-
J.B. Whitworth, "A' Cryogenic Irradiation Device for the TRIGA Mark I Nuclear Reactor", Masters Thesis, Mechanical' Engineering.
(Nuclear Engineering) Department,'The University of Texas at Austin, 52 pp., January 1967.
11.
D.A. Pullen, "A Rod Oscillator Design and Z'ero Power Transfer Function Measurement for a TRIGA Mark I Reactor," Masters Thesis, Mechanical Engineering (Nuclear. Engineering) Department,1The University of Texas at Austin, January 1967.
12.
G.F. Malan,'" Transfer Function Analysis of Temperature and Xenon Feedback in Coupled-Core Nuclear Reactor Systems", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University.of Texas at Austin, 69 pp., August 1967.
13.
F.H. Antunez-Castillo, " Gamma Radiation Dosimetry. Techniques-and Application to Mapping of The University of Texas Cobalt-60 Irradiation Facility", Masters Thesis, Physics (Nuclear Engineering) Department, The University of Texas at Austin, 60 pp., September 1968.
l 14.
R. Valiente, " Neutron Radiography with The University'of Texas TRIGA Nuclear Reactor", Masters Thesis, Physics (Nuclear Engineering) Department, The University of Texas at Austin, August 1968, 15.
J.A. Villalobos, "A Study of Gamma Radiation Dosimetry Techniques l.
and Application to Radiation Field Mapping", Masters Thesis, l
Physics (Nuclear Engineering) Department, The University of Texas at Austin, January 1969.
16.
M.A. Zuniga, " Delayed Neutron Counting Technique for Uranium Determination" Masters Thesis, Physics (Nuclear Engineering)
Department, The University of Texas ~at Austin, January 1969.
17.
G.D. Atkinson, Jr., " Investigation of the Dynamic B'ehavior of a Two-Region Suberitical Reactor", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, January 1969.
18.
M. Gallardo, " Trace Elements in Six Quartz Samples by Nondestructive Neutron Activation Analysis Technique", Masters.
Thesis, Physics (Nuclear Engineering) Department, The University of Texas at Austin, January 1969.
19.
F.G. Pasos, "Nondispersive X-Ray. Fluorescence Analysis using a Lithium Drifted Germanium Detector", Masters Thesis, Physics i
L (Nuclear Engineering) Department,' The University of Texas at Austin, 54 pp., January.1969.
42'
20.
D.G. Jopling, "The Politics of Nuclear Reactor Siting", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, December 1970.
21.
A.H. Urdaneta, "A Programmed Associative Analyzer", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, December 1960.
22.
K.R. Waid., " Solid State Radiation Detection Devices: Fabrication, Techniques and Application to Nuclear Engineering", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, January 1970.
23.
V.H. Chanto, " Neutron Activation Analysis of Chlorine and Bromine in Some Haliburton-Bancroft Rocks and Minerals", Masters Thesis, Physics (Nuclear Engineering) Department, The University of Texas at Austin, January 1970.
24.
R.J. Gramatges-Figueras, " Neutron Waves in Cylindrical Geometries for a Subcritical Reactor", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, 98 pp., May 1970.
25.
E. Gelkers, Jr., "A Learning Method for Identification of Nuclear Reactor Point Dynamics", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, 165 pp., August 1970.
26.
J.R. Deen, " Calculation of Resonance Integrals Using the Intermediate Resonance Approximation", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, 140 pp., January 1970.
27.
C.T. Rombough, " Application of Queueing Theory to closed-Loop Computer-Reactor Control Systems", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, 78 pp., December 1970.
28.
A.H.U. Bohorquez, "A Programmed Associative Analyzer", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, 98 pp., December 1970.
29.
J.J. Chromik, " Experimental Determination of the Neutron Flux in The University of Texas Californium-252 Irradiation Facility",
Masters Thesis, Mechanical Engineering (Nuclear Engineering)
Department, The University of Texas at Austin, 85 pp., December 1971.
30.
M.B. Owen, " Fuel Management Using Dynamic Programming", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department.
The University of Texas at Austin, 59 pp., May 1972.
31.
C.E. Brauer, " Thermal Neutron Radiography with a Lithium-Lead Collimator-Filter", Masters Thesis, Mechanical Engineering 43
v 4
(Nuclear Engineering) Department, The University of Texas at Austin, 64 pp., May 1972.
32.
J.L. MacDonald, " Heuristic Learning Control for Nuclear Reactors", Masters Thesis, Hechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, 131 J
pp., August 1972.
)
l 33.
S.G. Barbee, "Neutronic Calculations in a Simulated Fusion i
Reactor Blanket", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, 259 pp., November 1972.
34.
D.M. Williams, " Identification of Thermal Feedback Parameters for a TRIGA Mark I Reactor", Masters Thesis, Electric Engineering Department, The University of Texas at Austin, 53 pp., December 1972.
35.
L.D. Hansborough, "Overall Tritium Considerations for Controlled Thermonuclear Reactors", Masters Thesis, The University of Texas at Austin, 154 pp., May 1973.
36.
M.E. Senglaub, " Cross Section Studies Based on the Statistical Model", Masters Thesis, The University of Texas at Austin, 109 pp., August 1973.
37.
S.P. Nichols, " Experimental Determination of Neutron Fermi Age from Californium-252 Fission Spectrum to Cadmium Covered Indium Resonance in a Graphite Medium", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, 101 pp., January 1974.
38.
Thomas L. Bauer, " Discrimination of Uranium-235 and Plutonium-239 by Cyclic Activation and Delayed Gamma Ray Analysis Using Californium-252 as a Neutron Interrogation Source", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, 178 pp., August 1974.
39.
Olan D. Thompson, " Optimization of Shipping Containers for Radioisotopic Neutron Sources", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, 30 pp., (August 1974).
40.
J.W. Davidson, "A Cost-Benefit Analysis for Partitioning Strategies Involved in High-Level Nuclear Waste Management",
Masters Thesis, Mechanical Engineering (Nuclear Engineering)
Department, The University of Texas at Austin, May 1975.
41.
J.P. Percy, " Experimental Determination of Local Convective Heat Transfer Coefficients Over a Ribbed Surface", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, May 1979.
44
s i
42.
G.A. Taylor, "The Analysis of the Grid Spacer Pressure and Temperature Effects in SAGAP0", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, August 1979.
43.
D.D. Usu, " Determination of the Relative Toxicities of the Fission Products Produced in the Transmutation of Actinide Wastes", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, December 1979.
44.
M.A. Ross, " Electrical Power Generation and Process Heat Application for Coal Gasification and Liquefaction Using a Very-High Temperature and Gas-Cooled Reactor", Masters Thesis, Mechanical Engineering'(Nuclear Engineering) Department, The University of Texas at Austin, May 1980.
45.
T.L. Sanders, "An Alternative Numerical Method for the. Steady State and Transient Thermal-Hydraulic Analysis of Gas-Cooled Fast Breeder Reactor Arrays", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, May 1981.
l 1
46.
J.E. Hamann, " Thermal Analysis of a Spent Fuel Railcar Shipping Cask in an Engulfing Fire", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, May 1983.
47.
M. Ally, " Reconcentration Method for the Determination of Uranium, Thorium and Transition Elements Using X-Ray Fluorescence and Activation Analysis", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, May 1983.
48.
A. Patterson-Hine, " Character 1zation of the Effects of Continuous Salt Processing on the Performance of Mo].en Salt Fusion Breeder Blankets", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, May 1984.
49.
E. Ibrahim, " Determining the Minimum Plasma Minor Radius for a I
Power Balanced Reversed Field Pinched Device at Ignition",
Masters Thesis, Mechanical Engineering (Nuclear Engineering)
Department, The University of Texas at Austin, December 1984.
50.
M.G. Krause, " Design and Fabrication of a Texas Assembly for the Evaluation of Heat Transfer in Flow Past Discrete Roughness l
Elements", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, December 1984.
i 51.
