ML20069H626

Annual Rept for Univ of Texas at Austin Nuclear Engineering Teaching Lab,1982

ML20069H626
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Site:	05000192
Issue date:	01/31/1983
From:	Bauer T, Klein D TEXAS, UNIV. OF, AUSTIN, TX
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1982 Annual Report i

of The University of Texas at Austin Nuclear Engineering Teaching Laboratory January 1, 1982 - December 31, 1982 D. E. Klein, Director T. L. Bauer, Supervisor Taylor Hall 104 512-471-5136 e January 1983 8304066275 830401 PDR ADOCK 05000192 R PDR

TABLE OF CONTENTS O

Page List of Figures . . . . . . . . . . . . . . . . . . . . ii Li st of Tab l es . . . . . . . . . . . . . . . . . . . . . iii I. Introduction. . . . . . . . . . . . . . . . . . . . . . I II. Laboratory Adminis trati on . . . . . . . . . . . . . . . 5 A. Organization B. Personnel C. Reactor Committee D. Radiation Safety Committee E. Report to College of Engineering III. Laboratory Development. . . . . . . . . . . . . . . . . 8 A. Organization B. Nuclear Engineering Teaching Laboratory C. Neutron Activation Analysis Facilities D. Nuclear Radiation Laboratory IV. Laboratory Operation and Utilization. . . . . . . . . . 11 A. Reactor Facility B. Facility Changes V. Laboratory Inspections. . . . . . . . . . . . . . . . . 22 A. Inspection by the Nuclear Regulatory Commission B. Inspections by the Texas Department of Health C. Other VI. Public Service Activities . . . . . . . . . . . . . . . 23 A. Summer High School Science Teachers Symposium B. Lectures and Presentations C. Tours and Radiation Monitoring VII. Research Activities . . . . . . . . . . . . . . . . . . 24 VIII. Publications from the Nuclear Engineering Teaching Laboratory . . . . . . . . . . . . . . . . . . . . 34 e

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List of Figures Figure No. Page

1. Floor Plan of Nuclear Reactor Laboratory 2

2. Floor Plan of the Nuclear Engineering 3 Teaching Laboratory

3. Organization Chart of the Nuclear 6 Engineering Teaching Laboratory

4. Comparison Burn up vs year 15

5. Comparison of number of samples 16 irradiated vs year W

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List of Tables Table No. Page

1. Reactor Scrams 12

2. Comparison of Yearly Inadvertant Scrams 12

3. NETL Performance Data 1982 13

4. Comparison of Previous Utilization Data 14

5. Statistical Summary of Radiation Exposures 17

6. Courses Utilizing NETL Facilities 19

7. Research Funding 25 m

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I. INTRODUCTION

= This report has been prepared by the staff of the Nuclear Engineering Teaching Laboratory (NETL), The University of Texas at Austin, to satisfy 4

the reporting requirements of the U.S. Department of Energy Contract Number At-(40-1)-3919 and 10 CFR 50.59. The report covers the period j from January 1, 1982 to December 31, 1982.

j The Nuclear Engineering Teaching Laboratory (NETL) is a part of the Mechanical Engineering Department in the College of Engineering at The University of Texas at Austin, Austin, Texas. The programs major equipment consists of a 250 kW TRIGA Mark I reactor operated in pulsing and steady-i state modes. The reactor laboratory and adjacent laboratory areas are shown in Figures 1 and 2. Other equipment maintained by the NETL program includes two Cockcroft-Walton 14 MeV neutron generators, a Lockheed Aerojet subcritical assembly, and a 1150 curie Co-60 irradiator. Isotopic neutron sources available include three californium-252 sources and six plutonium-t i

beryllium sources. A wide array of detectors and electronic equipment are available to provide measurement and analysis capability of laboratory produced or maintained radiation sources.

Changes in the NETL program occur as a continuing response to achieve effective operation of various NETL projects and program development.

. During the past year the following events that represent a significant impact on the NETL program occurred:

a. Radiochemist position (half time) was vacated. A replacement l was found temporarily but later resigned.

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b. Three new Senicr Operator licenses were issued and one Senior Operator license renewed.

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c. Operation license R-92 is still effected by timely renewal pending completion of the license renewal processes scheduled

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for NRC fiscal year 1983.

. d. A new emergency plan has been submitted for NRC review and approval .

e. Completion of the review and revision of all laboratory procedures was completed.

f. The startup and log power channels of the reactor console have been replaced by a newer wide range channel manufactured by General Atomic.

g. A new data acquisition and analysis system for neutron activa-tion analysis was installed.

h. " An order for three new undergraduate counting stations to supplement teaching of radiation detection and measurement was completed.

i. University plans for complete renovation of Taylor Hall and construction of an adjacent building were scheduled for 1983 or later.

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i II. LABORATORY ADMINISTRATION i

A. Organization j ,

The present organizational chart of the NETL program is presented in Figure 3. Budgeted NETL staff funding is provided for a Supervisor /

Assistant Director, technician / operator, radiochemist, operator, and secreta ry.

B. Personnel

! Personnel associated with the laboratory consist of NETL staff,

! faculty, students, and certain other university personnel. The following lists reflects personnel involved in the NETL program during the past year.

1. Staff and Faculty Personnel e Director D.E. Klein Assistant Director / Supervisor T.L. B'uer+

Nuclear Technical Specialist N. Povio+

Nuclear Technical Specialist M. Krause+

Radiochemist S. Piorek Assistant Professor N.E. Hertel Administrative Secretary M.G. Morrison

2. Support Personnel Adjunct Associate Professor D.G. Anderson &

Safety Officer H.W. Bryant Research Scientist J.W. Davidson

, 3. Graduate Assistants i M. Ally 4

A. Gaines

, B. Gantt

! M. Krause+

R. Laucius F. Patterson l M. Razzaque

. T. Sanders

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l 4. Student Assistants i G. Anderson

! . A. Chapa

S. Reichert S. Sherwood

+--Licensed Senior Operator L

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J Dean of Engineering 4

Chairman M. E. Department .

Director

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_ _ _ _ _ _ _ _ _ _ _ _ CONSULTATION AND VET 0 POWER FIGURE 3 - ORGANIZATIONAL CHART e

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t I C. Reactor Committee i 1. Connittee Composition

Regular Members

(9/1/82) j Dr. Dale Klein Dr. Joe Ledbetter

, Dr. Harris Marcus (Chairman)

Dr. Nolan E. Hertel Mr. J. Gluck (student)

Ex Officie Members:

Dr. H. G. Rylander, Chairman, Department of Mechanical Engineering

Mr. H. W. Bryant, University Radiation Safety Officer Dr. T. L. Bauer, Supervisor, Nuclear Engineering Teaching Laboratory

, 2. Meeting Frequency l The Reactor Committee met four times for the calendar year of 1982 (March 31, July 29, October 14, and January 7)

D. Radiation Safety Committee

1. Committee Composition

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i Dr. P. Riley, Chairman 2

Dr. l.. O. Morgan

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Dr. C. Desjardins Mr. H. W. Bryant, Ex Officio i

2. Meeting Frequency The Radiation Safety Committee met twice during the calendar l

year of 1982 (April 14 and November 11).

., E. Report to the College of Engineering Each year the Reactor Committee provides a report to the Dean of the College of Engineering describing activities of the committee and a review or assessment of the operation of specific portions of the NETL program concerning the reactor and other radiation producing equipment.

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III. LABORATORY DEVELOPMENT

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A. Organization

. Dr. Dale E. Klein continued as the Director and Dr. Tom L. Bauer continued as Reactor Supervisor during the past year. Technical and I secretarial personnel also remained unchanged. Stanislaw Piorek filled the vacant radiochemist position.

The radiochemist position was increased from half to full time by decreasing one technical position to half time. Unfortunately, Stanislaw Piorek resigned and a new search was initiated for a full time successor.

j Key faculty and university support personnel remained unchanged.

B. Nuclear Engineering Teaching Laboratory The Nuclear Engineering Teaching Laboratory is part of the Nuclear Engineering Program at The University of Texas.

The Nuclear Engineering Teaching Laboratory's central feature is a Mark I TRIGA thermal fission reactor. Originally licensed by the Atomic Energy Commission to operate at 10 KW in 1963, the nuclear reactor l and the associated laboratory equipment have been updated over the past years and the research capabilities of the Laboratory are now more i

i diverse. In 1968, the facility license was amended to allow the TRIGA i

reactor to operate at a steady state power level of 250 KW and pulsed power of 250 MW which increased experimental capabilities.

Other radiation producing devices maintained by the Laboratory are a several thousand curie Co-60 irradiator, vertical neutron beam tube, i subcritical assembly, industrial x-ray source,14 MeV neutron generator, and several isotopic neutron sources. Different types of radiation

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detection devices provide the capacity to monitor or analyze the various radiation sources.

One of the functions of the nuclear reactor and its associated

. equipment has been to teach and demonstrate the fundamentals of reactor operation. Several organized classes routinely utilize the reactor facility. Numerous other classes, organizations and groups schedule tours or demonstrations of the reactor facility. Approximately 1,150 persons were admitted into the reactor facility during the past year.

The use, operation, regulation, security, and monitoring of the Nuclear Engineering Teaching Laboratory is controlled by the United States Nuclear Regulatory Commission, the Nuclear Reactor Committee of The University of Texas, the Director of the Nuclear Engineering Teaching Laboratory, the Radiation Safety Committee and the Texas

. Department of Health Radiation Control Board.

B. Neutron Activation Analysis Facilities The Nuclear Analytical Laboratory has provided support for individual projects ranging from student laboratory support for advanced classes in chemistry, zoology, physics, and engineering to investigative projects in environmental monitoring. Scientific articles based upon the results of sponsored and unsponsored research by this laboratory have been published or accepted for publication in several journals and proceedings, and have been presented at conferences at the state, national and inter-national level.

. Radiation detection systems available include gamma ray spectroscopy HpGe detection acquisition and analysis system, multi sample a-S propor-tional counter, Nal detectors, Si(Li) detector, neutror, detectors and associated electronic modules to accomplish several types of standard 9

I nuclear measurements. An important function of the laboratory is to i support various research projects with the neutron activation analysis method and other related nuclear radiation research techniques.

