ML19309E800

Annual Operating Rept 1979.

ML19309E800
Person / Time
Site:	05000192
Issue date:	03/31/1980
From:	Klein D TEXAS, UNIV. OF, AUSTIN, TX
To:
Shared Package
ML19309E798	List: ML19309E797 ML19309E800
References
NUDOCS 8004240420
Download: ML19309E800 (56)

Text

_ _ _ . _ __ ___ _ _. ._ _ _. . __

!O

.c ,  !

+3 4

'i' a ( . :;

s.

s . x .f ~

.glliE-

- p-1 i V l

i i

NUCLEAR REACTOR LABORATORY TECHNICAL REPORT l

THE UNIVERSITY OF TEXAS COLLEGE OF ENGINEERING DEPARTMENT OF MECifANICAL ENGINEERING l

8004240YSG,

1979 Annual Report of The University of Texas at Austin Nuclear Engineering Teaching Laboratory l

l l

January 1,1979 - December. 31, 1979 D. - E. Klein, Director J. A. Burack, Supervisor Taylor Hall 104 512-471-5136 March 1979-  !

1

TABLE OF CONTENTS Page

i. List of Figures . . . . . . . . . . . . . . . . . . . . . i ii iv ii. List of Tables .....................

1

1. Introduction ......................

Laboratory Administration . . . . . . . . . . . . . . . . 3 II.

A. Organization B. Personnel C. Reactor Comittee D. Radiation Safety Comittee Laboratory Development ................. 9 III.

A. Organization B. Nuclear Engineering Teaching Laboratory C. Nuclear Radiation Laboratory D. Subcritical Facility E. Neutron Activation Analysis Facilities Laboratory Operation and Utilization 13 IV. ..........

A. Reactor Facility V. Laboratory Inspections ................. 20 A. Inspection by the Nuclear Regulatory Comission on Special Nuclear Materials B. Inspection by the Nuclear Regulatory Comission on Controlling and Accounting for Special Nuclear Material C. Inspection by the Nuclear Regulatory Comission on l Operations and Procedures D. Inspection by the Nuclear Regulatory Comission on Physical Protection of Plants and Materials VI. Public Service Activities . . . . . . . . . . . . . . . . 21 ,

1 A. Summer High School Science Teachers Symposium B. Lectures and Presentations

- C. Tours and Radiation Monitoring 23 VII. Research Activities . . . . . . . . . . . . . . . . . . .

VIII. Publications from the Nuclear Engineering Teaching Laboratory ..................... 36 11 e,

= <wv-- -

s List of Figures Figure No. Page

1. Floor Plan of the Nuclear Engineering Teaching 2 Laboratory

2. Organization Chart of the Nuclear Engineering 4 Teaching Laboratory

3. Comparison of Burn up vs year 16

4. Comparison of number of samples irradiated vs 17 year O

O iii-0

List of Tables Table No. Page

1. Comparison of Previous Utilization Data 14

2. Nuclear Engineering Teaching Laboratory 15 Performance Data 1979

3. Courses Utilizing the Reactor and Associated 18 Facilities

4. Reactor Scrams 19

5. Comparison of Yearly Inadvertant Scrams 19

6. Statistical Summary of Radiation Exposure 22

7. Research Funding 35 l

1 I

iv l O

I. INTRODUCTION This report has been prepared by the staff of the Nuclear Engineering Teaching Laboratory (NETL), The University of Texas at Austin, to satisfy the reporting requirements of the U.S. Department of Energy Contract Number At-(40-1)-3919 and 10 CFR 50.59. This report covers the period from January 1, 1979 to December 31, 1979.

The NETL is presently equipped with a 250 kW TRIGA Mark I nuclear reactor, a 1900 curie Cobalt-60 irradiator, a 150 kV Cockcroft-Walton 14 MeV neutron generator, three Californium-252 neutron sources, a subcritical assembly, and a computer coupled neutron activation analysis laboratory.

The nuclear reactor complex is siiawn is Figure 1.

The major changes made to the laboratory during this period were:

1. The Nuclear Reactor Laboratory became entitled the Nuclear Engineering Teaching Laboratory and received separate funding during the 1979-80 academic year. The Nuclear Engineering l

Teaching Laboratory remains within the Department of Mechanical Engineering.

2. Replacement of the Compensated Ion Chamber for the Linear Recorder Power Channel.

I

3. Transfer of the Californium-252 sources from the LSU loan program to the facilities D.O.E. fuel contract.

4. Complete renovation of thel 50 kV Cockcroft-Walton 14 MeV l

neutron generator.

1 l

1 l

2 l.

l l

I l

l 12 7 . .

SHOP AREA e t l NEUTRON ACTIVATION ANALYSIS NUCLEAR LABORATORY TEACHING ls s LA80RATORY ,,

CHENISTRY

~~

l25 LABORATORY F OFFICE . -

1 a RADl0 CHEMISTRY 3.

DARK LABORATORY -

RM. AIR -

, , J CONDITIONING ROOM

~'

131B REACTOR ..

CONSOLE 1 " "

8 ROOM -- 131 --

SHOP 13lA - -

T b-- .

10 4 0FFICE ,,

D RIVEWAY I b--i t---

NORTH * ""

/\ OFFICE . . O F FICE "

1358 135A ..

a FIGURE l- FLOOR PL AN OF REACTOR L A80R AT ORY COMPLEX.

II. LABORATORY ADMINISTRATION A. Organization The present organizational chart of the Nuclear Engineering Teaching Laboratory is presented in Figure 2.

~

B. Personnel The following is a list of personnel of the Nuclear Engineering Teaching Laboraotry for the period January 1,1979 to December 31, 1979.

3aboratory Administration and Staff Klein, D.E., Director

+8auer, T. L. , Researcher

• Burack, J. A., Supervisor Tomlin, B. B., Chief Technician (terminated)

• Pradzynski, A. H., Radiochemist Garcia-Morrison, M., Administrative Secretary -

Garvel, L., Secretary Dao, T., Laboratory Assistant Hertel, N.E., Researcher Graduate Assistants Ally, M.

Davidson, J.

Ganthner, S.

Hamann, J. -

Hodge, S.

Hsu, D.

Krause, M.

Kunimoto, Y. l Murphie, B.

Razzaque, M.

Sanders, T.

Simov, R.