R.D. Savage, " Error Analysis for a Hydrogen Filled Benjamin Counter", Masters Thesis, Mechanical Engineering Department. The University of Texas at Austin, December 1984.
45 l
j l
{
i i
52.
A. Sharif-Homayoun, " Comparison of Parametric Empirical Bayes with Maximum Likelihood Estimators When Applied to Nuclear Reliability Data -- A Simulation Study", Masters Thesis, Mechanical Engineering Department, The University of Texas at 1
Austin, December 1983.
53.
R.M. Laucius, " Calculation of the Differential Efficiencies of Organic Scintillator to Neutrons", Masters Thesis, Mechanical Engineering Department, The University of Texas at Austin, May 1983.
l l
54.
R.D. Manteufel, "Analagous Finite Element /Einite Difference
{
Method for the Heat Diffusion Problem", Masters Thesis, l
Mechanical Engineering Department, The University of Texas at i
Austin, December 1987.
Reports and Papers l
1.
D.C. Anderson, "A Technique for Recoil Fission Frag ment Range Measurements", Health Physics, 12:4, 558 (April 1966).
2.
P.J. Rodriguez and D.H. Nguyen, " Time Decay Constants in Pulsed j
Multiplying Media", Trans. Amer. Nucl. Soc. 11:1, 289 (June 1968).
l i
P.J. Rodriguez and D.H. Nguyen, "The Maximum Eigen-value in the 3.
Pulsed-Neutron Initial-Value Problem", Trans. Amer. Nucl. Soc.
11:2, 578 (November 1968).
4.
P.J. Rodriguez and D.H. Nguyen, " Contribution of the Continuum to the Neutron Transient Behavior in a Pulsed Multiplying Cylinder",
Trans. Amer. Nucl. Soc. 11:2, 582 (November 1968).
5.
G.D. Bouchey and S.J. Gage, " Neutron Radiography with a Small Suberitical Reactor", Trans. Amer. Nucl. Soc. 12, 462 (1969).
t 6.
G.D. Atkinson, Jr., W. Coltharp, R. Cramatges, E. Oelkers, D.A.
l Roberts, K.R. Waid, S.H. Gage, and B.V. Koen, " Project Atlantis:
j A Design of the Nuclear Power Supply for an Undersea City", Proc.
of the Offshore Technology Conference, Dallas, Texas, 1969.
i 7.
V. Chanto, S.J. Gage, and D.F. Barker, " Chlorine and Bromine Concentrations in Some Haliburton-Bancroft Rocks and Minerals by Neutron Activation Analysis", 1969.
j i
8.
M. Gallardo, S.J. Gage, and D.F. Barker, " Trace Elements in l
Quartz by Nondestructive Neutron Activation Analysis", 1969.
l 9.
F.A. Rodriguez, S.J. Gage, and K.M. Ralls, " Nondestructive
)
Neutron Activation Analysis for Trace impurities in Niobium",
presented at the Seventh Symposium on Nondestructive Evaluation l
of Components and Materials in Aerospace, Weapon Systems, and 3
Nuc1 car Applications, San Antonio, Texas, 1969.
l 1
I 46
y 10.
S.J. Gage and M. Zuniga, " Uranium Trace Analysis by Pulsed Reactor Irradiation", Radiation and Isotope Technology in Latin American Development, American Nuclear Society Topical Meeting, San Juan, Puerto Rico, May 1969.
11.
R.H. Richardson, " Migration and Enzyme Polymorphism in Natural Populations of Drosophila", Jap. J. Gen., 1969.
l 12.
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 i
Ed., The University of Texas Press, Austin, Texas, 1969.
13.
G.D. Bouchey and S.J. Gage, " Development and Potential Utilization of a Neutron Radiography Facility at The University j
of Texas Nuclear Reactor Laboratory", presented at the Seventh Symposium on Nondestructive Evaluation of Components and Materials in Aerospace, Weapons Systems and Nuclear Applications, San Antonio, Texas, 1969.
14.
G.D. Bouchey and S.J. Gage, " Utilization of The University of Texas TRIGA Reactor for Neutron Activation Analysis Service;',
)
ANS/CNA Transactions 1, 287 (1968).
15.
G.D. Bouchey and G. Gjerstad, " Chemical Studies of Aloe Vera l
Juice -- II. Inorganic Ingredients", Quarterly Journal of Crude I
Drug Research, 9:4, (1969).
16.
S.J. Gage, R.H. Richardson, and G.D. Bouchey, " Neutron Activation Techniques for Labeling of Insects with Stable Elements", Trans.
Amer. Nucl. Soc., 12, 495 (1969).
l 17.
G.D. Bouchey, B.V. Koen, and C.S. fuightler, "The Optimal Allocation of Energy in Industria ind Agro-Industrial Complexes Using Dynamic Programming", Nucl.
ci. and Engr., 4_1, 70 (1970).
18.
G.F. Malan and B.V. Koen, "A Nonlinear Programming Approach to Optimal Control of Nuclear Reactors", Trans. Amer. Nucl. Soc.,
l (1970).
1 19.
M.G. Stevenson and S.J. Gage, " Application of a Coupled Fission Mode Approach to Modular Reactor Kinetics", Journal of Nucl.
2_4, 1 (1970).
4
- Energy, 20.
G.D. Bouchey and S.J. Gage, " Neutron Radiography at The University of Texas Nuclear Reactor Laboratory", Isotopes and Radiation Technology, 1, 294 (1970).
l 21.
G.D. Bouchey and S.J. Gage, " Detection and Location of Leaking TRIGA Reactor Fuel Elements", GA Publication T-117, Papers and Abstracts, TRIGA Reactors Owners' Seminar, Denver, Colorado, February 1970.
47
v 22.
G.D. Bouchey and S.J. Gage, " Neutron Radiography with a Small Suberitical Assembly", International Journal of Nondestructive Testing, 1970.
23.
G.D. Atkinson, Jr., J.B. Whitworth, and S.J. Gage, "NAACOL -- A Spectrum Analysis Routine for the Small Laboratory", presented at the 21st Mid-America Symposium on Spectroscopy, Chicago, Illinois, 1970.
24 S.J. Gage, G.D. Atkinson, Jr., J.B. Whitworth, and A.H.
Pradzynski, " Computer-Aided Multielement Gamma Ray Analysis with a Compton Suppressed Ge(Li) Radiation Source", presented at the Ninth National Society of Applied Spectroscopy, New Orleans, Louisiana, October 1970.
25.
J.J. Chromik and E.L. Draper, Jr., " Energy Integral Tests of I
Differential Fission C?,ss Section Data", Trans. Amer. Nucl.
Soc., 13:2, 755 (1970).
i 26.
S.J. Gage and D.G. Jopling, The Nuplex Concept: Potential for the SINB Region, Southern Interstate Nuclear Board, 250 pp., March 22, 1971.
27.
G.F. M9lan and B.V. Koen, " Application of Nonlinear Programming to the Optimal Control of a Point Model Nuclear Reactor", Nucl.
Sci. and Engr., (1971).
28.
G.D. Bouchey, B.V. Koen, and C.S. Beightler, " Optimization of Fbterial Safeguards Sampling System", Trans. Amer. Nucl. Soc.,
Winter Meeting, 1971.
29.
A.H. Pradzynski and S.J. Gage, " Nondestructive Identification of Material by Nondispersive X-Ray Fluorescence Spectrosocpy Using Si(Li) Detectors and Radio-isotopic Sources", Proc. Eighch Symposium on Nondestructive Evaluation in Aerospace, Weapons Systems, and Nuclear Applications, San Antonio, Texas, 1971.
I 30.
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, Palm Springs, Florida, July 1971.
31.
S.J. Gage E. Linn Draper, Jr., G.D. Bouchey, and R.R. Day,
" Design and Construction of a Versatile Cf-252 Source Shield and Experimental Facility", Neutron Sources and Applications, CONF-710402, 2, Proc. of ANS Topical Meeting, Augusta, Georgia, April 1971.
(
32.