C. Nuclear Radiation Laboratory The Nuclear Radiation Laboratory at Balcones Research Center has been utilized by the students and staff of the Nuclear Engineering Program at The University of Texas at Austin for the past several years.

The primary use of the building was to house and operate a 14 MeV Texas Nuclear neutron generator. When the Nuclear Engineering Teaching Laboratory acquired three (3) Californium-252 sources from Louisiana State University in 1973, the Nuclear Radiation Laboratory became the logical place for their storage and use due to the space and availability of the already installed neutron shielding around the neutron generator.

252 Thus, with the acquisition of Cf , students and staff can perform experiments utilizing not only the high energy neutrons from the neutron generator but fission spectrum neutrons from Cf 252 In addition to the

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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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IV. LABORATORY OPERATION AND UTILIZATION

. A. Reactor

1. Operation During this reporting period the reactor operated for a total of 247.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> while supporting numerous nuclear engineering and operation courses, research, and other related activities.

Fuel burnup was approximately two-thirds grams from 16,150 kW-hrs of operation.

2. Maintenance During 1982 maintenance consisted of routine repair and adjust-ments, plus a reactor console improvement project. Both minor improvements, a physical rearrangement of console functions, and a major channel replacement were effected.

3. Safety 4

Inadvertant reactor shutdowns (" scrams") occurred 8 times during 1982 compared to 7 times the previous year. The scrams

are categorized according to the type of initiating event and the total number compared to previous years in Tables 1 and 2.

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4. Utilization Reactor utilization is measured by the number of operation hours (magnet power on), amount of energy produced (kW-hrs), and number of samples irradiated in reactor experiment facilities.

The data is presented in Tables 3 and 4 and Figures 4 and 5.

The effect of reactor operation on personnel radiation exposures are included in Table 5.

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l TABLE 1 REACTOR SCRAMS Intentional -- 10 Operator --

0 Instrument Error --

8 Power Outage --

0 Safety -- 0 Total -- 19

. TABLE 2 COMPARIS0N OF YEARLY INADVERTANT SCRAMS

'63 '64 '65 '66 '67 '68 '69 '70 '71 '72 '73 10 9 3 4 3 11 15 11 13 6 10

'74 '75 ' 7f[ '77 '78 '79 '80 '81 '82 4 7 5 9 11 12 7 7 8

• Inadvertant scrams are defined as all scrams that were not intentionally initiated.

• • Corrected to reflect log book data 12 1

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TABLE 3 NUCLEAR ENGINEERING TEACHING LABORATORY PERFORMANCE DATA, 1982 Total Hours Total Number of Reactor In Burn-up Samples Operation * (kW-hrs) Irradiated First Quarter 54.7 725 25 1982 Second Quarter 74.7 4943 53 1982 Third Quarter 78.4 5883 142 1982 Fourth Quarter 39.8 4599 74 1982 TOTAL 247.6 16150 294

• Time Reactor Key on; includes certain experimental setup time, maintenance, etc.

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. TABLE 4 COMPARIS0N OF PREVIOUS UTILIZATIC1 DATA Total Hours Total Number of Reactor In Burn-up Samples Operation * (kW-hrs) Irradiated Year 1965-66** 104.5 251 63 1966-67 150.0 595 202 1967-68*** 342.6 23,168 2449 1968-69 260.8 49,985 1452 1969-70 222.0 36,477 1640 1970-71 262.5 53,912 2990 1971-72 222.8 38,624 -1946 1973 318.6 45,794 1347 1974 226.1 27,641 778

. 1975 2 07 .0 20,450 363 1976 135.7 11,312 468 1977 139.3 7,509 164

- 1978 171.9 26,870 178 1979 311.6 72,616 1568 1980 184.1 11,760 150 1981 258.5 18,165 330 '

1982 247.6 16,150 294

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• Includes experimental setup time, maintenance, etc.

• • 1965 was the first year the utilization data were maintained.

*** Reactor upgraded from 10 to 250 kW during this academic year.

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YEAR NUMBER OF SA*1PLES IP. RADIATED f

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TABLE 5 STATISTICAL

SUMMARY

OF RADIATION EXPOSURE 1982 Range of Exposure Number of in REM Individuals Non-measurable exposure 13 0.0 - 0.1 7 0.1 - 0.25 0 0.25 - 0.5 0

. 0.5 - 0.75 0 0.75 - 1.0 0 1.0 - 2.0 0 2.0 - 3.0 0 17

5. Courses Table 6 lists the courses at The University of Texas at Austin that make some use of the reactor and its functions during the course of student instruction.

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TABLE 6

- Courses Utilizing the Reactor and Associated Facilities Mechanical Engineering Department Course Number Course Description ME 361F Introductory Nuclear Laboratory -

studies in radioactive decay, activation, detection and measurement.

ME 379M Reactor Operations - studies in nuclear reactor parameters, instrumentation characteristics and regulation.

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

- suamer course for foreign students.

ME 377K Projects in Mechani 11 Engineering -

- individual study and experiment projects for undergraduates.

ME 397 Current Studies in Engineering - special projects course for graduate study of selected topics.

Additional Courses in Other Departments GE0 388L Isotope Geology - graduate course CH 376K Advance Analytical Chemistry - senior level course in instrumental and analytical methods.

CE 390L Environmental Analysis - graduate course PHR 370K Nuclear Pharmacy - senior level course in measurement and analysis methods with nuclear pharmaceuticals.

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1 B. Facility Changes

1. Wide Range Channel Griginal equipment startup channel and log power channel were removed and replaced by a new wide range channel with percent power measurement capability. Scram signals for low source

! count,high voltage, period, and percent power were added to the original scram bus. The only scram removed from the original i bus was the period scram. A scram on high log power was not 4

implemented. The solid state channel with calibration circuits, power supplies and single detector replaces two separate non-j.

overlapping detectors and channels. For pulse mode operation the extended scram bus is shorted to remove the wide range channel operation.

. 2. Console Improvements To obtain greatest advantage of the new wide range channel a i physical rearrangement of the original console instrumentation i configuration was made. Several minor physical changes in the l water system alarms were also made to provide all alarm indica-l tion in a common area on the console. The replaced channels l are maintained for additional instrumentation to experimenters, i

! students, or operators.

3. Plans for renovation of Taylor Hall and future construction that will impinge on the reactor facility revised the requirements

, for operation of an exhaust ventilation system. The ventilation requirements are being~ reevaluated and the ventilation exhaust I

system maintained in a secured condition until future requirements

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are firmly established.

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4. A new gamma-ray spectroscopy detection, acquisition, and analysis system has been obtained to support research activities with neutron activation analysis. The system uses a high purity germanium detector and microcomputer processing system.

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V. LABORATORY INSPECTIONS No laboratory inspections by NRC or TDH personnel occurred during the calendar year 1982. Routine inspections by university radiation safety personnel, fire safety personnel, and reactor committee represen- '

tatives were conducted at periodic intervals.

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_ _ _ = - _ ._.

VI. PUBLIC SERVICE ACTIVITIES j . These activities include those other than research projects or assistance provided in the pursuit of research which are covered in Section VII of this report. In this section the subjects are symposiums, lectures, presentations, and tours.

A. Summer High School Science Teachers Symposium j Funded by the Electric Utility Companies of Texas, this program

! was designed to familiarize high school science teachers with the theory i i

and technology of energy resources. During the summer of 1982, 26 I teachers participated in the program.

B. Lectures and Presentations

On numerous occasions during 1982 the NETL staff gave talks on subjects including

" Nuclear Reactor Satety," " Nuclear Engineering and Society," "Research and Development of Energy Resources," " Energy and i

e the Environment," and "What Happened at Three Mile Island."

i j C. Tours and Radiation Monitoring During the calendar year of 1982 over 1,150 persons visited the lab. Most of these persons represented educational, civic, or industrial organizations, while others were part of formal engineering laboratory groups. All persons working in or around the laboratory are provided with personal radiation monitoring devices while tour group members are

randomly monitored. Measurable exposure to tour group members was in i

the non-measurable exposure range as indicated by pocket dosimeters.

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VII. RESEARCH ACTIVITIES The Nuclear Engineering Teaching Laboratory is pursuing research in numerous areas which are sponsored by the organizations listed below.

Major research funding is shown in Table 7.

A. The U.S. Department of Energy has provided research support by providing reactor fuel for the operation of The University of Texas at Austin TRIGA reactor.

B. The Electric Utility Companies of Texas have sponsored Summer High School Science Teachers Symposium, a program designed to familiarize these teachers with the theory and technology of energy resources.

C. Development of a Preconcentration Method for Field Sampling of Uranium Personnel: Dale Klein, NETL Mohammed Ally, NETL Sponsored by: Nuclear Engineering Teaching Laboratory

Description:

e Two basic techniques are used presently at the Nuclear Engineering Teaching Laboratory at The University of Texas at Austin for the determination of trace elements (e.g. uranium). These include neutron activation analysis and x-ray fluorescence. When the elements to be examined are present in trace quantities, either a large sample l

l must be measured or the sample must be preconcentrated. There are I

l several advantages of a preconcentration method and the objective of this l -

project is to develop a suitable method for the analysis of trace elements, including uranium, in water. In previous years a method was developed for l

transition elements in water. Experiments were extended to Cr, Mn, Th and U.

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TABLE 7 RESEARCH FUNDING Texas Atomic Energy Research Foundation $37,000 (5/1/81 - 4/30/82)

Department of Energy -- Fuel Program ----

Center for Energy Studies 15,000 (9/1/81 - 8/31/82)

National Science Foundation (5/15/80 - 10/31/82) 39,975 (2/81 - 2/83) 76,373 "

University of Texas (5/81)

Safety Related Purchases 26,510 College of Engineering Equipment Fund 9/81 53,000 Institute of Nuclear Power Operations (9/1/80 - 5/31/82) 8,000 TOTAL $255,858 e

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D. Modification of COBRA-4 Personnel: Dale Klein, NETL

, Tom Sanders, NETL Sponsored by: General Atomic Company

. Center for Energy Studies Descri ption:

The transient version of the thermal-hydraulic computer code COBRA-4 was modified. Considerable modifications were made to COBRA-4 to enhance its application for analyzing Gas Cooled Fast Breeder Reactor (GCFR) transients. This includes new numerical techniques to speed up calculations. The completed model is capable of analyzing transient events for reactor safety studies.