+ Smith, D.

Taylor, G.

Yang, S.

+ -- Licensed Senior Operator l

• -- Licensed Operator 3

j

Dean of Engineering Chairman M. E. Department Director

- Nuclear Engineering s

,- Teaching Laboratory 's Radiation N Reactor Safety '

/ Comittee Committee 's ,

I '

Reactor Supervisor '

1 Reactor Instructors -

Technicians -Experimenters l LINE OF RESPONSIBILITY

_ _ _ _ _ _ _ _ _ _ _ _ CONSULTATION AND VET 0 POWER FIGURE 2 - ORGANIZATIONAL CHART -1 t

4-l y -- -- --- - - - - - s - , --..-m e, n m - , , - -

C. Reactor Committee

1. Committee Composition Regular Members: (9/1/79)

Dr. Joe Ledbetter Dr. Harris Marcus (Chairman)

Dr. Dale Klein Dr. Nolan E. Hertel Mr. Michael Krause (Student)

Ex-Officio Members: . .

Dr. H. G. Rylander, Chairman, Department of Mechanical Engineering Mr. H. W. Bryant, University Radiation Safety Officer j Mr. J. A. Burack, Supervisor, Nuclear Engineering Teaching Laboratory Dr. T. L. Bauer, Researcher, Nuclear Engineering Teaching Laboratory

2. Meeting Frequency The Reactor Committee met four times during the cale1dar year of 1979.

3. The Nuclear Reactor Committee Annual Report for September 1978 to August 1979 is included on the following pages.

D. Radiation Safety Committee

1. Committee Composition Dr. E. L. Powers, Chairman (1/79 - 9/79)

Dr. P. Riley, Chairman (9/79 - 12/79)

Dr. L. O. Morgan Dr. Joanne Ravel '

Mr. H. W. Bryant, Ex-Officio

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

year of 1979.

5

T0: Dean Gloyna FROM: Harris L. Marcus

SUBJECT:

NUCLEAR REACTOR COMMITTEE ANNUAL REPORT September 1978 to August 1979 Function, Activities, and Membership _

The Nuclear Reactor Laboratory staff and facility are administered through the Department of Mechanical Engineering of the College of Engi-neering at The University of Texas at Austin. The Nuclear Reactor Com-mittee is a requirement of the Nuclear Regulatory Commission and its func-tion is to ensure that the nuclear reactor and its associated facilities are operated in a professional and safe manner.

This objective is met primarily by regularly scheduled quarterly meetings of the Nuclear Reactor Committee. These meetings include a re-view of the activities of the reactor staff, faculty, and associated graduate students; a tour of the laboratory facilities by a member or members of the committee; and a reporting of the minutes which includes any unusual occurrences. The committee also reviews and accepts or rejects any special experiments or requested changes in the reactor technical speci-fications and/or operating procedures. Minutes of the committee meetings

, are recorded and reviewed. The committee does not involve itself with the day-to-day activities of the reactor facility, as these responsibilities lie with the associated faculty and professional staff of the Nuclear Reactor Laboratory.

Membership on the committee consists of two categories: members and ex-officio members. The committee members are appointed by the Dean of 6

s the College of Engineering, usually after conferring with the Director of the Nuclear Reactor Laboratory and the Chairman of the Depar'tment of Mechan-ical Engineering. The members include faculty members having somt. knowledge of nuclear engineering and reactor operation, but with no direct involvement in the operation of the reactor facility. In recent years one or two stu-dents have been added to' the comittee. The members of the comittee as of June 1979 are: Professors H. L. Marcus (Comittee Chairman and on the Mechanical Engineering faculty), Joseph Ledbetter (Civil Engineering),

Nolan Hertel (Mechanical Engineering), and M. Krause (student in Mechanical Engineering). The ex-officio members are: the Chairman of the Mechanical Engineering Department (H. .G. Rylander), the Director of the Nuclear Reactor Laboratory (Dale Klein), the Reactor Supervisor (J. Burack), and the Univer-sity Radiation Safety Officer (W. Bryant).

Activities and Coments The recorded activities of the Nuclear Reactor Comittee and those items of business pertinent to the comittee are included in the minutes of the quarterly meetings, copies of which are attached. These include minutes for the meetings of October 26, 1978; January 31, 1979; and May 3, 1979. An additional meeting will be held this summer. Specific items of interest include:

(1) The Nuclear Regulatory Commission held inspections of the Special Nuclear Material license SNM-180; the Special Nuclear Material reporting and inventory; the annual fuel inspection and the inspection of.the operations and records. In total only one noncompliance was found.

L 7

, . (2) The number of . licensed opeartors was increased.

(3) Numerous minor upgrades in the equipment have been made and are underway.

(4) Usage of the reactor has been increasing steadily.

The committee has found an increas in vitality of the operations of the Reactor Facility under Professor Klein. This includes more planning and carrying out of research and service work in the reactor. The nuclear area is making large strides in moving forward in terms of the organization of the reactor and support facilities.

One of the strong suggestions of the committee is that security bars or mesh be put on all the windows in the reactor area. This includes both external and internal windows and doors. In. addition the equipment associated with the reactor is in continuing need of upgrading and wil1 need continued support if the positive direction of the Reactor Facility is to be maintained.

In general we feel that this year has been a very positive year for the Nuclear Reactor Facility in terms of activity, improvement in operations and in general enthusiasm.

Harris L. Marcus Chainnan Nuclear Reactor Committee (The original was signed by Dr. Marcus.)

8

III. LABORATORY DEVELOPMENT A. Organization

1. Dr. Dale E. Klein continued as the Director during the past year. The Nuclear Engineering Teaching Laboratory received separate University funding effective September 1979. Several full time staff positions are in the process of being filled as well as major upgrading of laboratory equipment.

B. Nuclear Engineering Teaching Laboratory The Nuclear Engineering Teaching Laboratory is an important part of the Nuclear Engineering program at The University of Texas.

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

In 1968, the facility license was amended to allow the TRIGA reactor to operate at a steady state power level of 250 KW and pulsed power of 250 MW which increased experimental capabilities tremendously. The acquisition of lithium drifted silicon and germanium solid state radiation' detectors along with dual Nuclear Data 1024 channel multichannel analyzt.rs coupled to a Data General Nova 800 minicomputer, into which the outputs of the solid state detectors are sent, has made possible rapid, accurate analyses of large quantities of data.