D.G. Jopling and S.J. Gage, "Public Resistance to Nuclear Reactor Siting" Nuclear News, 14:3, 32 (March 1971).
j 33.
J.B. Whitworth, G.D. Atkinson, and S.J. Gage, "Some Recent i
Applications of Nuclear Analysis Techniques to Typical Forensic
^
l 1
48
v
)
Evidence" presented at the 23rd Annual Program American Academy for Forensic Sciences, Phoenix, Arizona, February 1971.
34.
G.D. Bouchey, E. Linn Draper, Jr._B.V. Koen, and C.S.
Beightler, " Multiple Foil Activation Spectrum Determination Using a Numerical Direct Search Technique", Trans. Amer. Nucl.
~ '
Soc., 14:2, 667 (October 1971).
35.
G.D. Bouchey, B.V. Koen, and C.S. Beightler, "The Optimization of Nuclear Systems by Geometric Programming, Nucl. Sci. and Engr.,
44, 267 (1971).
q 36.
G.D. Bouchey, B.V. Koen, and C.S. Beightler, " Optimization of
/
Nuclear Materials Safeguards Sampling by Dynamic Programming",
Nuclear Technology, 12, 18 (1971).
37.
S.J. Gage, G.D. Atkinson, Jr., and G.D. Bouchey, " Cyclic Neutron Activation Analysis with a Cf-252 Neutron Source", Trans. Amer.
Nucl. Soc., (October 1971).
38.
E. Linn Draper, Jr., " Integral Reaction Rate Determination Part I: Tailored Reactor Spectrum Preparation and Measurement", Nucl.
,64_6,, 22 (1971).
Sci. and Engr.,
39.
E. Linn Draper, Jr., " Integral Reaction Rate Determination Part II: Fission Rate Measurements", Nucl. Sci, and Engr., 46, 31 (1971).
40.
G.D. Bouchey and S.J. Gage, " Detection and Location of Leaking TRIGA Reactor Fuel Elements", Nuclear Technology, 10, 211 (1971).
41.
G.D. Bouchey and S.J. Cage, " Neutron Radiography with a Small Subcritical Reactor", Int. J. of Nondestructive Testing, 2, 335 (1971).
42.
G.D. Bouchey and S.J. Gage, "The Economics of Subcritical Radiography", Trans. Amer. Nucl. Soc., 14, 123 (1971).
43.
G.D. Bouchey, E. Linn Draper, Jr., and S.J. Gage, " Neutron l
Radiography with Cf-252: The Effect of Tailoring Neutron Energy Spectra on Photographic Images", Neutron Sources and Appifcations, CONF 210402, 3, Proc. ANS Topic Meeting, Augusta,
)
Georgia, April 1971.
44.
G.D. Atkinson, Jr., J.B. Whitworth, and S.J. Gage, I
" Computer-Assisted Analysis of Gamma-Ray Spectra", Computer f
Physics Communications, -2, 40 (1971).
)
i.
4 45.
S.J. Cage,'i. Linn Draper, Jr., and G.D. Bouchey, "Recent Developments in Radioisotopic Source Neutron Radiography", Proc.
j Eighth Symposium on Nondestructive Evaluation in Aerospace, l
Weapon Systemt, and Nuclear Applications San Antonio, Texas, 1971.
1 I
49 1
v i
l 46.
E. Linn Draper, Jr., Mary Elizabeth Foster, and G.D. Bouchey, "X-Ray Fluorescence 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, Houston, Texas, November 1971.
l
~
47.
E. Linn Draper, Jr. and G.D. Bouchey, " Utilization of a i
Portable Californium-252 Source for Neutron Activation Analysis and Neutron Radiography", presented at the Combined Meeting of the Texas Association for Radiation Research and South Central Photobiology Group, Houston, Texas, November 1971.
l 48.
E. Linn Draper, Jr. and J.J. Chromik, " Production and Measurement l
of a Reference Spectrum in a Versatile Experimental Facility",
i Trans. Amer. Nucl. Soc., 15:1, 157 (1972).
l l
49.
E. Linn Draper, Jr. and Andrzej J. Pradzynski, " Identification of Alloys by Energy Dispersive X-Ray Spectroscopy", presented at the Ninth Symposium on Nondestructive Evaluation, 1972.
l l
50.
G.D. Atkinson, Jr., E. Linn Draper, Jr., and G.D. Bouchey, i
"Suberitical TRIGA Reactivity Measurements Using the Source Jerk Technique", presented at the TRIGA Owners' Conference II, College Station, Texas, 1972.
51.
G.D. Atkinson, Jr. and E. Linn Draper, Jr., " Transient Rod Failure in a Pulsing TRIGA Mark 1 Reactor", presented at the TRIGA Owners' Conference II, College Station, Texas, 1972.
52.
G.D. Atkinson, Jr., "A Safeguards Minicourse", presented at the 18th Annual Meeting of the American Nuclear Society, Las Vegas, Nevada (1972).
53.
G.D. Atkinson, Jr., E. Linn Draper, Jr., G.D. Bouchey, and S.J.
Cage, " Radioisotopic Source Amplification Using a Heterogeneous Subcritical Assembly", Proc. 18th Annual Meeting of the American Nuclear Society, Las Vegas, Nevada (1972).
l 54.
E. Linn Draper, Jr. and G.D. Atkinson, Jr., " Transient Rod Failure in a Pulsing TRIGA Mark I Reactor", published in Proc. of 2nd TRIGA Owners' Conference, February 1972.
55.
E. Linn Draper, Jr., John W. Davidson, S.J. Gage, and G.D.
Bouchey. "A System for Reduction of 41A Release from a Research l
Reactor Facility", Trans. Amer. Nucl. Soc., 15:1, 4 (1972).
56.
E. Linn Draper, Jr., et al, Standard for the Development of Technicel Specifications for Research Reactors", Trans. Amer.
l Nucl. Soc., (1972).
1 57.
E. Linn Draper, Jr., G.D. Atkinson, Jr., and B.B. Tomlin, "A Radiography and Capture Gamma Ray Facility for Californium-252",
Proc. of the American Nuclear Society " Applications of Californium-252" National Topical Meeting, September 1972.
50
I i
1 58.
E. Linn Draper, Jr., G.D. Bouchey, G.D. Atkinson, Jr., and S.J.
Gage, "A Versatile Subcritical Assembly for Undergraduate Nuclear Engineering Instruction", Proc. of the American Nuclear Society
" Applications of Californium-252" National Topical Meeting, September 1972.
]
t 59.
E. Linn Draper, Jr. and S. J. Gage, "The FusionFission Breeder:
l Its Potential in a Fuel Starved Thermal Reactor Economy",
presented at the 93rd Annual Meeting of ASME, New York, 1972.
60.
E. Linn Draper, Jr., " Technological Innovation and Assessment: A Novel Course for Nuclear Engineering", presented at the Winter Meeting of the American Nuclear Society, November 1972.
61.
D.T. Hall, E. Linn Draper, Jr., and P.S. Schmidt, " Management of the Transition to Nuclear Power Generation", Technical Report ESL-3, Energy Svstems Laboratories, College of Engineering, The University of Texas at Austin, December 1972.
62.
P.S. Schmidt and G.G. Park, " Heat Dissipation in a Power Plant J
Cooling Bay", ASME, Paper No. 72-WA/HT-61, November 1972.
]
63.
P.S. Schmidt and G.P. D' Arch, " Entry Region Effects on Flow and Pressure Drop of Lithium in Fusion Re-actor Blankets", Proc. of the Texas Symposium of Technology of Controlled Thermonuclear Fusion Experiments and Engineering Aspects of Fusion Reactors.
)
I 64.
E. Linn Draper, Jr. and Charles Brauer, " Lithium-Lead Collimator Fabrication for Radioisotopic Source Neutron Radiography", Trans.
Amer. Nucl. Soc., 15:1, 142 (1972).
65.