E. Thermal Analysis of a Spent Fuel Shipping Cask in an Engulfing Fire Personnel: Dale Klein, NETL James E. Hamann, NETL Sponsored by: Sandia Laboratories

Description:

A thermal analysis using the computer code HEATING 5 was completed to predict the temperature distribution in a nuclear fuel shipping cask. Results from this detailed model are compared with data from a full scale thermal test conducted by Sandia. The Sandia test involved a full-scale shipping container in an engulfing fire for more than 120 minutes. The HEATING 5 model enables thermal analysis for a 3-dimensional transient system where a change in phase occurs. Although this project is directly applicable for a spent-fuel shipping cask, other heat transfer systems can be examined.

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F. Heat Transfer and Friction Factor Analysis for Artifically Roughened Surfaces Personnel: Dale klein, NETL J. Parker Lamb, Mechanical Engineering Mike Krause, NETL Gary Polansky, Mechanical Engineering Sponsored by: Center for Energy Studies National Science Foundation

Description:

The proposed research is to determine the heat transfer and friction characteristics for surfaces with discrete roughness geometry.

Two major aspects are ta be examined in that this is both an experimental and an analytical investigation. Values of R(h+) and G(h+) in the universal velocity and temperature profiles will be examined. New experimental techniques have been developed at The University of Texas at Austin to measure local heat transfer values surrounding discrete roughness elements. A test assembly to examine artifically rougheneu

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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. Anal;tical predictions will be made utilizing fundamental parameters in boundary layer theory coupled with the latest information on rough surfaces using integral techniques. Results from the experimental and analytical methods will be compared in order to gain insight as to the dominant mechanism involved for the use of discrete rough surfaces. This research has fundamental application for heat transfer augmentation. Primary applica-tion includes heat exchangers and the Gas Cooled Fast Breeder Reactor (GCFR).

The modeling will be directed towards the GCFR design conditions. This is the fifth year of a seven year study.

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G. Finite Elements in Radiative Heat Transfer in Asboring/ Emitting i Medium Personnel: Dale Klein, NETL Muhammad Razzaque, NETL Sponsored by: Texas Atomic Energy Research Foundation

Description:

An exact analysis of radiative heat transfer coupled with conductive and/or convective modes was performed to predict the tempera-ture distribution inside a medium and the heat flux distribution at all bounding surfaces of an enclosure with a medium having absorbing-emitting properties. The Galerkin finite element technique was employed to solve numerically the resulting highly nonlinear partial integro-differential energy equation utilizing isoparametric, quadrilateral elements with Lagrangian tensor product biquadratic shape functions. The walls were assumed to be either gray or black with any given temperature distribu-tions and the medium was assumed to be gray. Internal heat generation within the medium can also be included. One often encounters such physical situations in practical engineering problems, particularly in a high temperature system where radiation plays an important role in the heat transfer process such as fusion reactors. The work has been concluded.

H. Fission Product Absorption in Continuously Processed Fission Suppressed Fusion Hybrid Reactor Blankets Personnel: Dale Klein, NETL J.W. Davidson, NETL Ann Patterson, NETL Sponsored by: Department of Energy Fellowship

Description:

28

The effects on blanket performance of fission product absorpt' 'n lithium / molten salt hybrid reactor blankets is being investigated. Neutron flux spectra in blankets of varying fuel and fission product compositions are being determined using the discrete ordinates codes, ANISN, and D0T-IV with multigroup cross section data from VITAMIN-C. Flux levels and spectrally weighted cross section libraries for the blanket materials, fuel, and fission products will be established for use in the depletion analyses. Generation and depletion of the various isotopes in the blanket will be calculated using ORIGEN.

A lumped fission product model will be used in the transport calculations; however, detailed information concerning the constituents of the lump will be included in the depletion analysis.

In addition to full and partial reprocessing of the molten salt,

, alternative processing concepts will be investigated. A parametric study of the effects of processing performance will be carried out. This study will result in the characterization of the fission product concentration in the molten salt with respect to isotopics, neutron absorption, and the effects on blanket parametcrs such as the tritium and fissile breeding ratios.

I. Construction of a Laroe Benjamin Counter Personnel: Nolan E. Hertel, NETL Richard Si vage, NETL Sponsored by: Texas Atomic Energy Research Foundation

Description:

A large spherical proton-recoil proportional counter is being constructed for use in measuring neutron energy spectra below 2 MeV.

By differentiating proton-recoil spectra obtaiied with the detector filling 29

gas (methane or hydrogen) at various pressures, an unknown neutron energy ,

spectrum can be reconstructed. This detector will be used with an existing NE-213 spectrometry system to make possible neutron spectral measurements from 20 MeV down to approximately 10 kev. The two detection systems will then be employed in fusion energy related neutronics studies.

J. Measurement of Gamma-Ray Spectra Resulting in Tissue from Bombardment with Neutron Radiotherapy Beams Personnel: Nolan E. Hertel, NETL James B. Smathers, UCLA Robert G. Graves, University of Rochester Sponsored by: National Institutes of Health: Public Health Service Grant CA12542 from the National Cancer Institute

Description:

Measurements of gamma-ray spectra produced in tissue-equivalent liquid when bombarded by 50-MeV d+-Be and 42 MeV p+-Be neutron beams have been performed. These measurements were done at the Texas A&M University Variable Energy Cyclotron using an NE-213 spectrometer. Analysis of the 1

measurements will help to determine gamma-ray spectral distribution in tissue during radiotherapy treatment. These spectral distributions are currently being used to calculate the average gamma-ray energy as well as the average gamma-ray mass-energy absorption coefficient.

K. High-Energy Neutron Transport Studies Personnel: Nolan E. Hertel, NETL Regina Laucius, NETL Sponsored by: National Science Foundation

Description:

The principal thrust of this project is to develop the cap-

~

ability to routinely and accurately measure high-energy neutron spectra from 1 to 50 million electron volts (MeV). An effective means of 30

performing such measurements is to utilize the recoil pulse-height data from an organic scintillation detector. The reconstruction of the

~

unknown neutron spectrum from the recoil data requires the use of a matrix describing the detector's response to monoenergetic neutrons over the energy range of interest. To meet this need, a neutron response matrix from 1 to 50 MeV is being constructed from recent neutron time-of-flight data. The resulting unnormalized experimental pulse-height distribution data will be used in conjunction with various computer codes to form the matrix. This matrix can then be applied with existing unfolding codes to reconstruct unknown energy spectra. High-energy spectral measurements could be made using this technique at neutron radiotherapy facilities and intense neutron source facilities such as fusion materials radiation damage facilities.

L. Transient Analysis of Fissile and Fusile Fuel Trajectories for Hybrid and Convertor Reactor Symbioses Personnel: Nolan E. Hertel, NETL J. Wiley Davidson, NETL Yukitaka Kunimoto, NETL Sponsored by: Texas Atomic Energy Research Foundation

Description:

Fissile fuel bred in a hybrid fusion reactor blanket may be used to expand the fission convertor reactor economy. Similarly, fusile fuel (tritium) produced in the convertor reactors may be used to expand the fusion economy. A model has been developed to predict the rate at which such a symbiotic economy could grow. The model allows the determination of time dependent fissile and fusile inventories for

~

stockpiles, as well as for both hybrid and convertor reactor cores and blankets. This transient analysis is being performed for a variety of 31 1

- - - . . - . . - . - - . ~ - - - .,.- . . . . , - - , -- - - - - - , .- . - , - - - .

fission convertor and anticipated fusion hybrid reactor concepts and fuel cycles. Such an analysis will allow the prediction of initial D

stockpile requirements in addition to providing a more accurate assessment of short term symbiotic system doubling times.

M. Neutron Transport Studies: Neutron Multiplication by Beryllium Personnel: Nolan E. Hertel, NETL J. Wiley Davidson, NETL Sponsored by: Pending, National Science Foundation

Description:

The use of beryllium as a neutron multiplier is central to the current fusion breeder design. Recent measurements of beryllium neutron multiplication and reevaluations of beryllium nuclear data indicate that the multiplying performance of beryllium previously 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 might well change. It is tantamount to the current fusion breeder concepts that the issue of beryllium neutron multiplication be resolved. Therefore, an experiment using a spherical shell of beryllium is being proposed.

The beryllium experiment has been designed to measure multiplication 252 resulting from DT, DD, PuBe, and Cf neutron sources being placed in a spherical shell. By doing so the sensitivity of the multiplication to spectral shape can be observed. In addition, the use of these four sources helps to simulate the effect of neutron source degradation in a fusion reactor. The neutron multiplication will be obtained directly from summing weighted Bonner ball measurements of the neutron leakage.

32

The neutron multiplication obtained in this manner will provide a number which tests the capability of the current beryllium nuclear data to calculate total neutron multiplication.

N. Determination of Selenium in Fish Personnel: Elsie Sorensen, Memphis State University A. H. Pradzynski, NETL Thomas L. Bauer, NETL Sponsored by: Nuclear Engineering Teaching Laboratory

Description:

Additional measurements and evaluation of selenium levels in fish to environmental contamination were performed. Part per million levels of fish hepatapancreas and muscle were observed and correlated with various other physical observations. Data from two separate lakes, one in Texas and one in North Carolina, were examined. A report to the State of Texas Attorney General was completed and several papers prepared.

0. Au and Cu Content of Athenian Coins Personnel: Tom Bauer, NETL Stanislaw Piorek, NETL Sponsored by: J. Kroll

Description:

Fifteen silver coins with owl insignias minted by Athens were examined for Au and Cu content. Correlation of the coins dates with previous studies was attempted by comparing ratios of the impurities. The coins were property of the American Numismatics Museum.

e 33 l

i I

• Vill. Publications From the Nuclear Engineering Teaching Laboratory *

l. K.L. Gilbert, " Neutron Flux Mapping of a Subcritical Reactor Core with l

a Polyethylene Reflector", Masters Thesis, Physics Department, The University j of Texas, 61 pp. , June 1961.