Other experimental devices available at the Laboratory are a subcritical assembly, a 1900 curie cobalt-60 irradiator, a Nuclear Chicago sodium iodide 9

coincidence counting system, a neutron beam irradiatinn facility and numerous proportional and Geiger-Mueller detection and counting systems.

The nuclear reactor and the associated laboratory equipment are also used to teach the fundamentals of reactor operation. Students from all over the state as well as other organizations and groups have toured the Nuclear Engineering Teaching Laboratory. Approximately 1000 persons tour the Laboratory each year.

The use, operation, regulation, security, and monitoring of the Nuclear Engineering Teaching Laboratory is controlled by the United States Nuclear Regulatory Commission, the Nuclear Reactor Committee of The Univer-sity of Texas, the Director of the Nuclear Engineering Teaching Laboratory and the Radiation Control Board of the State of Texas.

The use, operation, security and radiation monitoring of the Nuclear Radiation Laboratory is controlled by the Director of the Nuclear Engineer- ,

l ing Teaching Laboratory and the Radiation Safety Officer of The University of Texas at Austin.  ;

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

The initial use of the building was to house and operate a 14 MeV Texas Nuclear neutron generator. To facilitate ex;'eriments utilizing the neutron generator, a large quantity of graphite was obtairad, machined and formed into a 8 ft. cube into which was inserted the drift tube of the neu-tron generator. This device is a very flexible one for investigating neu-tron migration in matter. When the Nuclear Engineering Teaching Laboratory 10 g

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. Thus, with the acquisition 252 , itudents and staff can perform experiments utilizing not only of Cf the high energy neutrons from the neutron generator but fission spectrum 52 In addition to the neutron generator and the Californium neutrons from Cf .

sources, other smaller radioactive sources are also used within the confines of the Nuclear Radiation Laboratory.

Large amounts of neutron shielding material have been installed in and around the neutron generator cavity and at selected spots on the exterior of the building to protect other experimentalists and the environment from 1

abnormal radiation levels. Because of the possibility of high radiation doses within the confines of the neutron generator cavity, the Nuclear Radia-tion Laboratory is a limited access building and all external doors are wired into the controls of the generator so that any unwarranted entry auto-matically shuts down the machine.

D. Subcritical Facility In association with ME 361F, the undergraduate nuclear engineering laboratory course, the subcritical assembly has continued to provide a facility with which the student can perform measurements that are related to fundamental reactor parameters. Such concepts as age, diffusion, and buckling are demonstrated in individual experiments performed by each student.

E. Neutron Activation Analysis Facilities The Nuclear Analytical Laboratory has provided support for more than twenty separate projects ranging from analyses for criminal investigation 11

to student laboratory support for advanced classes in chemistry, zoology, I physics, and engineering. 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 f ,

i been presented at conferences of the state, national and international i level.

.* s i

I 1

1 i

t 1

12 1

I 1

IV. Laboratory Operation and Utilization A. Reactor

1. Operation During this reporting period the reactor operated for a total of 311.61 hours7.060185e-4 days <br />0.0169 hours <br />1.008598e-4 weeks <br />2.32105e-5 months <br /> while supporting numerous nuclear engineering and operation courses, research, and other related activities. This large increase in operating time was primarily due to the long irradiations of large numbers of samples from a subcontract with Southwest Research Institute.

2. Utilization Tables 1 and 2 and Figures 3 and 4 show the utilization of the reactor for the year and compares this data with that of previous years.

3. Courses Offered using the Reactor Table 3 lists the courses offered at The University of Texas at Austin which utilized the reactor and associated facilities.

4. Maintenance During 1979 most maintenance was limited to routine and adjustments; however, decreasing dependability of one of the compensating ion chambers required that a new chamber be purchased and installed.

5. Inadvertant Reactor Scrams During 1979 there were 11 inadvertant shutdowns as compared with 14 in 1978. Tables 4 and 5 itemize the " SCRAMS" and compare this year's data to previous years' data.

13

TABLE 1 I

COMPARIS0N OF PREVIOUS UTILIZATION 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 28,168 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 31 8.6 45,794 1347 1974 226.1 27,641 778 1975 206.905 20,450 363 1976 135.74 11,312 468 1977 139.29 7,509 164 1978 171.9 26,870 178 1979 311.61 72,616 1568 i

• 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.

14

^

4 TABLE 2 NUCLEAR ENGINEERING TEACHING LABORATORY ,

PERFORMANCE DATA, 1979 Total Hours Total Number of Reactor In Burn-up Samples Opera tion * (kW-hrs) Irradiated First Quarter 109.85 19,o42.8 223 1979

. Second Quarter 140.55 28,287.0 603 1979 Third Quarter 88.64 . 17,130.88 609 1979 Fourth Quarter 72.57 7,655 133 1979 TOTAL 311.61 72,615.68 1,568

• Includes experimental setup time, maintenance, etc.

15 va r n -

e

16 g._

60--

50--

en T

i 40--

n x

O o 30--

9 2

o-o 20--

l Z

T D

D lo.-

O , i i i i i i i i i l 67 68 69 70 71 72 73 74 75 76 77 78 79 YEAR FIGURE 3 - TOTAL BURN UP PER YEAR

17 3--

o IM

<[

a

<I

$_ 2-td i

2 LL o i..

o Z

D O

h O l I 1 l 1 l 1 1 68 69 70 71 72 73 74 75 76 l 77 78 79 YEAR FIGURE 4 - NUMBER OF SAMPLES IRRADIATED PER YEAR

l l

l l

TABLE 3 COURSES UTILIZING THE REACTOR AND ASSOCIATED FACILITIES Course Number Course Description ME 397 This course was a project course in which the experiments for ME 379M were documented for use as an aid to the students.

ME 361F Introductory Nuclear Laboratory Designed as an introduction to radio-active decay, activation, and radiation measurement.

CH 376K A senior level course in instrumental analytical methods which utilizes the Nuclear Reactor Laboratory Facilities to study Neutron Activation Analysis.

CE 390L Environmental Analysis This is a graduate course in environ-mental analysis for environmental health engineers. Students use neutron activa-tion analysis anc energy dispersive X-ray emission spectrometry to analyze samples l for toxic contaminants. l ME S389R A special projects laboratory course for foreign nuclear engineers.