E. Linn Draper, Jr. and James B. Fraim, " Theoretical and Experimental Evaluation of Nuclear Data and Calculation Techniques for Fusion Reactor Blanket Design", presented at the Texas Symposium on the Technology of Controlled Thermonuclear Fusion Experie nts and the Engineering Aspects of Fusion Reactors, Noverber 1972.
66.
E. Linn Draper, Jr., " Status of CTR Related Integral Experiments" presented at the Conference on Nuclear Data and Neutronics of CTR Blankets held in Seattle, Washington, September 1972.
67.
E. Linn Draper, Jr., " Fusion Reactor Engineering in the Nuclear Engineering Curriculum at The University of Texas at Austin",
Trans. Amer. Nucl. Soc., (1972).
68.
E. Linn Draper, Jr. and S.J. Gage, "The Fusion Fission Breeder:
i Its Potential in a Fuel Starved Thermal Reactor Economy",
presented at the Texas Symposium on the Technology of Controlled Thermonuclear Fusion Experiments and the Engineering Aspects of Fusion Fenetors, November 1972.
52
v 69.
James B. Freim and E. Linn Draper, Jr., " Experimental Determination of tl.e Fusion Spectrum in Graphite", Trans. Amer.
Nucl. Soc., (1972).
70.
G.D. Atkinson, Jr., S.J. Gage, and G.D. Bouchey, " Cyclic Activation with a Californium-252 Source", Nuclear Technology (1972).
71.
G.D. Atkinson, Jr., "What You Always Wanted to Know about Californium Source Facilities", Invited Paper, National Topical Meeting on the Applications of Californium-252, Austin, Texas (1972).
72.
T.L. Bauer and G.D. Atkincon, Jr., " Discrimination Between Plut:nium and Uranium by Gamma Ray Analysis Following Cf-252 Interrogation", presented at the National Topical Meeting on the Applications of Californium-252, Austin, Texas, 1972.
73.
E. Linn Draper, Jr., Editor, Proc. of Texas Symposium on the Technology of Controlled Thermo-nuclear Fusion Experiments and the Engineering Aspects of Fusion Reactors, published by USAEC.
74.
E. Linn Draper, Jr., Editor, Proc. of the Implications of Nuclear Power in Texas, published by the Texas Atomic Energy Research Foundation.
75.
E. Lian Draper, Jr., J.R. Deen, and J.J. Chromik, " Measurement of the Integral Fission Cross Section of Th-232 in a Cf-252 Fission Neutron Spectrum", Trans. Amer. Nucl. Soc., (1973).
76.
D.G. Anderson and E. Linn Draper, Jr., " Fission Product Mass-Yield Measurements from Intermediate Energy Neutron Fission i
of Plutonium-239 and Plutonium-241", Trans. Amer. Nucl. Soc.,
(1973).
17, E. Linn Draper, Jr. and James B. Freim, " Experimental Determination of the Fusion Spectrum in Graphite" Trans. Amer.
Nuct. Soc., 16, 9 (1973).
78.
E. Linn Draper, Jr., " Fusion Reactor Engineering in the Nuclear Engineering Curriculum at The University of Texas at Austin",
Trans. Amer. Nucl. Soc., 16, 16 (1973).
79.
E. Linn Draper, Jr., Theodore A. Parish, and Brian J. McArdle, "A Neutronic-Photonic Comparison of Vanadium and Niobium Containing Fusion Reactor Blankets", Trans. Amer. Nucl. Soc., (November 1973).
80.
John H. Vanston, Jr., "Use of Partitive Analytical forecasting (PAF) Techniques for Fusion Development Analysis", Trans. Amer.
Nucl. Soc., (November 1973).
81.
Theodore A Parish and E. Linn Draper, Jr., "Neutronic and Photonic Analyoes of Fusion Peactor Blankets Containing Thorium",
53
l l
presented at the Fifth Symposium on Engineering Problems of 1
Fusion Research, Princeton, New Jersey, November 1973.
82.
C.E. Locke and D.R. Paul, " Graft Copolymer Modification f Polyethylene-Polystyrene Blends. I. Graft Preparation and
--17, 2597 Characterization", Journal of Applied Polymer Science, (1973).
83.
C.E. Locke and D.R. Paul, " Graft Copolymer Modification of Polyethylene-Polystryene Blends. II. Properties of Modified Blends", Journal of Applied Polymer Science, 17, 2791 (1973).
84.
E. Linn Draper, Jr., M.J. Voltin, Jr., J.L. MacDonald, C.T.
Rombou3h, L.D. Hansborough, S.G. Barbee, and J.H. Vanston, Jr.,
"A University's Involvement in Municipal Decision-Making on Nuclear Power", Trans. Amer. Nucl. Soc., (1973).
85.
E. Linn Draper, Jr., J.L. MacDonald, and M.J. Voltin, Jr.,
" Nuclear vs. Coal: An Economic Comparison of Power Plant Economics in Texas", Trans. Amer. Nucl. Soc., (1973).
86.
R.E. Henry, " Forensic Applications of Neutron Activation Analysis", presented at the Combined Meeting of the Texas Association for Radiation Research and South Central Photobiology Group, San Marcos, Texas, November 1973.
87.
G.D. Atkinson, Jr., " Applications of Neutron Activation Analysis to the Life Sciences", presented at the Combined Meeting of the Texas Association for Radiation Research and South Central Photobiology Group, San Marcos, Texas, Ncvember 1973.
88.
E. Linn Draper, Jr. and J.R. Deen, " Measurement of Fission Product Yields from Thorium-232 in Californium-252 Fission Neutron Spectrum" Trans. Amer. Nucl. Soc., 17, 531 (1973).
89.
E. Linn Draper, Jr., M. Etzion, S.P. Nichols, and W.G. Davey,
" Neutron Fermi Age in Graphite from Fission and Fusion Sources to Indium Resonance", CONF 740402, USAEC, April 1974.
90.
E. Linn Draper, Jr. and T.A. Parish, "Neutronic and Photonic Analyses of Fusion Reactor Blankets Containing Natural Uranium",
CONF-740402, USAEC, April 1974.
91.
G.D. Atkinson, Jr., B.D. Adams, and S.J. Gage, "A Programmable and Automated System for Gamma and X-Ray Analysis", Proc. IEEE l
1973 Nuclear Science Symposium, San Francisco, California, 1973.
1 92.
G.D. Atkinson, Jr. and R.E. Henry, " Neutron Activation Analysis:
Environmental and Biolgical Applications", presented at the Sixth Annual Meeting of the Texas Association for Radiation Research, San Marcos, Texas, 1973.
93.
M. Etzion, R.G. Spangler, cnd E. Linn Draper, Jr., "Ma'.tiple Foil Activation Measurement of the Californium-252 Fission-Neutron Spectrum, Trans. Amer. Nucl. Soc., (October 1974).
54 m
v 94 A.H. Pradzynski, " Determination of Selenium in Water on the ppb icvel" presented at the Texas Association of Radiation Research, Dallas, Texas, November 1974.
95.
J.R. Deen and E. Linn Draper, Jr..." Measurement of the Fission Product Yields and the Energy Integral Fission Cross Section of Thorium-232 in a Californium 252 Fission-Neutron Spectrum",
I Nuclear Technology, 25, 416 (1975).
96.
E. Linn Draper, Jr., T.A. Parish, and M. Etzion, " Utilization of' a Small Accelerator for Pusion Reactor Blanket Design", Proc. of the Third Small Accelerator Conference, USAEC, CONF-741021, 1974.
l 97.
R.G. Spangler, E. Linn Draper, Jr., and T.A. Parish, "14'MeV Cross Section Measurements of Threshold Reactions for Seven Metals", Trans. Amer. Nucl. Soc., 22, 818 (November 1975).
98.
W.R. Smith, Jr. and E. Linn Draper, Jr., " Measured and Calculated l
Fast Neutron Spectra in a Craphite Medium", Trans. Amer. Nucl.
1 Soc., 22, 800 (November 1975).
99.
J.W. Davidson and E. Linn Draper, Jr., " Costs for Partitioning St ategies Involved in High-Level Nuclear Waste Management",
Trans. Amer. Nucl. Soc., 22, 348 (November 1975).