2. T.T. Doss, " Neutron Density Distribution in and Unreflected Subcritical Reactor Core", Masters Thesis, Physics Department, The University of Texas j 63 pp. , June 1961.

3. J.M. Norwood, "The Point Source Transport Solution for the Position and Velocity Dependent Neutron Distribution in a Spherical Body of Non-Multiplying Material", Masters Thesis, Physics Department, The University of Texas, 75 pp.

June, 1962.

, 4. R.W. Reed, "Effect of a Cadmium Control Rod on the Neutron Density in a Subcritical Reactor", Masters Thesis, Physics Department, The University of Texas, 85 pp., August 1962.

5. P. Berananda, " Neutron Flux Distribution of a Subcritical Reactor Core with a Graphite Reflector", Masters Thesis, Physics Department, The University of texas, 40 pp., January 1962.

i

6. T. A. Fredericks, " Thermal Neutron Flux Distribution Due to a Hane Wave Source in and Unreflected Reactor Assembly", Masters Thesis, Physics Department, The University of Texas,107 pp. , August 1963.

l 7. D.G. Martin, " Film Detector for a Neutron Spectrometer", Masters Thesis, Physics Department, The University of Texas, June 1963.

8. M.L. West II, " Flux Decay Rate in a Reflected Subcritical Reactor",

, Masters Thesis, Physics Department, The University of Texas, 55 pp., August 1963.

1 j 9. 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, 186 pp., January 1965.

! 10. B.E. Thompson, Sr., " Cryogenic Neutron Spectra Measurements Across a i Discontinuity in Temperature and Properties", Ph.D. Dissertation, The Univer-sity of Texas,149 pp., January 1965.

l

11. R.S. Kolflat, "An Experimental Approach to the Shdy of Nucleonic Funda-mentals", Masters Thesis, Mechanical Engineering Department, The University of Texas,190 pp. , May,1965.

12. D.G. Anderson, "A Technique for Recoil Fission Fragment Range Measurements",

Health Physics, Vol. 12, No. 4, 558, April 1966.

i

13. J.B. Whitworth, "A Cryogenic Irradiation Device for the TRIGA Mark I Nuclear Reactor", Masters Thesis, Mechanical Engineering Department, The Uni-l versity of Texas, 52 pp., January 1967.

34

14. D. A. Pullen, " A Rod Oscillator Design and Zero Power Transfer Function Measurement for a TRIGA Mark I Reactor," Masters Thesis, Mechanical Engineering (Nuclear Engineering), The University of Texas, January, 1967.

15. G.F. Malan, " Transfer Function Analysis of Temperature and Xenon Feedback in Coupled-Core Nuclear Reactor Systems", Masters Thesis, Mechanical Engineering Department, The University of Texas, 69 pp., August 1967.

16. M.G. Stevenson, " Investigations on the Macroscopic Nodal Approach to Space-dependent Nuclear Reactor Kinetics", Ph.D. Dissertation, The University of Texas, 203 pp. , August 1968.

17. F.H. Antunez-Castillo, " Gamma Radiation Dosimetry Techniques and Appli-cation to Mapping of The University of Texas Cobalt-60 Irradiation Facility",

Masters Thesis, Physics Department, The University of Texas, 60 pp., September 1968.

18. R. Valiente, " Neutron Radiography with the University of Texas TRIGA Nuclear Reactor", Masters Thesis, Physics (Nuclear Engineering), The University of Texas, August 1968.

19. P.J. Rodriguez and D.H. Nguyen, " Time Decay Constants in Pulsed Multi-plying Media", Trans. Amer. Nucl. Soc. 11:1, 289 (June 1968).

20. P.J. Rodriguez and D.H. Nguyen, "The Maximum Eigenvalue in the Pulsed-Neutron Initial-Value Problem", Trans. Amer. Nucl. Soc. 11:2, 578 (November 1968).

21. P.J. Rodriguez and D.H. Nguyen, " Contribution of the Continuum to the Neutron Transient Behavior in a Pulsed Multiplying Cylinder", Trans. Amer.

Nucl. Soc., 11:2, 582 (November 1968).

22. G.D. Bouchey and S.J. Gage, " Neutron Radiography with a Small Subtritical Reactor", Trans. Am. Nucl. Soc., 12, 462-463, 1969.

23. G.D. Atkinson, Jr., W. Coltharp, R. Cramatges, E. Oelkers, D.A. Roberts, K.R. Waid, S.H. Gage, and B.V. Koen, " Project Atlantis: A Design of the Nuclear Power Supply for an Undersea City", Proceedings of the_ Offshore Technology Conference, Dallas, Texas (1969).

24. J.A. Villalobos, "A Study of Gamma Radiation Dosimetry Techniques and Application to Radiation Field Mapping", Masters Thesis, Physics Department (Nuclear Engineering), The University of Texas, January 1969.

25. M. A. Zuniga, " Delayed Neutron Counting Technique for Uranium Determination",

Masters Thesis, Physics Department (Nuclear Engineering), The University of

~

Texas, January 1969.

26. V. Chanto, S.J. Gage, and D.F. Barker, " Chlorine and Bromine Concentrations in Some Haliburton-Bancroft Rocks and Minerals by Neutron Activation Analysis",

1969.

35

27. M. Gallardo, S.J. Gage, and D.F. Barker, " Trace Elements in Quartz by Nondestructive Neutron Activation Analysis", 1969.

. 28. G.D. Atkinson, Jr., " Investigation of the Dynamic Behavior of a Two-Region Subcritical Reactor", Masters Thesis, Mechanical Engineering (Nuclear Engineer-ing), The University of Texas, January 1969.

29. M. Gallardo, " Trace Elements in Six Quartz Samples by Nondestructive Neutron Activation Analysis Technique," Masters Thesis, Physics Department (Nuclear Engineering), The University of Texas, January 1969.

30. F. A. Rodriguez, S.J. Gage, and K.M. Ralls, " Nondestructive Neutron Activation Analysis for Trace Impurities in Niobium", Seventh Symposium on Nondestructive Evaluation of Components and Materials in Aerospace, Weapon Systems, and Nuclear Applications, San Antonio, Texas (1969).

31. S.J. Gage and M. Zuniga, " Uranium Trace Analysis by Pulsed Reactor Irra-diation", Radiation and Isotope Technology in Latin American Development, American Nuclear Society Topical Meeting, San Juan, Puerto Rico, May 4-6, 1969.

32. R.H. Richardson, " Migration, and Enzyme Polymorphisms in Natural Popula-tions of Drosophila", Jap. J. Gen. , (in press),1969.

33. R.H. Richardson, R.J. Wallace, Jr., S.J. Gage, G.D. Bouchey, and Margaret Denell, " Neutron Activation Techniques for Drosphila in Natural Populations",

Studies in Genetics, Marshall R. Wheeler Ed., The University of Texas Press,

. Austin, Texas 1969.

34. G.D. Bouchey and S.J. Gage, " Development and Potential Utilization of a Neutron Radiography Facility at The University of Texas NuclearReactor Laboratory",

Seventh Symposium on Nondestructive Evaluation of Components and Materials in Aerospace, Weapons Systems, and Nuclear Applications, San Antonio, Texas (1969).

35. G.D. Bouchey and S.J. Gage, " Utilization of the University of Texas TRIGA Reactor for Neutron Activation Analysis Service", ANS/CNA Transactions (11)

p. 287, 1968.

36. G.D. Bouchey and G. Gjerstad, " Chemical Studies of Aloe-Vera Juice --

II Inorganic Ingredients", Quarterly Journal of Crude Drug Research, Vol . 9_,

No. 4 (1969).

37. S.J. Gage, R.H. Richardson, and G.D. Bouchey, " Neutron Activation Tech-niques for Labelino of Insects with Stable Elements", Trans. Am. Nucl . Soc. ,

12,495-496,(1969).

38. F.G. Pasos, "Nondispersive X-Ray Fluorescence Analysis Using a Lithium-Drifted Germanium Detector", Masters Thesis, Physics Department, The University of Texas, 54 pp., January 1969.

36

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39. P.J. Rodriguez, " Time and Energy Dependent Neutron Distribution in a Pulsed Multiplying Medium", Ph.D. Dissertation, The University of Texas, 205 pp., January 1969.

40. G.D. Bouchey, B.V. Koen, C.S. Beightler, "The Optimal Allocation of Energy in Industrial and Agro-Industrial Complexes Using Dynamic Programing",

Nucl. Sci. and Engr., Vol. 41, 70-78 (1970).

41. G.F. Malan and B.V. Koen, "A Nonlinear Programing Approach to Optimal Control of Nuclear Reactors", Trans. Am. Nucl . Soc. , November 1970.

42. M.G. Stevenson and S.J. Gage, " Application of a Coupled Fission Mode Approach to Modular Reactor Vsinetics", Journal of Nucl . Energy, Vol . 24, pp.1-10. Pergamon Press 1970. Printed in Northern Ireland.

43. G.D. Bouchey and S.J. Gage, " Neutron Radiography at The University of Texas Nuclear Reactor Laboratory", I_sotopes and Radiation Technology 1, 294-296 (Spring 1970).

44. D.G. Jopling, "The Politics of Nuclear Reactor Siting", Masters Thesis, Mechanical Engineering, The University of Texas, December 1970.

45. A.H. Urdaneta, "A Programed Associative Analyzer", Masters Thesis, Mechanical Engineering (Nuclear Engineering), The University of Texas, December 1960.

~

46. G.D. Bouchey and S.J. Gage, " Detection and Location of Leaking TRIGA Reactor Fuel Elements", GA Publication T-ll7, Papers and Abstracts, TRIGA Reactor Owners' Seminar, February 19-20,1970 (Denver, Colorado) p. 43.

47. G.D. Bouchey and S.J. Gage, " Neutron Radiography with a Small Subcritical Assembly", International Journal of Nondestructive Testing, (1970).

48. G.D. Atkinson, Jr., J.B. Whitworth, and S.J. Gage, "NAAC0L--A Spectrum Analysis Routine for the Small Laboratory", 21st Mid-America Symposium on Spectroscopy, Chicago, Illinois (1970).