ME 379M A reactor operations course, open to all students. Designed to allow students with an interest in nuclear power to learn basic reactor theory and participate in actually operating a nuclear reactor.

ME 377K A special projects course whereby students can pursue special topics.

ME 389R A required laboratcry course for students pursuing a Master of Science in the Nuclear Program.

i l

18

1 a

E TABLE 4 REACTOR SCRAMS

! Intentional --

11 Operator Error -- 10 4 Instrument Error --

1

, Power Outage -- 0 Safety -- 1 1

Total --

23 4

i i

3 TABLE 5 ~

, COMPARIS0N OF YEARLY INADVERTANT SCRAMS

'63 '64 '65' '66 '67 '68 '69 '70 '71 '72 '73 '74 '75 i 10 9 3 4- 3 31 15 11 13 6 10 4 7 c

4

'76 '77 '78 '79 i

5 9 14 'll-l i

i n

19 h

y g . 9 7-w r-

V. LABORATORY INSPECTION A. An inspection by a member of the Nuclear Regulatory Comission of the facilities Special Nuclear Material License No. SNM-180 occurred during February,1979, in which no items of non-com-pliance were found.

B. An inspection by members of the NRC regarding the controlling and accounting for special nuclear material occurred during i March,1979, in which one item of non-compliance was found.

C. An inspection by members of the NRC regarding activities authorized by NRC Operating License No. R-92 occurred during April,1979,in which no items of non-compliance were found.

D. An inspection by a member of the NRC regarding applicable provisions of 10 CFR 50 and 10 CFR 73 pertaining to Physical f

J l Protection of Plants and Materials occurred during October,1979, in which no items of non-compliance were found.

20

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

A. Summer High School Science Teachers Symposium Funded by the Electric Utility Companies of Texas, this program was designed to familiarize high school science teachers with the theory and technology of energy resources. During the summer of 1979, 40 teachers participated in the program.

B. Lectures and Presentations On numerous occasions during 1979 the NETL staff gave talks on subjects including: " Nuclear Reactor Safety," " Nuclear Engineering and Society," "Research and Development of Energy Resources," " Energy and the Environment," and "What Happened at Three Mile Island."

C. Tours and Radiation Monitoring During the calendar year of 1979 over 1,000 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 the non-measurable exposure range as indicated by pocket dosimeters. Persons l employed by or working in the laboratory are issued film badges. The l annual statistical summary of those badges is found in Table 6.

21 l

4

4

, TABLE 6 i

STATISTICAL SUM 1ARY OF RADIATION EXPOSURE Range of Exposure Number of in REM Individuals i

Non-measurable exposure 49

~

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

1.0 - 2.0 0 j 2.0 - 3.0 0 1

1 4

i 22 l

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 has sponsored Summer iiigh School Science Teachers Symposium, a program designed to familiarize these teachers with the theory and technology of energy resources.

C. " Determination of Vanadium and Barium in Marine Sediments and Bicta."

Personnel: A. H. Pradzynski, NETL T. L. Bauer, NETL M. Ally, NETL Sponsored by: Southwest Research Institute (SWRI)

Description:

The Southwest Research Institute (SWRI) in San Antonio subcon-tracted to the Nuclear Engineering Teaching Laboratory a part of a project on " Ecological Investigations of Petroleum Production Platforms in the Central Gulf of Mexico." The project was performed under SWRI's contract with the Bureau of Land Development, Department of the Interior No. AA550-RP8-2.

l The primary goals of the Bureau of Lano Management's (BLM) Outer Continental Shelf (OCS) environmental studies program are: (1) to obtain environmental data on the impacts of petroleum exploration and production activities on the OCS and (2) to provide relevant information to decision-makers in the Bureau's 0CS minerals management program.

23

D. " Determination of Gold in Human Excretion Samples" Personnel: Gerald Yakatan, Dept. of Pharmacy Joseph Massarella, Dept. of Pharmacy Andrzej H. Pradzynski, NETL Sponsored by: Nuclear Engineering Teaching Laboratory and Dept. of Pharmacy

Description:

A feasibility study was performed with the Department of Pharmacy on determination of Au in human urine, salvia, and feces. Gold is admin-istered to patients suffering from arthritis as a systemic medication.

The excretion of Au from the body has been investigated in a pharmaco-logical study at the Department of Pharmacy. Neutron Activation Analysis was performed on several hundreds of samples of urine, feces and saliva.

The sensitivity and accuracy of determinations was established to be ade-quate for the application of the NAA-method in this project.

E. Measured Neutron and Gamma-Ray Spectra in a Tissue-Equivalent Medium Under Bombardment by 14-MeV Neutrons Personnel: Nolan E. Hertel, NETL William E. Murphie, NETL Sponsored by: Texas Atomic Energy Foundation .

Bureau of Engineering Research  !

1

Description:

An experimental fusion-neutron irradiation facility at Balcones Research Center is being used to measure neutron and gamma-ray fields in a tank of tissue-equivalent liquid. A neutron generator is used to pro-duce 14-MeV neutrons which impinge on the surface of the tank. An NE-213 spectrometer is used to measure neutron and gamma-ray fluxes at various

. locations in the tank as a function of incident neutron flux. The project 24 i l

1

will be useful in assessing the neutron-induced gamma-ray spectrum in tissue as well as the quality of the neutron and gamma-ray doses. The results will provide information of relevance in cancer radiotherapy as -

well as in the determination of dose equivalent indices due to fusion neutrons.

F. Accelerator Breeding of Fissile Fuel Personnel: flolan E. Hertel, fiETL Steve Ganthner, fiETL Sponsored by: Texas Atomic Energy Research Foundation

Description:

The production of fissile material from relatively abundant fertile isotopes through the use of accelerator breeders has been the sub-

% ject of several investigations. The concept which most fully utilizes

- uranium and thorium resources without requiring reprocessing of irradiated fuel involves placing entire Light Water Reactor fuel assemblies in accel-erator blankets. fleutronic evaluations are being undertaken to determine the advantages of using various initial enrichments in these uranium fuel assemblies. The irradiation time necessary to obtain a desired final reac-tivity is a significant factor in assessing the overall economic attractive-ness of accelerator breeding. A short irradiation tims yields a low accel-erator energy cost per ton'of fuel enriched. Ilowever, any cost advantage thus achieved may be offset by the greater cost of enriching the uranium.