100.
M.J. Voltin, Jr. and E. Linn Draper, Jr., " Sensitivity of Total Fuel Cycle Cost to Variations in Enrichment Tails Assay l
Strategies", Trans. Amer. Nucl. Soc., 22, 322 (November 1975).
101.
T.A. Parish, J.W. Davidson, and E. Linn Draper, Jr.,
" Transmutation of Fission Products in Fusion Reactor Blankets",
Trans. Amer. Nucl. Soc., 22, (November 1975).
102.
T.A. Parish, J.W. Davidson, and E. Linn Draper, Jr., "The Effects of the D-T Fusion Neutron Energy Spectrum on High Energy Reaction Rates", submitted to the Sixth Symposium on Engineering Problems of Fusion Rescat ch, San Diego, California, November 1975.
103.
A.ll Pradzynski, R.E. Henry, and J.L.S. Stewart, " Determination of Selenium in Water on the ppb Level by Coprecipitation and Energy Dispersive X-Ray Spectrometry", Radiochem. Radioanal.
l Letters, 21:5, 277 (1975).
104 B.E. Bulla, E. Linn Draper, Jr., R.E. Henry, M.J. Voltin, Jr., et al, Texas Nuclear Power Policies: A Study of Alternatives, Volume II: _ Methodology. The University of Texas at Austin Center for Energy Studies, Policy Alternative Study No. 1 (1975).
1 l
105.
A.ll. Pradzynski, R.E. Henry, and J.L.S. Stewart " Determination of Transition Metals by radioisotope-Excited Energy Dispersive X-Ray Spectrometry", Trans. Amer. Nucl. Soc., 21:3, 34 (1975).
55
v 106.
A.H. Pradzynski, R.E. Henry, and J.L.S. Stewart, "Non-destructive Determination of Toxic Elements in Toys", Proc. of 10th Symposium on Nondestructive Elements, San Antonio, Texas, April 1975.
107.
R.E. llenry, " Determination of ppb Levels of Selected Elements in Natural Water Using Radioisotope-Excited Energy Dispersive X-Ray Fluorescence Analysis", presented at the Eighth Annual Meeting of the Texas Association for Radiation Research, Austin, Texas, October 1975.
103.
T.A. Parish, J.W. Davidson, and E. Linn Draper, Jr., "The Minimization of the Hazard Resulting from Transmutation of Fission Products", Transactions of the American Nuclear Society, 23, 59 (June 1976).
109.
T.A. Parish, " Fusion-Fission Hybrid Studies at The University of Texas", presented at the U.S.-U.S.S.R.
Symposium on Fusion-Fission Reactors, Lawrence Livermore Laboratories, July 1976.
110.
T.A. Parish, J.W. Davidson, and E. Linn Draper, Jr., "Neutronic Performance of Graphite Fusion Reactor Blankets Containing Sr90 and 1129", presented at the Second ANS Topical Meeting on the Technology of Controlled Thermonuclear Fusion, Richland, Washingtori, September 1976.
111.
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.
J 112.
A.H. Pradzynski and J.R. Rhodes, " Development of Synthetic Standard Samples for Trace Analysis of Air Particulate", ASTM Special Technical Publication, 598, 320 (1976).
113.
A.H. Pradznyski. R.E. Henry, and J.S. Stewart, " Determination of ppb Concentrations of Transition Metals by Radioisotope-Excited Energy-Dispersive X-Ray Spectrometry, Journal of Radioanalytical Chemistry, 32, 219 (1976).
114 A.H. Pradzynski, R.E. Henry, and E.L. Draper, Jr., " Determination of ppb Concentrations of Uranium, Thorium and Molybdenum in Water f
using APDC Reconcentration and Radioisotope Excited X-Ray Emission Spectrometry", Proceedings of ERDA Symposium on X-and Gamma-Ray Sources and Applications, Ann Arbor, Michigan, May 1976.
115.
A.H. Pradzynski, R.E. Henry, and E.L. Draper, Jr., " Determination of Trace Elements of Hydrogeochemical Prospecting by APDC-Coprecipitation and X-Ray Spectrometry", Invited Paper at The International Conference on World Nuclear Energy a Status Report. Transactions of Amer. Nuclear Society, 24, 119 (1976).
116.
R.R. Gay, G.F. Breckett, and R.T. Johnson, "Two-Phase Flow Measurement Techniques for Nuclear Safety Fasearch", Two-Phase Flow and Heat Transfer Symposium Workshop, Miami Beach, Florida, 1976.
56
l I
117.
C.W. Savery and R.R. Gay, "Effect of Entrained Droplet Phase Upon Predicted Compartmental Pressures in Nuclear Containments",
Two-Phase Flow and Heat Transfer Symposium-Workshop, Miami Beach, Florida, 1976.
118.
Rodney R. Gay, " Reactor Hydrodynamics During the Reflood Phase of Loss-of-Coolant Accident", Nuclear Technology, 36:2, 229 (December 1977).
119.
D.E. Klein, S.R. Bull, and J.B. Miles, " Flow Visualization Around GCFR Fuel Rod Roughness Elements", Trans. Amer. Nucl. Soc., 28, (June 1978).
3 120.
D.E. Klein, S.R. Bull, and J.B. Miles, " Pressure Drop for GCFR Fuel Rod Roughness Elements", Trans. Amer. Nucl. Soc., 30, (November 1978).
i 121.
E.M.B. Sorensen, R.E. Henry, and R. Ramirez-Mitchell, " Time Dependent Localization of Arsenic in Subcellular Hepatocyte Fractions", J. of Pathology and Toxicology, 2:4, 1161 (1979).
122.
E.M.B. Sorensen, R.E. Henry, and R. Ramirez-Mitchell, " Arsenic Accumulation, Tissue Distribution, Cytotoxity in Teleosts 1
Following Indirect ATseous Exposure", Bulletin of Environmental Contamination and Toxicology, 2_1, 162 (1979).
123.
J.W. Davidson and T.A. Parish, " Fission Product Toxicity Reduction via Transmutation Using D-T Fusion Neutrons", presented I
at the Eighth Symposium on Engineering Problems of Fusion Research, San Francisco, California, November 1979.
124.
J.W. Davidson and T.A. Parish, "An Evaluation of the Requirements and Performance of a Transmutation Waste Management System, Trans. Amer. Nucl. Soc., 33_, (November 1979).
125.
S.A. Hodge, J.P. Sanders, and D.E. Klein, " Determination of Friction Factors and Heat Transfer Coefficients for Flow Past Artificially Roughened Surfaces", Oak Ridge National Laboratory Report, ORNL-5599, November 1979.
!?6.
D.E. Klein, " Nuclear Problems and Prospects", National Energy Policy Issues, Council on Energy Resources, The University of Texas at Aut.-in, May 1979.
127.
D.E. Klein, H.H. Woodson, and J.W. Davidson, " Commercial Nuclec.r Power Generation", Council on Energy Resources, The University of Texas at Austin, June 1979.
128.
E.M.B. Sorensen, R.R. Mitchell, A. Pradzynski, T. Bauer, and L.
Graham, "Morphometric Analyses of Arsenic-Induced Histopathological Chenges in Parenchymal Hepatocytes", Tennessee Academy of Scier.ce Annual Meeting, Nashville, TN, November 16-17, 1979.
t 57
129.
A.H. Pradzynski, " Determination of V and Ba in Marine Sediments and Biota", Internal Report, Nuclear Engineering Teaching Laboratory, Mechanical Engineering (Nuclear Engineering)
Department, The University of Texas at Austin,1979.
130.
N.E. Hertel, B.W. Wehring, and J.J. Dorning, " Integral 7est of ENDF/B-IV High-Energy Neutron Cross'Section Data for Tungsten",
3_2, 632 (1979).
Trans. Amer. Nucl.. Soc.,
2 131.