49. S.J. Gage, G.D. Atkinson, Jr., J.B. Whitworth, and A.H. Pradzynski,

" Computer-Aided Multielement Cama Ray Analysis with a Compton Suppressed Ge(Li) Radiation Source", Ninth National of the Society of Applied Spectros-copy, New Orleans, Louisiana, October 5-9, 1970.

50. K.R. Waid, " Solid State Radiation Detection Devices: Fabrication, Techniques and Application to Nuclear Engineering", Masters Thesis, Mechanical Engineering (Nuclear Engineering), The University of Texas, January 1970. .

51. V.H. Chanto, " Neutron Activation Analysis of Chlorine and Bromine in Some Haliburton-Bancroft Rocks and Minerals", Masters Thesis, Physics (Nuclear Engineering), The University of Texas, January 1970.

37

[

l i

- 52. J.J. Chromik and E.L. Draper, Jr., " Energy Integral Tests of Differential Fission Cross Section Data", Trans. Am. Nucl. Soc., Vol.13, No. 2, p. 755 j (1970).

o I

53. R.J. Gramatges-Figueras, " Neutron Waves in Cylindrical Geometries for a i Subcritical Reactor", Masters Thesis, Mechanical Engineering Department, The University of Texas, 98 pp., May 1970.

54. E. Oelkers, Jr., "A Learning Method for Identification of Nuclear Reactor i .

Point Dynamics", Masters Thesis, Mechanical Engineering Department, The Uni-versity of Texas, pp.165, August 1970.

4

55. 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,131 pp.

August 1970.

56. J.R. Deen, " Calculation of Resonance Integrals Using the Intermediate Resonance Approximation", Masters Thesis, Mechanical Engineering Department, 1 The University of Texas, 140 pp., January 1970.

57. C.T. Rombough, " Application of Queueing Theory to Closed-Loop Computer-Reactor Control Systems", Masters Thesis, Mechanical Engineering Department,

- The University of Texas, 78 pp. , December 1970.

58. A.H.U. Bohorquez, "A Programmed Associative Analyzer", Masters Thesis, Mechanical Engineering Department, The University of Texas, 98 pp. December

1970.

l 59. S.J. Gage and D.G. Joplino, The Nuplex Concept: Potential for the SINB Region, Southern Interstate Nuclear Board, 250 pp., March 22, 1971.

l

60. G.F. Malan and B.V. Koen. " Application of Nonlinear Programming to the Optimal Control of a Point Model Nuclear Reactor", Nucl. Sci. and Engr. ,

(1971).

i

61. G.D. Bouchey, B.V. Koen, and C.S. Beightler, " Optimization of Material Safeguards Sampling System", Trans. Am. Nucl . Soc. , Winter Meeting, (1971).

4

62. A.H. Pradzynski and S.J. Gage, " Nondestructive Identification of Material

by Nondispersive X-Ray Fluorescence Spectroscopy using Si(Li) Detectors and Radioisotopic Sources", Proc. Eighth Symposium on Nondestructive Evaluation in Aerospace, Weapons Systems, and Nuclear Applications, San Antonio, Texas (1971).

! 63. G.D. Atkinson, Jr. , and S.J. Gage," Uranium Assay by Delayed Gamma Ray l

Analysis Following Cf-252 Neutron Interrogation", Proc. Twelfth Annual Meeting

> Institute of Nuclear Materials Management, Plam Springs, Florida (July 1971).

l 38 i

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1 4

s

64. S.J. Gage, E. Linn Draper, Jr., G.D. Bouchey, and R.R. Day, " Design and Construction of a Versatile Cf-252 Source Shield and Experimental Facility",

Neutron Sources and Applicatior.s, CONF-710402, Vol . 2, Proc. of ANS Topical Meeting, _ Augusta, Georgia , Apr1T 19-21,1971.

65. D.G. Jopling and S.J. Gage, "Public Resistance to Nuclear Reactor Siting",

Nuclear News, 14:3, 32-35 (March 1971).

4 66. J.B. Whitworth, G.D. Atkinson, and S.J. Gage, "Some Recent Applications of Nuclear Analysis Techniques to Typical Forensic Evidence" 23rd Annual Pro-gram American Academy for Forensic Sciences, Phoenix, Arizona (February 25, 1971).

67. G.D. Bouchey, E. Linn Draper, Jr. , B.V. Koen, and C.S. Beightler,

" Multiple Foil Activation Spectrum Determination Using a Numerical Direct Search Technique", Trans. Am. Nucl. Soc., Vol. 14_:2, pp. 667-668, (October

]~

1971).

68. G.D. Bouchey, B.V. Koen, and C.S. Beightler, "The Optimization of Nuclear Systems by Geometric Programming, Nucl. Sci, and Engr. 44, 267-272 (1971).

69. G.D. Bouchey, B.V. Koen, and C.S. Beightler, " Optimization of Nuclear Materials Safeguards Sampling Systems by Dynamic Programming", Nuclear Technology 12, 18-25 (1971).

70. S.J. Gage, G.D. Atkinson, Jr. and G.D. Bouchey, " Cyclic Neutron Activation i

Analysis with a Cf-252 Neutron Source", Trans. Am. Nucl. Soc., (October 4

1971).

l

71. E. Linn Draper, Jr., " Integral Reaction Rate Determination Part I:

Tailored Reactor Spectrum Preparation and Measurement", Nuclear Science and Engineering, 46,22,(1971).

! 72. E. Linn Draper, Jr., " Integral Reaction Rate Determinations Part II:

Fission Rate Measurements", Nuclear Science and Engineering, 46,,31,(1971).

73. G.D. Bouchey and S.J. Gage, " Detection and Location of Leaking TRIGA

' Reactor Fuel Elements", Nuclear Technology, 10, 211-214 (1971).

74. G.D. Bouchey and S.J. Gage, " Neutron Radiography with a Small Subcritical Reactor", Int. J. of Nondestructive Testing, 2,335-353,(1971).

75. G.D. Bouchey and S.J. Gage, "The Economics of Subcritical Radiography",

• Trans. Am. Nucl. Soc., 14, 123 (1971).

l

76. G.D. Bouchey, E. Linn Draper, Jr. , and S.J. Gage, " Neutron Radiography with Cf-252: The Effect of Tailoring Neutron Energy Spectra on Photogrpahic 1 Images", Neutron Sources and Applications, CONF-210402, Vol. 3, Proc. ANS j Topical Meeting, Augusta, Georgia, April 19-21, 1971.

i-39 l

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77. G.D. Atkinson, Jr., J.B. Whitworth, and S.J. Gage, " Computer-Assisted Analysis of Gamma-Ray Spectra", Computer Physics Communications,22 40-46 (1971).

78. S.J. Gage, E. Linn Draper, Jr., and G.D. Bouchey, "Recent Developments in Radioisotopic Source Neutron Radiography", Proc. Eighth Symposium on Non-destructive Evaluation in Aerospace, Weapon Systems, and Nuclear Applica-tions, San Antonio, Texas (1971).

79. G.D. Atkinson, Jr., "Ncadestructive Uranium Assay by Delayed Gamma Ray Analysis Following Californium-252 Neutron Interrogation", Ph.D. Dissertation, l The University of Texas,183 pp. , August 1971.

i

80. G.D. Bouchey, "The Optimization of Nuclear Systems", Ph.D. Dissertation, The University of Texas, 231 pp., August 1971.

I' 81. J.B. Whitworth, "The Development and Application of a Systematic Approach to Elemental Analysis in Forensic Investigations", Ph.D. Dissertation, The University of Texas, 223 pp., December 1971.

I

82. J.J. Chromik, " Experimental Determination of the Neutron Flux in the University of Texas Californium-252 Irradiation Facility", Masters Thesis, j Mechanical Engineering Department, The University of Texas, 85 pp. December 1971.

83. E. Linn Draper, Jr., Mary Elizabeth Foster and G.D. Bouchey, "X-Ray Fluroescence Analysis and Neutron Activation Analysis in an Analytical Chemistry Laboratory", presented at the Combined Meeting of the Texas Association for Radiation Research and South Central Photobiology Group, Houston, Texas, November 5-6, 1971.

84. E. Linn Draper, Jr. and G.D. Bouchey, " Utilization of a Portable Cali-fornium-252 Source for Neutron Activation Analysis and Neutron Radiography",

Presented at the Combined Meeting of the Texas Association for Radiation Research and South Central Photobiology Group, Houston, Texas, November 5-6, 1971.

85. E. Linn Draper, Jr. and J.J. Chromik, " Production and Measurement of a Reference Spectrum in a Versatile Experimental Facility", Trans. Am. Nucl.

i Soc. , Volume 15_:1, p.157,1972.

I 86. E. Linn Draper, Jr. and Andrzej H. Pradzynski, " Identification of Alloys l

by Energy Dispersive X-Ray Spectroscopy", Ninth Symposium on Nondestructive 4

Evaluation (1972).

87. M.B. Owen, " Fuel Management Using Dynamic Programming", Masters Thesis l ,

Mechanical Engineering Department, The University of Texas, 59 pp. May 1972.

88. C.E. Brauer, " Thermal Neutron Radiography with a Lithium-Lead Collimator-l Filter", Masters Thesis, Mechanical Engineering Department, The University of Texas, 64 pp., May 1972.

40

,-------w,, -- -

w.,. , - - - , - , - , , , ,-+,,..,nw-en-._~.,,,_--..---r. ---,----,.n -- _ . . _ , - - , - . - , _ , - -

J i

. 89. J.L. Macdonald, " Heuristic Learning Control for Nuclear Reactors", Masters 1 Thesis, Mechanical Engineering Department, The University of Texas, 131 pp.

4 August 1972.

90. J. Frein, " Theoretical and Experimental Evaluation of Nuclear Data and Calculation 'echniques for Fusion Reactor Blanket Design", Ph.D. Dissertaticn, lhe University of Texas, 210 pp. , December 1972.

'l. S.G. Barbee, "Neutronic Calculations in a Simulated Fusion Reactor Blanket", Masters Thesis, Mechanical Engineering Department, The University of Texas, 259 pp. , November 1972.

92. D.G. Anderson, " Fission Product Mass-Yield Measurements from Intermediate Energy Neutron Fission of Plutonium-239 and Plutonium-241", Ph.D. Dissertation, The University of Texas,125 pp. , December 1972.