Another important cost consideration 'is the large amount of external power required to drive the accelerator. An accelerator breeder design which would use the thermal power potential of the blanket is also being investi-gated.

25

G. A Study of Waste Toxicities in a Thorium Fuel Cycle Personnel: Nolan E. Hertel, NETL Yukitaka Kunimoto, NETL Sponsored by: Texas Atomic Energy Research Foundation

Description:

As the availability of uranium becomes limited, reactors fueled exclusively with uranium may give rise to the development of thorium fuels.

Although thorium has excellent nuclear properties, the use of thorium fuels is relatively undeveloped. To explore the properties of thorium fuel cycles, a model fuel cycle was developed which would use thorium and highly enriched uranium. This model fuel type was used to investigate the waste stream toxicities for the thorium fuel cycles and compare them with other fuel cycle toxicities.

H. Modification of COBRA-4 Personnel: Dale Klein, NETL Sam Yang, NETL Pat Peng, NETL Tom Sanders, NETL Sponsored by: General Atomic Company and the Center for Energy Studies

Description:

Thermal-hydraulic analysis is presently performed for the Gas Cooled Fast Breeder Reactor (GCFR) using the computer code COBRA-4. The steady state version has been verified thoroughly by benchmark experiments.

However, the. transient version has not been verified and the'present tran-sient versica utilizes considerable computer time. The present project involves a detailed analysis of the model used, an updating of the present code to take advantage of recent numerical methods, and an addition of a l

new model to speed up calculations.

26

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

Description:

Two basic techniques exist presently at the Nuclear Engineering Teaching Laboratory at The University of Texas at Austin for the determina-tion of trace elements (e.g. uranium). These include neutron activation analysis and x-ray fluorescence. When the elements to be examined are present in small quantities, either a large sample must be activated or a sample must be concentrated. There are several advantages of a preconcen-tration method and the objective of this project is to develop a suitable method for the analysis of trace elements of uranium in water. This method may then be extended to other similar trace elements.

l J. Design and Construction of a Test Assembly for Rough Surface Analysis Personnel: Dale Klein, NETL Mike Krause, NETL Sponsored by: Center for Energy Studies

Description:

The surface of the Gas Cooled Fast Breeder (GCFR) fuel rods is artificially roughened. This roughening enhances heat transfer and enables a higher bulk coolant temperature. A new method has been developed recently l

that demonstrates the slope and the intercept-in the dimensionless velocity l l

profile can be determined without velocity profile measurements. Data is insufficient for a variety of roughness shapes and geometric spacing values under consideration for the GCFR. This project is to develop a system to I \

enable fundamental heat transfer augmentation measurements from artificially

-j roughened surfaces.

27 l l

K. Use of an HTGR for Lignite Gasification or Liquefaction Personnel: Dale Klein, NETL Mike Ross , Graduate Student in Energy and Fluid Systems Sponsored by: Center for Energy Studies

Description:

Texas has cons.derable deposits of lignite and these deposits might be more * .ly utilized if converted to another form,either gas or liquid. This project is to examine the economic and environmental aspects of lignite development in conjunction with a High Temperature Gas Cooled Reactor (HTGR). Various processes will be considered whereby the process heat is supplied by an HTGR. Economic considerations will be based on the HTGR being used for electrical production in addition to supplying process. heat.

L. Thermal Analysis of a Spant Fuel Shipping Cask in an Enguling Fire personnel: Dale Klein, NETL James Hamann, NETL

~

Sponsored by: Sandia Laboratories

Description:

The design of a nuclear fuel shipping cask must be'such that it survive an engulfing fire in a manner to contain the enclosed radioactive material. A thermal analysis using the computer code HEATING 5 is underway to predict the temperature distribution in a nuclear fuel shipping cask.

Results-obtained from this analysis will be compared to data obtained by Sandia from a full scale test ,where a shipping cask was engulfed in a fire for over 120 minutes. The present thermal analysis models a 3-dinensional transient system where a change of phase can occur.

28 l

M. Determination of the Relative Toxicities of the Fission Products Produced in the Transmutation of Actinide Wastes Personnel: Dale Klein, NETL Duncan Hsu, NETL Sponsored by: Texas Atomic Energy Research Foundation

~

Description:

The dominant contribution to the total toxicity of radioactive wastes will be analyzed. This will include the contribution of the acti-nides from a long-term management point of view. Reducing the toxicities of the actinides via neutron-induced fission transmutation is being examined.

Three fission reactor fuel cycles (PWR-U, PWR-Pu, and LMFBR) and two trans-muter neutron energy spectra will be considered.

N. Determination of Friction Factors and Heat Transfer Coefficients for Flow Past Artificially Roughened Surfaces Personnel: Dale Klein, NETL Steve Hodge, NETL Sponsored by: Oak Ridge Associated Universities Oak Ridge National Laboratory

Description:

A critical review of the assumptions, theoretical foundati6ns, and supporting experimental evidence for the a..alytical procedures in current use for evaluation of the effects of artificial surface roughening is under-way. A new method for analysis is to be demonstrated for the determination of the slope and intercept of the universal logarithmic dimensionless velocity law for fully rough flow. This method does not require experimental measure-ment of the velocity profile. Results from this study will be applied to the Core Flow Test Loop (CFTC) under construction at Oak Ridge National Laboratory T

and will aid'in the design studies-for the Gas Cooled Fast Breeder Reactor (GCFR).

29

0. Structural Activation in Fusion Devices Personnel: Dale Klein, NETL Danny Smith, NETL Sponsored by: Texas Atomic Research Foundation

Description:

The primary thrust of the current work in the area of structure activation in fusion devices involves the development: of capabilities for characterizing the neutron flux in the various regions of the devices to be examined. Computer codes are available for one-dimensional neutron transport calculations and other codes are being adapted to The University of Texas computer system which will allow two-dimensional transport analysis.

Other aspects of this work include the selection of the specif.ic devices to

• I .'

be investigated, formulation of better methods for characterizing the poten-tial hazard of the radioisotopes generated and examination of techniques j for minimizing the total hazard of the radioisotopes generated.