R.H. Johnson, K.R. Koch, B.W. Wehring, and N.E. Hertel, "TDL Measurements in an Iron Sphere Containing a DT Source", Trans.
Amer. Nucl. Soc., 32, 632 (1979).
132.
B.W. Wehring, J.J. Dorning, N.E. Hertel, D.T. Ingersoll, and R.H.
Johnson, " Benchmark Shielding Problems Obtained from Integral Tests of Neutron Cross Sections", Trans. Amer. Nucl. Soc.,
- 3_3_,
3 666 (1979).
133.
N.E. Hertel, R.H. Johnson, J.J. Dorning, and B.W. Wehring, "Hearsurements and Analyses of Neutron Transport Through Iron",
Proc. Conf. Nuclear Cross Sections and Technology, Knoxville, TN, October 22-26, 1979, NBS Special Publication #594, pp. 568-571.
134.
N.E. Hertel and B.W. Wehring, " Absolute Monitoring of DD and DT Neutron Fluences Using the AssociatedParticle Technique", Nucl.
Instr. Meth., 172, 501 (1980).
135.
S.A. Hodge, J.P. Sanders, and D.E. Klein, " Slope and Intercept of the Dimensionless Velocity Profiles for Artificially Roughened Surfaces", Int. J. Heat Mass Transfer, y, 135 (February 1980).
136.
N.E. Hertel, J.B. Smathers, and R.G. Graves, " Gamma-Ray Spectra Measured in a Tissue-Equivalent Medium Irradiated with Neutron Radiotherapy Sources", Trans. Amer. Nucl. Soc., g, 457 (1980).
137.
N.E. Hertel, W.E. Murphie, and R.J. Calhoun, " Measurements of Neutron and Gamma-Ray Spectra in a Phantom Irradiated with 14-MeV Neutrons", presented at the Health Physics Society Annual 1
Meeting, Louisville, KY, June 21-26, 1981.
138.
D.E. Klein, S.R. Bull, and J.B. Miles, " Pressure Drop Measurements and Flow Visualization Surrounding Roughness
)
Elements", Journal of Energy, 4:3, 112 (1980).
]
139.
D.E. Klein, "ANS Student Involvement in Public Information - The University of Texas at Austin", Invited Paper, Trans. Amer. Nucl.
Soc., 34 (1980).
140.
R.B.P5e,H.R.Yoshimura,J.E.Hamann,andD.E.Klein,"An Assessment of Accident Thermal Testing and Analysis Procedures i
for Radioactive Materials Shipping Package", ASME 80-HT-38, April 1980.
l 141.
J.E. Hamann, D.E. Klein, R.B. Pop, and H.R. Yoshimura, j
"Modelling of Pool 11re Environments Using Experimental Results l
58
of a Two-Hour Test of a Railcar/ Cask System",: Paper #147, PATRAM-80, West Berlin, FRG., November 1980.
142.
M.A. Ross and D.E. Klein, " Synthetic Fuel Production Utilizing Texas Lignite and a VHTR for Process Heat", Trans. Amer. Nucl.
Soc., 35, (1980).-
P 143.
J.W. Davidson and D.E. Klein (co-editors), Proc.-of the International Conference on Nuclear Waste Transmutation, The University of Texas at Austin Press, March 1981.
144 M.A. Ross and D.E. Klein, " Synthetic Fuel Production Using Texas Lignite and a VHTR for Process Heat", Nuclear Technology, 56:3, (March 1982).
145.
T.L. Sanders and D.E. Klein, "A Modified Numerical Scheme for GCFR Flow Transient Analysis", Trans. Amer. Nucl. Soc., 39, (November 1981).
1 i
146.
M.A. Ross and D.E. Klein, " Synthetic Fuel Production Using Texas Lignite and a Very High Temperature Gas Cooled Reactor for Process Heat and Electrical Power Generation", The University of Texas at Austin Center for Energy Studies Research Report, 13, May 1981.
~
147.
M.M. Razzaque, J.R. Howell, and D.E. Klein, " Finite Element l
Solution of Heat Transfer for Gas Flow Through a Tube" IAA Journal 20:7, July 1982.
148.
S. Yang, J.R. Howell, end D.E. Klein, " Radiative Heat Transfer Through a Randomly Packed Bed of Spheres by.the Monte Carlo Method", AIAA/ASME 3rd Joint Thermophysics, Fluids, Plasma & Heat Transfer Conference, ASME 82-HT-5, St. Louis, Missouri, June 1982.
149.
J. Andersen and D.E. Klein, et al., " Peer Review of the Preliminary Design and Program Interfaces for the Transuranic Waste Package Transporter (TRUPACT)", Sandia Report, SAND 81-2405, June 1982.
150.
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 j
1982.
l 151.
S. Yang, J.R. Howell, and D.E. Klein, " Monte Carlo Simulation of Thermal Conduction Through a Randomly Packed Bed of Spheres", 7th International Heat Transfer Conference, Munich, Germany, 82-IHTC-91, September 1982.
152.
T.L. $snders and D.E. Klein, " Comparison Analysis of Severe Flow Blockages for Computational Efficiency Using COBRA", Proc. from Gas-Cooled Reactors Today Conference, British Nuclear Energy Society, London, England, September 1982.
59 l
L
153.
M.M. Kazzaque, J.R. Howell, and D.E. Klein, " Finite Element Solution of Radiative Heat Transfer in a Two-Dimensional Rectangular Enclosure with Gray Participating Media",
82-WA/HT-51, ASME Annual Meeting, Phoenix, Arizona, November 1982.
154 J.B. Smathers, N.E. Hertel, and R.G. Graves, "In Phantom Photon Spectra Measurements for High-Energy Neutron Therapy Sources",
Proc. from the Fourth Symposium on Neutron Dosimetry: Beam Dosimetry, Neuherberg/ Munich, Germany, June 1981.
155.
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 Nucl. Sci. and Engr., November 1981.
156.
Y. Kunimoto, J.W. Davidson, and N.E. liertel, "A Core Inventory Model for Fuel Trajectory Analysis in Fusion-Fission Symbiotic Systems", Trans. Amer. Nucl. Soc., 41, 1978 (June 1982).
157.
N.E. Hertel and W.E. Murphie, "The Use of Neutron and Gamma-Ray NE-213 Spectral Measurements and Calculations to Obtain Dosimetric Information for DT Neutrons", Medical Physics, 10:66, (1983).
158.
R. Lauclus, J.W. Davidson, and N.E. Hertel, " Calculation of the Differential Efficiencies of Organic Scintillator to Neutrons Above 10 MeV", Trans. Amer. Nucl. Soc., 43, 625 (November 1982).
159.
J.W. Davidson and N.E. Hertel, "Bonner Ball Detection Responses for Neutrons from Thermal Energies to 17.3 MeV", Health Physics Society Annual Meeting, Baltimore, Maryland, 1983.
160.
N.E. Hertel, J.W. Davidson, and R.M. Laucius, "NE-213 Response Matrix for Neutron Spectrometry Up to 50 MeV", Health Physics Society Annual Meeting, Baltimore, Maryland, 1983.
161.
N.E. Hertel, J.W. Davidson, and R.M. Laucius, "An NE-213 Response Matrix to 50 MeV", Trans. Amer. Nucl. Soc., 45, 607 (1983).
162 J.W. David 8on and N.E. Hertel, "An Equal Probability Neutron Detection System Using Bonner Spheres", Trans. Amer. Nucl. Soc.,
45, 609 (1983).
163.
M.M. Razzaque, J.R. Howell, and D.E. Klein, " Coupled Radiative and Conductive Heat Transfer in a Two Dimensional Rectangular Enclosure with Gray Participating Media Using Finite Elements",
ASME/JSME Thermal Engineering Joint Conference, ASME-H-35 Honolulu, Hawaii, March 1983.
164.
S. Yang, J.R. Howell, and D.E. Klein, " Radiative Heat Transfer Through a Randomly Packed Bed of Spheres by the Monte Carlo Method" Journal of Hest Transfer, 105:2, 325 (May 1983).
l 60
s-l l
165.