93. D.M. Williams, " Identification of Thermal Feedback Parameters for a TRIGA Mark I Reactor", Masters Thesis, Electrical Engineering Department.

The University of Texas, 53 pp. , December 1972.

94. G.D. Atkinson, Jr. E. Linn Draper, Jr., and G.D. Bouchey, "Subcritical TRIGA Reactivity Measurements Using the Source Jerk Technique", TRIGA Owner's 4

Conference II, College Station, Texas (1972).

95. G.D. Atkinson, Jr. , and E. Linn Draper, Jr., " Transient Rod Failure in a Pulsing TRIGA Mark I Reactor", TRIGA Owner's Conference II, College Station, Texas (1972).

96. G.D. Atkinson, Jr. , "A Safeguards Minicourse",18th Annual Meeting of the American Nuclear Society, Las Vegas, Nevada (1972).

I

57. G.D. Atkinson, Jr., E. Linn Draper, Jr., G.D. Bouchey, and S.J. Gage,

" Radioisotopic Source Amplification Using a Heterogeneous Subcritical Assembly",

Proc.18th Annual Meeting of the American Nuclear Society, Las Vegas, Nevada (1972).

i

98. E. Linn Draper, Jr., and G.D. Atkinson, Jr. , " Transient Rod Failure in a l Fulsing TRIGA Mark I Reactor", published in proceedings of 2nd TRIGA Owner's Conference, February 1972.

99. E. Linn Drapgy, Jr. , John W. Davidson, S.J. Gage, G.D. Bouchey, "A System for Reduction of A Release from a Research Reactor Facility", Trans. Am.

Nucl . Soc. , Vol .15:1, p. 4-5, (1972).

i 100. E. Linn Draper, Jr., et.al., " Standard for the Development of Technical Specifications for Research Reactors", Trans. Am. Nucl. Soc., (1972).

1 =

101. E. Linn Draper, Jr. , G.D. Atkinson, Jr. , and B.B. Tomlin, "A Radiography and Capture Gamma Ray Facility for Californium-252" Proceedings of the American Nuclear Society " Applications of Californium-252" National Topical Meeting, September 11-13, 1972.

41

l l

r l, 102. E. Linn Draper, Jr., G.D. Bouchey, G.D. Atkinson, Jr., and S.J. Gage, i "A Versatile Subcritical Assembly for Undergraduate Nuclear Engineering Instruction", Proceedings of the American Nuclear Society " Applications of i . Californium-252" National Topical Meeting, September 11-13, 1972.

i 103. E. Linn Draper, Jr., and S.J. Gage, "The Fusion-Fission Breeder: Its Potential in a Fuel Starved Thermal Reactor Economy", 93rd Annual Meeting of the ASME, New York, New York (1972).

! 104. E. Linn Draper, Jr., " Technological Innovation and Assessment: A Novel Course for Nuclear Engineering", Winter Meeting of the American Nuclear Society, November 12-16, 1972.

I 105. D.T. Hall, E. Linn Draper, Jr. , and P.S. Schmidt, " Management of the Transition to Nuclear Power Generation", Technical Report ESL-3, Energy Systems Laboratories, College of Engineering, The University of Texas at Austin,

.f December 1972.

106. P.S. Schmidt and G.G. Park, " Heat Dissipation in a Power ylant Cooling Bay", ASME, Paper No. 72-WA/HT-61, November 1972.

107. P.S. Schmidt and G.P. D' Arch, " Entry Region Effects on Flow and Pressure Drop of Li;hium in Fusion Reactor Blankets", Proceedings of the Texas Symposium on Technology of Controlled Thermonuclear Fusion Experiments and Engineering Aspects of Fusion Reactors, Austin, Texas (November 20-22,1972).

, . 108. E. Linn Draper, Jr., Charles Brauer, " Lithium-Lead Collimator Fabrication for Radioisotopic Source Neutron Radiography," Trans. Am. Nucl . Soc. , Vol .15:1,

p. 142-143, (1972).

109. E. Linn Draper, Jr. , James B. Freim, " Theoretical and Experimental Eval-uation of Nuclear Data and Calculation Techniques for Fusion Reactor Blanket Design", Texas Symposium on the Technology of Controlled Thermonuclear Fusion i Experiments and the Engineering Aspects of Fusion Reactors, November 20-22, i 1972.

110. E. Linn Draper, Jr., " Status of CTR Related Integral Experiments" pre-sented at the conference on " Nuclear Data and Neutronics of CTR Blankets" held in Seattle, Washington, September 19-21, 1972.

111. E. Linn Draper, Jr., " Fusion Reactor Engineering in the Nuclear Engineering Curriculum at The University of Texas at Austin", Trans. Am. Nucl. Soc.

(1972).

112. E. Linn Draper, Jr., S.J. Gage, "The Fusion-Fission Breeder: Its Potential l'

in a Fuel Starved Thennal Reactor Economy", presented at the Texas Symposium

. on the Technology of Controlled Thermonuclear Fusion Experiments and the

- Engineering Aspects of Fusion Reactors, November 20-22, 1972.

113. James B. Freim, E. Linn Draper, Jr., " Experimental Determination of the Fusion Spectrum in Graphite", Trans. Am. Nuci. Soc., (1972). .

42

,m--wwww.,7v...., ,.r..s,.,,,..,.w---.- ,7 .%- ,,,...w,m., - --._,~,_.~,...-.,-,,_,.,----.n._--

. -. , .,_v.._ g.-,--.--.~.---ww,-...

l 1

4 114. G.D. Atkinson, Jr. , S.J. Gage, G.D. Bouchey, " Cyclic Activation with a Californium-252 Soutce", Nuclear Technology (1972).

115. G.D. Atkinson, Jr. , "What You Always Wanted to Know About Californium i Source Facilities", invited Ppaer, National Topical Meeting on the Applications of Californium-252, Austin, Texas (1972).

i 116. T.L. Bauer, G.D. Atkinson, Jr., " Discrimination Between Plutonium and Uranium by Gamma Ray Analysis Following Cf-252 Interrogation", National Topical

' Meeting on the Applications of Californium-252, Austin, Texas (1972).

117. E. Linn Draper, Jr. , Editor, Proceedings of Texas Symposium on the Tech-nology of Controlled Thermonuclear Fusion Experiments and the Engineering Aspects of Fusion Reactors, published by USAEC.

j 118. E. Linn Draper, Jr., Editor, P_roceedings of the Implications of Nuclear Power in Texas, published by the Texas Atomic Energy Research Foundation.

[

119. E. Linn Draper, Jr., J.R. Deen, J.J. Chromik, " Measurement of the Integral Fission Cross Section of Th-232 in a Cf-252 Fission Neutron Spectrum,"

Trans. Am. Nucl. So_c_. (1973).

120. D.G. Anderson, E. Linn Draper, Jr., " Fission Product Mass-Yield Measure-ments From Intermediate Energy Neutron Fission of Plutonium-239 and Plutonium-j 241", Trans. Am. Nucl. Soc. 1973.

121. E. Linn Draper, Jr. , and James B. Freir., "Fxperimental Determination of

, the Fusion Spectrum in Graphite", Trans. Am. Nuci. Soc., ]6, 9, (1973).

122. E. Linn Draper, Jr., " Fusion Reactor Engineering in the Nuclear Engineer-ing Curriculum at The University of Texas at Austin", Trans. Am. Nucl. Soc.,

! 16,, 16 (1973).

i 123. E. Linn Draper, Jr. , Theodore A. Parish, and Brian J. McArdle, "A Neu-tronic-Photonic Comparison of Vanadium and Niobium Containing Fusion Reactor Blankets", Trans. Am. Nucl . Soc. , (November 1973).

j 124. John H. Vanston, Jr., "Use of Partitive Analytical Forecasting (PAF)

Techniques for Fusion Development Analysis", Trans. Am. Nucl. Soc., (November

1973).

I 125. Theodore A. Parish and E. Linn Draper, Jr. , "Neutronic and Photonic Analyses

of Fusion Reactor Blankets Containing Thorium," Fifth Symposium on Engineering

! - Problems of Fusion Research, Princeton, New Jersey, November 5, 1973.

I 126. C.E. Locke and D.R. Paul . "Graf t Copolymer Modification of Poly-ethylene-Polystyrene Blends. I. Graf t Preparation and Characterization".

j Journal of Applied Polymer Science, Vol. ]7_, 7 pp. 2597-2617 (1973.) ,

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l 127. C.E. Locke and D.R. Paul, " Graft Copolymer Modification of Poly-ethylene-Polystyrene Blends. II. Properties of Modified Blends", Journal of Applied Polymer Science, Vol. 17, pp. 2791-3800 (1973).

128. J.R. Deen, " Measurement of Fission Product Yields from Thorium-232 in a Californium-252 Fission Neutron Spectrum", Ph.D. Dissertation, The Uni-versity of Texas at Austin, 141 pp., (May 1973).

129. L.D. Hansborough, "Overall Tritium Considerations for Controlled Ther-monuclear Reactors", Masters Thesis, The University of Texas at Austin, 154 pp. (May 1973).

130. "M.E. Senglaub, "Ci oss Sc: tion Studies Rased on the Statistical Model",

Masters Thesis, The University of Texas at Austir,109 pp. , (August 1973).

131. E. Linn Draper, Jr. M.J. Voltin, Jr., J.L Macdonald, C.T. Rombough, L.D. Hansborough, S.G. Barbee, and J.H. Vanston, Jr. , "A University's In-volvement in Municipal Decision-Making on Nuclear Power", Trans. Am. Nucl.

Soc.,(1973).

132. E. Linn Draper, Jr. , J.L. Macdonald, and M.J. Voltin, Jr. , " Nuclear vs.

Coai: An Economic Comparison of Power Plant Economics in Texas", Trans. Am.

Naci. Soc., (1973).

133. R.E. Henry, " Forensic Applications of Neutron Activation Analysis",

presented at the Combined Meeting of the Texas Association for Radiation Research and South Central Photobiology Group, San Marcos, Texas, November 9-10, 1973.

134. 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 Sout h Central Pho*obiology Group, San Marcos, Texas, November 9-10, 1973.