P. Finite Elements in Radiative Heat Transfer in A';borbing/ Emitting Medium Personnel : Dale Klein, NETL  ;

Muhammad Razzaque, NETL l

Sponsored by: Texas Atomic Energy Research Foundation

Description:

The transfer of heat through materials that attenuate radiation is- 1 l

mathematically difficult to model. The finite element method is being used in an effort to solve such problems as heat transfer by radiation through hot gases in gas-cooled reactors, industrial furnaces or a fusion plasma.

Successful application may allow design of more efficient devices of their  ;

I associated heat transfer components, l l

4 I

30 l

Q. Steel Analysis Using Advanced Radiation Detection Methods' -

i Undergraduate Research Project for ME 377K Personnel: Dale Klein, NETL A. H. Pradzynski, NETL Douglas Devine, Undergraduate Student in Mechanical Engineering j Sponsored by: Nuclear Engineering Teaching Laboratory

Description:

Qualitative X-Ray Fluorescence Analysis and Neutron Activation Analysis were used for identification of steel samples. Unknowns and standard samples were measured and spectra were compared. Conclusions on steel types were drawn on the basis of chemical composition.

R. Development of Neutron Flux Monitor for Short Irradiations in Pneumatic Transfer Systems - Undergraduate Research Project EM 377K Personnel: Dale Klein, NETL A. H. Pradzynski, NETL Louis N. DeCuir, III, Undergraduate Student-in Mech. Engr.

Sponsored by: Nuclear Engineering Teaching. Laboratory 'l l

Description:

Criteria for an optimal neutron _ flux monitor for short irradiations I were established. Suitable elements were selected. A preparation technique was developed and several monitors were produced. The optimized monitors were tested by irradiation and gamma-spectroscopic measurements. -

S. Determination of Trace Elements: Cr and Mn in Water Using'a Pre-concentration Method and XRF Analysis-Undergraduate Research Project CH 369K Personnel: Stephen E. Webber, Chemistry.

A. H. Pradzynski, NETL .

Peter Gilman , Undergraduate Student -in Chemistry. '

Sponsored by: Nuclear Engineering Teaching Laboratory 1

31

Description:

Conditions'of coprecipitation of Cr and Mn with carriers: Fe and Co, using Ammonium Pyrrolidine Dithio-Carbamate (APDC), were researched.

Optiumu pH levels were determined for maximum recovery of trace elements.

Samples were prepared by pressure filtration and measured using an Energy Dispensive X-Ray Fluorescence Si(Li) spectrometer. Data were processed using an on-line computer.

T. Determination of Cs, Rb, Na, K - Graduate Research Project Personnel: Joseph J. Lagowoski, Chemistry A. H. Pradzynski, NETL Ron Harris, Graduate Student in Chemistry Sponsored by: Nuclear Engineering Teaching Laboratory

Description:

Quantitative determinations of Cs, Rb, Na and K in small samples are difficult and inaccurate by conventional chemical methods. Neutron Activation Analysis and Gamma Spectrometry were used for determination of these elements in small samples evaporated from liquid ammonia.

U. Advanced Analytical Chemistry - CH 376K Personnel: J. Holcomb, Chemistry A. H. Pradzynski, NETL Sponsored by: Nuclear Engineering Teaching Laboratory

Description:

Undergraudate students in chemistry performed qualitative and quan-titative determinations of several elements in samples by neu+.ron activation analysis. The program of the class included: (a) sample preparation and en-capsulation, (b)- two irradiations i,n the TRIGA reactor, one for long half-life _ and another for short half-life radioisotopes, (c) measurements using 32

a Ge-Li detector gamma spectrometer, (d) data processing using an on-line computer and (e) data evaluation and discussion of practical applications of NAA in analytical chemistry.

V. 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:

During experiments on As accumulation in fish from a contaminated lake, another toxic element, Se has been found in the samples. Determina-tions of Se were done by Neutron Activation Analysis and Gamma Spectrometry using the same method as in the As study. Further exeriments will.be per-formed.

W. Arsenic Accumulation in Fish

! Personnel: Elsie Sorensen, Memphis State University A. H. Pradzynski, NETL l Thomas L. Bauer, NETL Sponsored by: Nuclear Engineering Teaching Laboratory

Description:

Teleccts have been known to accumulate As to high levels during environmental exposure. Fish (L. cyanellus) from a contaminated lake ex-l posed to As were dissected and As was determined in livers and kidneys. i Neutron Activation Analysis and gamma spectrometry were used for the deter-mination of As. Data were compared with the results of histological tests using optical and. electron microscopy. Good correlation was established.

33 1

1

X. Neutron Activation Analysis of Ferro-Alloys, Ores and Intermediates in Iron Metallurgy Personnel: A. H. Pradzynski, NETL Sponsored by: Nuclear Engineering Teaching Laboratory

Description:

In cooperation with the University of Monterey, Mexico, samples of Ferro-Alloys, Ores and Iron-Sponge were analyzed oy Neutron Activation Analysis and by X-Ray Fluorescence Spectrometry for several minor and trace elements. Experiments were performed by a group of students from the Uni-versity of Monterey.

Y. Preconcentration of Water Samples for X-Ray Fluorescence Spectrometric Analysis and Neutron Activation Analysis .

Personnel: A. H. Pradzynski, NETL Sponsored by: Nuclear Engineering Teaching Laboratory

Description:

Previous work on determination of trace elements in water by XRF-and HAA was continued. Investigation of a preconcentration method com-prising APDC coprecipitation and pressure filtration was performed. The investigation was extended to samples of waste water and industrial effluent.

l I

\

l 34 l

l l

a

4 TABLE 7 RESEARCH FUNDING Texas Atomic Energy Research Foundation $ 40,000 DOE -- Fuel Program ----

! Center for Energy Studies- 20,400 Southwest Research Institute _19,320 l

. Sandia Laboratories 17,000 j General Atomic Company 35,000 l l

I I

TOTAL $131,720 l

f 6

1 1

l 35

VIII. Publications From the Nuclear Engineering Teaching Laboratory

1. K.L. Gilbert, " Neutron Flux Mapping of a Subcritical Reactor Core with a Polyethylene Reflector", Masters Thesis, Physics Department, The University of Texas, 61 pp. , June 1961.

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

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

June,1962.

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

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

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

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

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

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

9. R.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 Discontinuity in Temperature and Properties", Ph.D. Dissertation, The Univer-sity of Texas, 149 pp., January 1965.