M.M. Razzaque, J.R. Howell, and D.E. Klein, " Finite Element Solution of Radiative Heat Transfer in a Two Dimensional Rectangular Enclosure with Gray Participating Media", (accepted by the Journal of Ileat Transfer).
166.
M.M. Razzaque, J.R. Howell, and D.E. Klein, " Coupled Radiative and Conductive Heat Transfer in a Two Dimensional Rectangular Enclosure with Gray Participating Media Using Finite Elements",
Journal of Heat Transfer, 106, 613 (1984).
167.
E.M.B. Sorensen, C.W. Harlan, M.D., T.L. Bauer, and A.
Pradzynski, " Hepatocyte Changes Following Selenium Accumulation in a Freshwater Teleost", The Amer. Journal of Forensic Medicine and Pathology, 3:3, 8 (1982).
168.
E.M.B. Sorensen and T.L. Bauer, "A Correlation Between Selenium Accumulation in Sunfish and Changes in Condition Factor and Organ Weight", Environmental Pollution Series A, 0143, 357 (1984).
169.
E.M.B. Sorensen, T.L. Bauer, J.S. Bell, and C.W. liarlan,
" Selenium Accumulation and Cytotoxicity in Teleosts Following Chronic, Environmental Exposure", Bulletin of Environmental Contamination and Toxicology, 29, 699 (1982).
170.
E.M.B. Sorensen and T.L. Bauer, " Selenium Induced Hematological l
Dyscrasia in Teleosts", Archives Environ. Contam. and Toxicology, 12, 135 (1983).
171.
E.M.B. Sorensen, P.M. Cumbie, T.L. Bauer, J.S. Bell, and C.W.
Ilarlan, " Histopathological, Hematological, Condition Factor and Organ Weight Changes Associated with Selenium Accumulation in Fish from Belews Lake, North Carolina", Archives Environ. Contam.
and Toxicology, 13, 153 (1984).
172.
E.M.B. Sorensen, R.R. Mitchell, A. Pradzynski, T.L. Bauer, and L.
Craham, " Serological Analyses of Hepat ocyte Changes Parallel l
Arsenic Accumulation in the Livers of Green Sunfish", (accepted by The Journal of Environmental Pathology, Toxicology and l
Oncology).
173.
N.E. Hertel and J.W. Davidson, "The Effect of Cadmium Covers on Bonner Sphere Responses", to appear in the Proc-. of the Personnel l
Radiation Dosimetry Symposium, Knoxville, Tennessee, October 1984.
174.
N.E. liertel and J.W. Davidson, "The Response of Bonner Spheres from Thermal Energies to 17.3 MeV", (accepted for publication Nuclear Instruments and Methods, (February 1985).
175.
A. Patterson-Hine, J.W. Davideor, and D.E. Klein,
" Characterization of Product Buildup in Continuously Processed Molten Salt Fusion Breeder Blankets", Trans. Amer. Nucl. Soc.,
(
45, (1983).
61
-v 176.
A. Patterson-Hine, J.W. Davidson, and D.E. Klein, " Contributions to the Thermal Power of continuously Processed TMHR Molten Salt Blankets", 10th Symposium on Fusion Engineering, Philadelphia, Pennsylvania, December 5-9, 1983.
o 177.
G.F. Polansky, J.P. Lamb, and D.E. Klein, "A Finite Element Analysis of Incompressible Laminar and Turbulent Flow with Heat Transfer", presented to the 5th International Symposium on Finite Elements and Flow Problems, The University of Texas at Austin, Austin, Texas, January 23-26, 1984.
178.
M. Ally, D.E. Klein, and T.L. Bauer, " Reconcentration Methods of Trace Elements in Water for EDXRF and INAA", 5t'n International Conference on Nuclear Methods in Environmental and Energy Research, Mayaguez, Puerto Rico, April 2-6, 1984.
179.
D.E. Klein and W.H. Miller, " Student ANS Branch Involvement in Public Information", Invited Paper, Trans. Amer. Nucl. Soc., June 1984.
180.
F.Y. Iskander, D.E. Klein, and T.L. Bauer, " Toxic and Other Elements in American Cigarette Tobacco Compared with International Brands", 17th Annual Meeting of Texas Association for Radiation Research, Denton, Texas, November 1984.
181.
F.Y. Iskander and R.H. Filby, " Formation of Anatase from Ti(IV)-pre-asphaltene Complexes under Coal Liquefaction Conditions", Fuel, 63, 280 (1984).
182.
F.Y. Iskander and R.H. Filby, "Speciation of Titanium in Solvent Refined Coal Using SESC-INAA", Proc. of American Nuclear Society Meeting, Fifth International Conference, Mayaguez, Puerto Rico, April 2-6, 1984.
183.
T.L. Sanders, D.E. KJein, and M.E. Crawford, "A Liquid Metal Facility for the Analysis of Phenomena Related to the Magnetohydrodynamics of Fusion Related Systems", Sixth Topical Meeting on the Technology of Fusion Energy, San Francisco, California, March 1985.
184.
T.L. Sanders, D.E. Klein and M.E. Crawford, "A Liquid Metal Facility for the Analysis of MHD Effects in Fusion-Related Systems", Fusion Technology, 8:1, (1985).
185.
A. Patterson-Hine, J.W. Davidson, D.E. Klein, and J.D. Lee,
" Characterization of the Effects of Continuous Salt Processing on the Performance of Molten Salt Fusion Breeder Blankets", accepted to J. of Fusion Energy.
186.
F.Y. Iskander, " Neutron Activation Analysis of an Egyptian Cigarette and its Ash", J. Radioanal. Nucl. Chem., 89, 511 (1985).
~~
62
v 187.
F.Y. Iskander, " Egyptian and Foreign Cigarettes. 1.. Determination of Trace Elements in Cigarette Filter Before and After Smoking",.
J. Radionnal. Nucl. Chem., 91,'191 (1985).
188.
F.Y. Iskander, " Cigarette Ash as a Possible Source of Environmental Contamination", Environ. Pollut. (Series B), 11 (1986).
189.
F.Y. Iskander, " Egyptian and Foreign Cigarettes. 2. Determination of Trace Elements in Tobacco, Ash, and Wrapping Paper", h Radionnal. Nucl. Chem., 97,, 107-(1986).
190.
F.Y. Iskander, T.L. Bauer, and D.E. Klein, " Determination of 28-Elements in American Cigarette Tobacco by Neutron Activation Analysis", Analyst, 111, 107 (1986).
191.
F.Y. Iskander, D.E. Klein and T.L. Bauer, " Determination of Trace Impurities in Aspirin Tablets by Neutron Activation Analysis", h 97,, 353 (1986).
Radioanal. Nucl. Chem.,
7 192.
M.M. Morad, F.Y. Iskander, L.W. Rooney,~and C.F. Earp, "Physico-chemical Properties of Alkali-cooked Corn Using Traditional and Presoaking Procedures", Cereal Chem., 63(3)
~
(1986) 255.
~
193.
F.Y. Iskander and M.M. Morad, " Neutron Activation Analysis of Texas Hard Red Winter Wheat and its Milling Fractions", American Association of Cereal Chemistry, 70th Meeting, Orlando, Florida, 1
paper 151, 1985.
l 1
194.
F.Y. Iskander, " Neutron Activation Analysis for Assessing the Concentration of Trace Elements in Laboratory Detergents", J.
~
Appl. Radiat. Isotopes, E (5) (1986) 435.
195.
F.Y. Iskander, T.L. Bauer, and D.E. Klein, "Some Considerations of Elements Content of Cigarette Wrapping Paper", TAPPI, 69 (5)
(1986) 134.
196.
F.Y. Iskander, M.M. Morad, D.E. Klein, and.T.L. Bauer, (1987).
" Protein, In-Vitro Protein Digestibility and Minerals Content of i
Hard and Soft Red Wheat Varieties", Cereal Chem. 64:285.
197.