135. S.P. Nichols, " Experimental Determination of Neutron Fermi Age from Californium-252 Fission Spectrum to Cadmium Colered Indium Resonance in a Graphite Medium" Masters Thesis, The Univers- ty of Texas at Austin,101 pp.,

January 1974.

136. T.A. Parish, "Neutornic and Photonic Analyses of Simulated Fusion Reactor Blankets Containing Thorium and Natural Uranium", Ph.D. Dissertation, The University of Texas at Austin, 329 pp. January 1974.

137. J.H. Vanston, Jr., "Use of the Partitive Analytical Forecasting (PAF)

Technique for Analysis of the Effects of Various Funding and Administrative Strategies on Nuclear Fusion Power -lant Development", Ph.D. Dissertation, The University of Texas at Austin, 459 pp. , January 1974.

138. E.M. B. Sorensen, " Thermal Effects on the Biological Magnification of Arsenic in Green Sunfish, Lepo!nis Cyanellus", Ph.D. Dissertation, The Univer-sity of Texas at Austin, 233 pp , May 1974.

44

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. 139. E. Linn Draper, Jr., and J.R. Deen, " Measurement of Fission Product Yields from Thorium-232 in a Californium-252 Fission Neutron Spectrum", Trans. Am.

Nucl. Soc., 17_, 531 (1973).

140. E. Linn Draper, Jr., M. Etzion, S.P. Nichols and W.G. Davey, " Neutron Fermi Age in Graphite from Fission and Fusion Sources to Indium Resonance",

• CONF-740402, USAEC, (April 1974).

141. E. Linn Draper, Jr., and T.A. Parish, "Neutronic and Photonic Analyses of Fusion Reactor Blankets Containing Natural Uranium", CONF-740402, USAEC, (Apri1 1974).

142. G.D. Atkinson, Jr. , B.D. Adams, and S.J. Gage, "A Programmable and Automated System for Gamma and X-Ray Analysis", PROC. IEEE 1973 NUCLEAR SCIENCE SYMPOSIUM, San Francisco, California (1973).

143. G.D. Atkinson, Jr. , and R.E. Henry, " Neutron Activation Analysis:

Environmental and Biological Applications", Sixth Annual Meeting of the Texas Association for Radiation Research, San Marcos, Texas (1973). .

i 144. M. Etzion, R.G. Spangler, E. Linn Draper, Jr., " Multiple Foil Activation Measurement of the Californium-252 Fission-Neutron Spectrum, Trans. Am. Nucl.

Soc.,(October 1974).

. 145. A. H. Pradzynski, " Determination of Selenium in Water on the ppb Level" presented before the Texas Association for Radiation Research, Dallas, Texas, (November 22,1974).

146. Thomas L. Bauer, " Discrimination of Uranium-235 and Plutonium-239 by Cyclic Activation and Delayed Gamma Ray Analysis Using Californium-252 as a Neutron Interrogation Source", Masters Thesis, Mechanical Engineering De-partment, The University of Texas at Austin,178 pp. (August 1974).

i 147. Olan D. Thompson, " Optimization of Shipping Containers for Radioisotopic Neutron Sources", Masters Thesis, Mechanical Engineering Department, The Uni-versity of Texas at Austin, 30 pp. , (August 1974).

l 148. J.R. Deen, E. Linn Draper, Jr., " Measurement of the Fission Product t Yields and the Energy Integral Fission Cross Section of Thorium-232 in a Cali-

! fornium-252 Fission-Neutron Spectrum", Nuclear Technology, 25, 416 (1975).

l l 149. E. Linn Draper, Jr. , T. A. Parish, M. Etzion, " Utilization of a Small

, Accelerator for Fusion Reactor Blanket Design", Proceedings of the Third Small

. Accelerator Conference, USAEC, CONF-741021 (1974).

l 150. R.G. Spangler, E. Linn Draper, Jr., T.A. Parish, "14 MeV Cross Section

- Measurements of Threshold Reactions for Seven Metals", Trans. Am. Nucl. Soc.,

22, 818 (November 1975).

?

45 1

i .. . . - - - - --.- - - - . - - . - _ - -- - . - . _ . - . - ,_

. 151. W.R. Smith, Jr., E. Linn Draper, Jr., " Measured and Calculated Fast Neutron Spectra in a Graphite Medium" Trans. Am. Nucl . Soc. , 2_2, 2 800 i

(November 1975).

152. J.W. Davidson, E. Linn Draper, Jr., " Costs for Partitioning Strategies l'

Involved in High-Level Nuclear Waste Management", Trans. Am. Nucl . Soc. , 22, ~

348 (November 1975).

153. M.J. Voltin, Jr., E. Linn Draper, Jr. , " Sensitivity of Total Fuel Cycle i Cost to Variations in Enrichment Tails Assay Strategies", Trans. Am. Nucl. Soc.,

22, 322 (November 1975).

. 154. T. A. Parish, J.W. Davidson, E. Linn Draper, Jr. , " Transmutation of i Fission Products in Fusion Reactor Blankets", Trans. Am. Nucl. Soc., ~22, j (November 1975).

155. T. A. Parish, J.W. Davidson, E. Linn Draper, Jr., "The Effects of the D-T Fusion Neutron Energy Spectrum on High Energy Reaction Rates", submitted to the Sixth Symposium on Engineering Problems of Fusion Research, San Diego,

' California (November 18-21,1975).

156. A.H. Pradzynski, R.E. Henry, J.L.S. Stewart, " Determination of Selenium in Water on the ppb Level by Coprecipitation and Energy Dispersive X-Ray

. Spectrometry", Radiochem. Radioanal. Letters, 21(5) 277-285 (1975).

157. B.E. Bulla, E. Linn Draper, Jr. , R.E. Henry, M.J. 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).

J 158. A.H. Pradzynski, R.E. Henry, J.L.S. Stewart " Determination of Transition Metals by Radioisotope-Excited Energy Dispersive X-Ray Spectrometry",

Trans. Am. Nucl . Soc. , 21, No. 3 34-35 (1975).

! 159. A.H. Pradzynski, R.E. Henry, J.L.S. Stewart, " Nondestructive Determination l

of Toxic Elements in Toys", Proc. of 10th Symposium on Nondestructive Elements, San Antonio, Texas, 257-265 (April 23-25, 1975).

l I

160. 9.E. Henry, " Determination of ppb Levels of Selected Elements in Natural Water Using Radiosiotope-Excited Energy Dispersive X-Ray Fluorescence Analysis",

presented at the Eighth Annual Meeting of the Texas Association for Radiation Research, Austin, Texas (October 31 -- November 1, 1975).

l t

- 161. S.P. Nichols, " Application of the Partitive Analytical Forecasting (PAF)

Technique to the United States Controlled Thermonuclear Research Effort,"

l Ph.D. Dissertation, The University of Texas at Austin (December 1975).

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l 162. C.T. Rombough, "The Total Energy Investment in Nuclear Power Plants",

Ph.D. Dissertation, The University of Texas at Austin, (January 1975).

46 1

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- 163. J.L. Macdonald, " Investigation of Pattern Recognition Techniquei for the Identification of Splitting Surfaces in Monte Carlo Particle Transport Cal-culations", Ph.D. Dissertation, The University of Texas at Austin (August 1975).

I 164. J.W. Davidson, "A Cost-Benefit Analysis for Pdrtitioning Strategies In-l volved in High-Level Nuclear Waste Management", Masters Thesis, The University

' of Texas at Austin, (May 1975).

165. T. A. Parish, J. W. Davidson, and E. Linn Draper, Jr. , "The Minimization of the Hazard Resulting from Transmutation of Fission Products," Transactions of the American Nuclear Society, 23_, 59, June 1976.

166. T. A. Parish, " Fusion-Fission Hybrid Studies at The University of Texas,"

U.S.-U.S.S.R. Symposium on Fusion-Fission Reactors, Lawrence Livermore Labora-tory, July 1976.

167. T. A. Parish, J. W. Davidson and E. Linn Draper, Jr., "Neutronic Perfor-mance of Graphite Fusion Reactor Blankets Containing Sr90 and 1 129," Second ANS Topical Meeting on the Technology of Controlled Thermonuclear Fusion, Richland, Washington, September 1976.

168. T. A. Parish, J. W. Davidson and J. B. Cornwell, "The Effectiveness of a Sr90 Fusion Reactor Transmutation Waste Management Program," Transactions

- of the American Nuclear Society, 24,, November 1976.

169. A. H. Pradzynski and J. R. Rhodes, " Development of Synthetic Standard Samples fa Trace Analysis of Air Particulates," ASTM Special Technical Publication No. 598, 1976, pp. 320-336.

170. A. H. Pradzynski, 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, 3_2, 2 1976, p. 219-28.

171. A. H. Pradzynski, R. E. Henry and E. L. Draper, Jr., " Determination of PPB Concentrations of Uranium, Thorium and Molybdenum in Water using APDC Preconcentration and Radioisotope Excited X-Ray Emission Spectrometry,"

Proceedings of ERDA Symposium on X- and Gamma-Ray Sources and Applications, Ann Arbor, Michigan, May 19-21,1976, pp.175-177.

i

172. 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 Am. Nuclear Society, 24,

- 1976, p.119.

173. R. R. Gay, G. F. Brockett and R. T. Johnson, "Two-Phase Flow Measurement l

Techniques for Nuclear Safety Research," Two-Phase Flow and Heat Transfer Symposium-Workshop, Miami Beach, Florida (1976).

174. C. W. Savery and R. R. Gay, "Effect of Entrained Droplet Phase Upon Predicted Compartmental Pressures in Nuclear Containments," Two-Phase Flow and Heat Transfer Symposium-Workshop, Miami Beach, Florida (1976).

47 '

1 175. Rodney R. Gay, " Reactor Hydrodynamics During the Reflood Phase of a loss-

• of-Coolant Accident," Nuclear Technology, Vol . 36, No. 2, Dec.1977, pp. 229-237.

176. D. E. Klein, S. R. Bull, and J. B. Miles, " Flow Visualization Around GCFR i

Fuel Rod Roughness Elements," Trans. Am. Nuclear Soc., 28, June, 1978.

177. D. E. Klein, S. R. Bull, and J. B. Miles, " Pressure Drop for GCFR Fuel Rod Roughness Elements," Trans. Am. Nuclear Soc., 30, November 1978.