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

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

Hyalth Physics, Vol .12, No.- 4, 558, April 1966.

-13. J.B. Whitworth, "A Cryogenic Irradiation Device for the TRIGA Mark I

' Nuclear Reactor", Masters Thesis, Mechanical Engineering Department, The Uni-versity of Texas, 52 pp.. January 1967.

v

4

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 Texa:, 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.

1

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

20. P.J. Rodriguez and 0.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.

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

22. G.D. Bouchey and S.J. Gage, " Neutron Radiography with a Small Subcritical Reactor", Trans. Am. Nucl. Soc., R , 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). l

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 1959.  ;

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

Masters Thesis, Physics Department (Nuclear Engineering), The University of Texas, January 1969.

V. Chanto, S.J. Gage, and D.F. Barker, " Chlorine and Bromine. Concentrations  !

26.

in Some Haliburton-Bancroft Rocks and Minerals by Neutron Activation Analysis",

1969.

u

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

28. G.D. Atkinson, Jr., " Investigation of the Dynamic Behavior of a Two-Region Subcritical Reactor", Masters Thesis, Mechanical Engineering (Naclear 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.

I

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

II Inorganic Ingredients", Quarterly Journal of Crude Drug Research, Vol. 9_, 1 No. 4 (1969). j

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

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.

l

39. P.J. Rodriguez, " Time ar.d Energy Dependent Neutron Distribution in a Pulsed Multiplying Medium", Ph.D. Dissertation, The University of Texas, 205 pp. , Jar.Jary 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 Nonlit. ear Programming 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 Kinetics", Journal of Nucl . Energy, Vol. 24, pp.1-10. Pergamon Press 1970. Printed in Northern Ireland.

43. G.D. Bouchey and S.J. Gage, " Neutron Radiography at The University of Texas Nuclear Reactor Laboratory", Isotopes 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. 6.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 Gama Ray Analysis with a Compton Suppressed Ge(Li) Radiation Source", Ninth National of the Society of Applied Spectros-copy, New Orleans, Louisiana, October 5-9, 1970.

K.R. Waid, " Solid State Radiation Detection Devices: Fabrication, Techniques 50.

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.

l r

i

52. J.J. Chromik and E.L. Draper, Jr., " Energy Integral Tests of Differential Fission Cross Section Data", Trans. Am. Nucl. Soc., Vol. l_3,, 3 No. 2, p. 755 (1970).

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

54. E. Oelkers, Jr., "A Learning Method for Identification of Nuclear Reactor Point Dynamics", Masters Thesis, Mechanical Engineering Department, The Uni-versity of Texas, pp.165, August 1970.

55. F.A. Rodriguez-Gonzalez, " Application of Neutron Activation Analysis .

to the Study of Interstitial Solid Solution of 0xygen in Niobium and in Niobium-Titanium Alloys", Ph.D. Dissertation, The University of Texas,131 pp.

August 1970.

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

57. C.T. Rombough, " Application of Queueing Theory to Closed-Loop Computer-Reactor Control Systems", Masters Thesis, Mechanical Engineering Department, The University of Texas, 78 pp. , December 1970.

58. A.H.U. Bohorquez, "A Programmed Associative Analyzer", Masters Thesis, Mechanical Engineering Department. The University of Texas, 98 pp. December 1970.

59. S.J. Gage and D.G. Jopling, The Nuplex Concept: Potential for the, SINB Region, Southern Interstate Nuclear Board, 250 pp., March 22, 19: .

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

(1971).

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

62. A.H. Pradzynski and S.J. Gage, " Nondestructive Identification of Material by Nondispersive X-Ray Fluorescence Spactroscopy Using Si(Li) Detectors and Radioisotopic Sources", Proc. Eighth Symposium on Nondestructive Evaluation in Aerospace, Weapons Systems, and Nuclear Applications, San Antonio, Texas.

(1971).

63. G.D. Atkinson, Jr. , and S.J. Gage," Uranium Assay by Delayed Gamma Ray Analysis Following Cf-252 Neutron Interrogation", Proc. Twelfth Annual Meeting Institute of Nuclear Materials Management, Plam Springs, Florida (July 1971).

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 Application _s, CONF-710402, Vol. 2, Proc. of ANS Topical Meeting, Augusta, Georgia, April 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).

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 Programing, Nucl. Sci. and Engr. 4_4, 4 267-272 (1971).

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

70. S.J. Gage, G.D. Atkinson, Jr. and G.D. Bouchey, " Cyclic Neutron Activation Anal sis with a Cf-252 Neutron Source", Trans. Am. Nucl. Soc., (October 1971 .

l

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

Tailored Reactor Spectrum Preparation and Measurement", Nuclear Science and Engineering, M , 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_,

4 123 (1971).

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

1

77. G.D. Atkinson, Jr., J.B. Whitworth, and S.J. Gage, " Computer-Assisted Analysis of Gama-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., " Nondestructive Uranium Assay by Delayed Gama Ray Analysis Following Californium-252 Neutron Interrogation", Ph.D. Dissertation, The University of Texas,183 pp., August 1971.

80. G.D. Bouchey, "The Optimization of Nuclear Systems", Ph.D. Dissertation.

The University of Texas, 231 pp., August 1971.

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

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

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

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

86. E. Linn Draper, by Energy Dispersive, X-Ray Jr.Spectroscopy",

and AndrzejNinth H. Pradzynski, " Identification Symposium on Nondestructive of Alloys Evaluation (1972).

87. M.B. Owen, " Fuel Management Using Dynamic Programming", Masters Thesis Mechanical Engineering Department, The University of Texas, 59 pp. May 1972.

88. C.E. Brauer, " Thermal Neutron Radiography with a Lithium-Lead Collimator-Filter", Masters Thesis, Mechanical Engineering Department, The University.

. of Texas, 64 pp. , May 1972.

b

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

August 1972.

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

91. 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 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).

97. 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 j (1972).

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

! 99. E.LinnDrapgr,Jr.,JohnW.Davidson,S.J. Gage,G.D.Bouchey,"ASystem for Reduction of 'A-Release from a Research Reactor Facility", Trans. Am.

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

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

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 Anerican Nuclear -Society " Applications of Californium-252" National Topical Meeting,-

September 11-13, 1972.

?