F.Y. Iskander, (1987). Neutron activation analysis for measuring the unsaturation in edible oils.
J. Radioanal. Nucl. Chem.
Letters 118(2):149 198.
F.Y. Iskander and M.M. Morad, " Minerals and Protein Contents in Texas Hard Red Winter Wheat and Its Milling Fractions", Food 9
11 (1986) 1522.
- Science, 1
199.
F.Y. Iskander, D.E. Klein, T.L. Bauer, and M.M. Morad, " Protein and Nutritional Elements Content in Texas Wheat", 18th Annual i
Meeting of Texas Association for Radiation Research, San Antonio, l
Texas, November 1985.
63
a 200.
F.Y. Isk mder and M.M. Morad, "Multielement Determination in -
Wheat and Eran", Radiaochem. Radioanal. Letters, 105 (3) (1986) 151.
201.
0.I. Asubiojo, J.A. Adepetu, and F.Y. Iskander, " Determination of the Chemical Composition of Nigerian Harmattan Dust by
~
Instrumental Neutron Activation Analysis", The 7th International Conference, Modern Trends in Activation Analysis, Copenhagan, Denmark, 1986.
I 202.
F.Y. Iskander, (1987). Maturation stage and mineral content in j
soybeans.
J. Food Chem. 24:29, 1
203.
T.R. Ajayi, F.Y. Iskander, 0.1. Asubiojo, D.E. Klein, Geochemistry'of upper cretaceous classic sediments of Ifon area,
)
S. W. Nigeria. Accepted, Nigerian Journal of Mining and Geology..
204.
K.R. Davis, F.Y. Iskander, H. Ashour, H.F. Hassan, Aluminum content in Egyptian breads.
Submitted to Cereal Chem.
205.
F.Y. Iskander (1986). Use~of NAA to determine nutritive elements
)
in immature and mature soybeans. Trans. Am. Nucl. Soc., 53:170 205.
J.A. Adeptu, 0.I. Asubiojo, F.Y. Iskander, and T.L. Bauer, (1988). Elemental composition of Nigerian harmattan dust for ecological monitoring using instrumental neutron activation analysis.
J. Radionnal. Nucl. Chem. 121(1):141.
207.
R.D. Manteufel, D.E. Klein, and H.R. Yoshimura, " Benchmarking of Q/TRAN Thermal Analysis Computer Code", PATRAM-86, IAEA-SM-286/95P, pp. 465-474.
208.
R.D. Manteufel, D.E. Klein, and H.R. Yoshimura, " Comparison Study of PATRAN and Q/TRAN for Thermal Analysis of Shipping Containers", 1986 PATRAM User's Conference.
209.
G.F. Polansky, J.P. Lamb and D.E. Klein, " Finite Element j
Simulation of Recirculating Flows with Heat Transfer",
1 Communication in Applied Nummerical Methods, Vol 3, No. 1, P.
)
17-22, Jan-Feb, 1987.
210.
F.Y. Iskander, " Determination of iodine value by Br/INAA."
Accepted J. Am. Oil Chem Soc.
211.
0.1. Asubiojo, F.Y. Iskander,(1988). "A Trace element study of commercial infant milk and cereal formulas."
J. Radioanal. Nucl. Chem. 125:265.
212.
K.R. Davis, F.Y. Iskander, H. Ashour, H.F. Hassan, " Aluminum content in Egyptian breads." Accepted Journal of Food Chemistry.
~
213.
F.Y.'Iskanrte and A. Askar, (1987). " Minor and Trace elements in
~
two faba bean meals." Ernahrung-Kutrition 11:756.
I 64
l 214.
D.E. Klein, " Nuclear Engineering Teaching Laboratory at The University of Texas at Austin", invited paper, Trans Am Nucl.
Soc., 55, November, 1987.
215.
R.D. Manteufel, D.E. Klein and H.R. Yoshimura, "An Evaluation of
)
a Translator for Finite Element Data to Resistor / Capacitor Data j
for the Heat Diffusion Equation", 1987 ASME Annual Meeting, j
HTD-Vol. 88, pp 67-72.
)
216.
J.E. Hamann, D.E. Klein and H.R. Yoshimura, " Thermal Analysis of a Spent-Fuel Railcar Shipping Cask in an Engulfing Fire", Sandia National Laboratories (submitted 1987).
j k
217.
Iskander, F.Y. Determination of Iodine value by Br/INAA.
(Abstract). The 102nd Annual meeting and exhibition of the
]
Association of Official " Analytical Chemists. Palm Beach, 1
l Florida, Aug. 1988. Paper #336.
218.
- Behardi, F., Isk'.ander, F.Y., Freeland-Graves, J., Line, P.H. and Bauer, T. (1988). Mineral Balance in young men fed a constant conventional diet.
(Abstract). Federation of American Societies
]
of Experimental Biologists, Las Vegas, Nevada. May 1988.
J l
219.
N.E. Hertel, C.G. Pollard, and B.A. Gantner, " Transportation Worker Exposure from the Trnaport of BRC Radwaste," Proceedings of the Waste Management '88 Symposium, Tuscon, February 28-March 3, 1988.
220.
R.S. Hartley, N.E. Hertel, and J.W. Davidson, " Neutron Multiplication in Beryllium," accepted for publication as a paper in Fusion Engineering and Design.
221.
N.E. Hertel, R.S. Hartley, and J.W. Davidson, " Measured and l
Calculated Neutron Leakage Multiplication for Beryllium Shells,"
Trans. Am. Nucl. Soc. 56 123 (1988).
222.
N.E. Hertel, J.W. Davidson, and R.S. Hartley, " Analysis of the Texas Beryllium Neutron Leakage Multiplication Experiments,"
Eighth Topical Meeting on the Technology of Fusion Energy, Salt Lake City, Utah, October 9-13, 1988.
223.
T. Parish, R. Carrera, and N.E. Hertel, " Nuclear Radiation Analysis in the IGNITEX Ignition Experiment," Eighth Topical Meeting on the Technology of Fusion Energy, Salt Lake City, October 9-13, 1988.
l t
224.
R. Carrera, M. Driga, J.H. Gully, N.E. Hertel, J. Hopf, K.T.
Hsieh, E. Montalvo, C. Ordonez, T. Parish, M.N. Rosenbluth, W.A.
Walls, W.G. Weldon, M. Werst, and LH. Woodson, " Ignition Experiment in a Single-Turn-Coil Tokamak, Eighth Topical Meeting on the Technology of Fusion Energy, Salt Lake City, October 9-13, 1988.
65
.y 225.
N.E. Hertel and J.C. Mcdonald, " Dose Equivalent and Phantoms in Conventional Calibration Practice," Trans. Am. Nucl. Soc. 57, 219 (1988).
o 226.
- Klein, D.E., Taborek, J.J., and Fair, J.R., " Energy Savings by Use of Disk / Donut Baffling in Tubular Heat Exchangers," Tenth Annual Industrial Energy Technology Conference, Houston, Texas, 1988.
227.
- Hopf, J.,
- Carrera, R., Klein, D. and Montalvo, E., " Plasma Physics Simulation of Alternative Modes of Operation in the IGNITEX Experiment," Thirtieth Annual Meeting, PLASMA Physics Oct-Nov 1988.
l l
I l
l l
l i
O I
66
______________m
$ a 6RA COLLEGE OF ENGINEERING 8
a J r S'.d 6t{ff:Ag' THE UNIVERSITY OF TEXAS AT AUSTIN L-
'%;g y Departmentof hiechanicalEngineering NuclearEngineeringProgram Austin, Texas 78712-(312)4713136
- e. a March 28, 1989 USNRC Document Control Desk Washington, D.C.
20555
Dear Sir:
Enclosed is one copy of the calendar year 1988 Annual Report.
These are being submitted according to 10 CFR Section 50.59.
Sincerely, Ike,we 4 ). bd Dr. Thomas L. Bauer Assistant Director Nuclear Engineering Teaching Laboratory TLB:jgr Enclosure cc:
Dr. Dale Klein
~.,
_