178. E. M. B. Sorensen, R. E. Henry and R. Ramirez-Mitchell, " Time Dependent Localization of Arsenic in Subcellular Hepatocyte Fractions," J. of Pathology and Toxicology, Vol. 2, No. 4, 1979, pp. 1161-1171.

179. E. M. B. Sorensen, R. E. Henry, and R. Ramirez-Mitchell, " Arsenic Accumula-l tion, Tissue Distribution, Cytotoxity in Teleosts following Indirect Aqueous 21, 1979, Exposure," Bulletin of Environmental Contamination and Toxicology, Vol.

pp. 162-169.

180. J. W. Davidson and T. A. Parish, " Fission Product Toxicity Reduction via l Transmutation Using D-T Fusion Neutrons," Eight Symposium on Engineering Problems

)

of Fusion Research, San Francisco, California, November 1979.

181. J. W. Davidson and T. A. Parish, "An Evaluation of the Requirements and Performance of a Transmutation Waste Management System, Trans. Am. Nuclear Soc.,

33, November 1979.

182. S. A. Hodge, J. P. Sanders, and D. E. Klein, " Determination of Friction Factors and Heat Transfer Coefficients for Flow Past Artifically Roughened Surfaces, Oak Ridge National Laboratory Report, ORNL-5599, November 1979.

183. D. E. Klein, " Nuclear Problems and Prospects," National Energy Policy Issues, Council on Energy Resources, The University of Texas at Austin, May 1979.

l 184 D. E. Klein, H. H. Woodson, and J. W. Davidson, " Commercial Nuclear Power Generation," Council on Energy Resources, The University of Texas at Austin, June 1979.

j 185. E. M. B. Sorensen, R. R. Mitchell, A. Pradzynski, T. Bauer and L. Graham, "Morphometric Analyses of Arsenic-Induced Histopathological Changes in Parenchymal Hepatocytes," Tennessee Academy of Science Annual Meeting, Nashville, TN, November 16-i7, 1979.

186. A. H. Pradzynski, " Determination of V and Ba in Marine Sediments and Biota," Internal Report, Nuclear Engineering Teaching Laboratory, The University

,l-of Texas at Austin, Department of Mechanical Engineering (1979).

i

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187. N. E. Hertel, B. W. Wehring, and J. J. Dorning, " Integral Test of ENDF/B-IV High-Energy Neutron Cross Section Data for Tungsten," Trans. Am.

Nucl. Soc. 32, 631 (1979).

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i 188. R. H. Johnson, K. R. Koch, B. W. Wehring, and N. E. Hertel, "TDL Measure-ments in an Iron Sphere Containing a DT Source," Trans. Am. Nucl. Soc. 32, 632(1979).

189. B. W. Wehring, J. J. Dorning, N. E. Hertel, D.T. Ingersoll, R. H. Johnson,

" Benchmark Shielding Problems Obtained from Integral Tests of Neutron Cross Sections," Trans. Am. Nucl. Soc. 33, 666 (1979).

190. N. E. Hertel , R. H. Johnson, J. J. Dorning, and B. W. Wehring, " Measure-ments and Analyses of Neutron Transport Through Iron," Proc. Conf. Nuclear Cross Sections and Technology, Knoxville, TN, Oct. 22-26, 1979, NBS Special Publication #594, pp. 568-571.

i i 191. N. E. Hertel, B. W. Wehring, " Absolute Monitoring of DD and DT Nuetron 4

Fluences Using the Associated-Particle Technique," Nucl. Instr. Meth. 172, 501(1980).

l 192. S. A. Hodgc, J. P. Sanders, and D. E. Klein, " Slope and Intercept of the Dimensionless Velocity Profiles for Artificially Roughened Surfaces, Int. J. Heat Mass Transfer, Vol . 23, February 1980, pp.135-149.

193. N. E. Hertel, J. B. Smathers , and R.G. Graves, " Gamma-Ray Spectra

! Measured in a Tissue-Equivalent Medium Irradiated with Neutron Radiotherapy j Sources ," Trans. !hn. Nucl . Soc. 35, 457 (1980).

194. N. E. Hertel, W. E. Murphie, and R. J. Calhoun, " Measurements of Neutron and Gamma-Ray Spectra in a Phantom Irradiated with 14-MeV Neutrons,"

presented at the Health Physics Society Annual Meeting, Louisville, KY, June 21-26, 1981.

195. D. E. Klein, S. R. Bull and J. B. Miles, " Pressure Drop Measurements i and Flow Visualization Surrounding Roughness Elements," Journal of Energy, Vol . 4, No. 3, May-June 1980, p.112-119.

196. D. E. Klein, "ANS Student Involvement in Public Information-The University of Texas at Austin," Trans. Am. Nuclear Soc., 34, June 1980 (invited).

197. R. B. Pope, H. R. Yoshimura, J. E. Hamann, and D. E. Klein, "An Assessment

of Accident Thermal Testing and Analysis Procedures for Radioactive Materials Shipping Package," ASME 80-HT-38, ' April 1980.

l 198. J. E. Hamann, D. E. Klein, R. B. Pope, and H. R. Yoshimura, "Modelling

! of Pool Fire Environments Using Experimental Results of a Two-Hour Test of a l Railcar/ Cask System, " Paper #147, PATRAM-80, West Berlin, FRG. , Nov.1980.

l t 199. M. A. Ross and D. E. Klein " Synthetic Fuel Production Utilizing Texas l, Lignite and a VHTR for Process Heat," Trans. Am. Nuclear Soc. , 35, Nov.1980.

i 200. J.W. Davidson and D. E. Klein (co-editors), Proceedings of the International

, , Conference on Nuclear Waste Transmutation, University of Texas Press, March 1981.

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201. M. A. Ross and D. E. Klein, " Synthetic Fuel Production Using Texas Lignite and a VHTR for Process Heat," Number 3, March 1982, Nuclear Technology, Vol. 56.

202. T. L. Sanders and D. E. Klein, "A Modified Numercial 5cheme for GCFR Flow Transient Analysis," Trans. Am. Nuclear Soc., 39, November 1981.

203. M. A. Ross and D. E. Klein, " Synthetic Fuel Production Using Texas Lignite and A Very High Temperature Gas Cooled Reactor for Process Heat and Electrical Power Generation," Center for Energy Studies, The University of Texas at Austin, Research Report No. 13, May 1981.

! 204. M. M. Razzaque, J. R. Howell and D. E. Klein, " Finite Element Solution of Heat Transfer for Gas Flow Through a Tube," AIAA Journal, Vol. 20, No. 7,

.lulv 1982.

205. S. Yang, J. R. Howell and D.E. Klein, " Radiative Heat Transfer Through a Randomlv Packed Bed of Spheres by the Monte Carlo Method," AIAA/ASME 3rd Joint Thermophysics, Fluids, Plasma & Heat Transfer Conference, ASME 82-HT-5, St. Louis, Missouri, June 1982.

206. D.E. Klein and J. Andersen et al., " Peer Review of the Preliminary Design and Program Interfaces for the Transuranic Waste Package Transporter (TRUPACT)," Sandia Report, SAND 81-2405, June 1982.

207. T. L. Sanders and D. E. Klein, " Transient Thermal-Hydraulic Analysis Using a Modified Version of COBRA IV," 7th International Heat Transfer Conference, Munich, Germany 82-IHTC-104, September 1982.

208. S. Yang, J. R. Howell and D. E. Klein, " Monte Carlo Simulation of Thermal Conduction Through a Randomly Packed Bed of Spheres," 7th Interna-tional Heat Transfer Conference, Munich, Germany, 82-IHTC-91, September 1982.

, 209. T. L. Sanders and D. E. Klein, " Comparison Analysis of Severe Flow Blockages for Computational Efficiency Using COBRA," Proceedings from Gas-Cooled Reactors Today Conference, British Nuclear Energy Society, London, England, September 1982.

210. M. M. Razzaque, J. R. Howell and D. E. Klein, " Finite Element Solution i of Radiative Heat Transfer in a Two-Dimensional Rectangular Enclosure with

Gray Participating Media," 82-WA/HT-51, ASME Annual Meeting, Phoenix, Arizona, i November 1982.

211. J. B. Smathers, N. E. Hertel, R. G. Graves, "In Phantom Photon Spectra

! Measurements for High-Energy Neutroa Therapy Sources," Proceedings: Fourth l Symposium on Neutron Dosimetry: Beam Dosimetry,1-5 June 1981, Neuberberg/Munchen, Federal Republic of Germany, EUR 7448en (1981).

,, 212. N.E. Hertel, B. W. Wehring and J. J. Dorning, " Measurements and Analyses

of High-Energy Neutron Transport Through Tungsten," (accepted for publication j subject to revision in Nuclear Science and Engineering, November 1981).

50

._ ___ _ _ . _ _ . _ . _ _ _ _ , _ _ _ ~,, _ _ _ . . _ . . . . _ _ _ _ -

213. Y. Kunimoto, J. W. Davidson, and N. E. Hertel, "A Core Inventory Model for Fuel Trajectory Analysis in Fusion-Fission Symbiotic Systems," Trans. Am.

Nucl. Soc., 41, 1978, June 1982.

214. N. E. Hertel and W. E. Murphie, "The Use of Neutron and Gamma-Ray NE-213 i Spectral Measurements and Calculations to Obtain Dosimetric Information for

. DT Neutrons," Medical Physics 10,66,(1983).

215. R. Laucius, J. W. Davidson, and N. E. Hertel, " Calculation of the i Differential Efficiencies of Organic Scintillators to Neutrons Above 10 MeV,"

i Trans. Am. Nucl. Soc. , 43, 625, November 1982.

216. J. W. Davidson and N. E. Hertel, "Bonner Ball Detection Responses for i Neutrons from Thermal Energies to 17.3 MeV," Health Physics Society Annual Meeting, Baltimore, Maryland, (submitted for publication).

1 217. N. E. Hertel, J. W. Davidson and R. M. Laucius, "NE-213 Response Matrix for Neutron Spectrometry Up to 50-MeV," Health Physics Society Annual Meeting, Baltimore, Maryland (submitted for publication).

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