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

103. E. Linn Draper, Jr., and S.J. Gage, "The Fusion-Fission Breeder: Its Potential in a Fuel Starved Thermal Reactor 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 M.eeting of the American Nuclear Society, November 12-16, 1972.

j 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, 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 Lithium ir 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).

1 109. E. Linn Draper, Jr. , Jcmes B. Freim, " Theoretical and Experimental Eval-uation of Nuclear Data and Calculation Techniques for Fusion Reactor Blanket 1 Design", Texas Symposium on the Technology of Controlled Thermonuclear Fusion Experiments and the Engineering Aspects of Fusion Reactors, November 20-22, 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 in a Fuel Starved Thermal Reactor Economy", presented at tha 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. Nucl . Soc. , (1972).

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

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

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

118. E. Linn Draper, Jr., Editor, Proceedings 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-241", Trans. Am. Nucl. Soc., 1973.

121. E. Linn Draper, Jr., and James B. Freim, " Experimental Determination of the Fusion Spectrum in Graphite", 'rans. Am. Nucl . Soc. , 16_,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).

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).

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

Techniques for Fusion Development Analysis", Trans. Am. Nucl. Soc., (November 1973).

125. Theodore A. 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.

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

Journal of Applied Polymer Science, Vol. _lJ7,, pp. 2597-2617 (1973.)

l l

l 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. Jeen, " 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, " Cross Section Studies Based on the Statistical Model",

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

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

Soc.,(1973).

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

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

Nucl. Soc _., (1973).

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

presented at the Combined Meetirg 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 South Central Photobiology 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 Covered Indium Resonance in a Graphite Medium" Masters Thesis, The University 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, Lepomis Cyanellus", Ph.D. Dissertation, The Univer-sity of Texas at Austin, 233 pp., May 1974.

I

! 139. E. Linn Draper, Ir., 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, (April 1974).

4 142. 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).

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

143.

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

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

Soc. , (October 1974).

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

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

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

148. J.R. Deen, E. Linn Draper, Jr., " Measurement of the Fission Product Yields and the Energy Integral Fission Cross Section of Thorium-232 in a Cali-fornium-252 Fission-Neutron Spectrum", Nuclear Technology, 25, 416 (1975).

149. E. Linn Draper, 'Jr., T. A. Parish, M. Etzion, " Utilization of a Small Accelerator for Fusion Reactor Blanket Desi n", Proceedings 'of the Third Small Accelerator Conference, USAEC, CONF-741021 1974).

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.,

2_2_, 818 (November 1975).

1 51. W.R. Smith, Jr. , E. Linn Draper, Jr. , " Measured and Calculated Fast Neutron Spectra in a Graphite Medium", Trans. Am. Nucl. Soc., 2_2,, 800 (November 1975).

152. J.W. Davidson, E. Linn Draper, Jr., " Costs for Partitioning Strategies Involved in High-Level Nuclear Waste Management", Trans. Am. Nucl . Soc. , 22, 348 (November 1975).

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

22, 322 (November 1975).

154. T.A. Parish, J.W. Davidson, E. Linn Draper, Jr., " Transmutation'of Fission Products in Fusion Reactor Blankets", Trans. Am. Nucl . Soc., 22_, -

(November 1975).

155. T.A. Parish, J.W. Davidson, E. Linn Draper, Jr., "The Effects of the D-T Fusion Neutron Energy Spectrum on High Energy Reaction Rates", submitted to the Sixth Symposium on Engineering Problems of Fusion Research, San Diego, California (November 18-21,1975).

156. A.H. Pradzynski, R.E. Henry, J.L.S. Stewart, " Determination of Selenium 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 Alterm tives, Volume II: Methodology _.

The University of Texas at Austin Center for Ent. ;y Studies, Policy Alternative Study No. 1 (1975).

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

160. R.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).

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

Technique'to the United States Controlled Thermonuclear Research Effort,"

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

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

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

i l

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

164. J.W. Davidson, "A Cost-Benefit Analysis for Partitioning Strategies In-volved in High-Level Nuclear Waste Management", Masters Thesis, The University of Texas at Austin, (May 1975).

165. T. A. Parish, J. W. Davidson, and E. Linn Draper, Jr., "The Minimization of the Hazard Resulting from Transmutation of Fission Products," Transactions of the 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-2 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 for 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, E,1976, p. 219-28.

i 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, l Ann Arbor, Michigan, May 19-21,1976, pp.175-177.

172. A. H. Pradzynski, R. E. Henry and E. L. Draper, Jr. , "Detennination of Trace Elements of Hydrogeochemical Prospecting by APDC-Coprecipitation and  !

X-Ray Spectrometry," invited paper at The International Conference on World i Nuclear Energy a Status Report. Transactions of Am. Nuclear Society, 24, -

l 1976, p.119.

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

Techniques for Nuclear Safety Research," Two-Phase Flow and Heat Transfer l 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).

j

4 175. 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 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 Jependent 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-tion, Tissue Distribution, Cytotoxity in Teleosts following Indirect Aqueous Exposure," Bulletin of Environmental Contamination and Toxicology, Vol. 21, 1979, pp. 162-169.

180. J. W. Davidson and T. A. Parish, " Fission Product Toxicity Reduction via Transmutation Using D-T Fusion Neutrons," Eight Symposium on Engineering Problems of Fusion Research, San Francisco, California, November 1979.

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

1 3_3,, 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.

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.

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 16-17, 1979.

186. A. H. Pradzynski, "Detennination of V and Ba in Marine Sediments and Biota," Internal Report, Nuclear Engineering Teaching Laboratory, The University of Texas at Austin, Department of Mechanical Engineering (1979).

187. E. M. B. Sorensen, R. R. Mitchell, A. Pradzynski, T. L. Bauer, and L. Graham,

" Correlations Between Stereological Analyses of the Parenchymal Hepatocyte and Arsenic Accumulation in the Liver of a Freshwater Teleost Naturally Exposed to Arsenic," (to be published, 1979).

l l

r .,

188. 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).

189. 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).

190. 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).

191. 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, (to be published in an NBS special publication).

192. N. E. Hertal, B. W. Wehring, " Absolute Monitoring of DD and DT Neutron Fluences Using the Associated-Particle Technique," (accepted for publication in Nuclear Instruments and Methods, December 1979).

193. 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, (accepted for publication, 1979).

d

)

1

.