ML20003F823

1980 Annual Rept of Univ of Tx at Austin,Nuclear Engineering Teaching Lab

ML20003F823
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Site:	05000192
Issue date:	03/31/1981
From:	Bauer T, Klein D TEXAS, UNIV. OF, AUSTIN, TX
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Text

O 1930 Annual Report of The University of Texas at Austin Nuclear Engineering Teaching Laboratory

~

January 1, 1980 - December 31, 1980 D. E. Klein, Director T. L. Sauer, Supervisor Taylor Hall 104 512-471-5136 March 1981 J

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_ _ _. _ _ = _ _ _.

l TABLE OF CONTENTS Page 1.

Li s t ' o f F i gures..................... -.

iii 11.

List of Tables iv I.

Introduction 1

4 II.

Laboratory Administration..................

4 A.

Organization B.

Personnel i

C.

Reactor Committee j

D.

Radiation Safety Committee III.

Laboratory Development 9

A.

Organization 4

B.

Nuclear Engineering Teaching Laboratory C.

Nuclear Radiation Laboratory D.

Subcritical Facility I

E.

Neutron Activation Analysis Facilities

)

IV.

Laboratory Operation and Utilization 13

)

A.

Reactor Facility B.

Facility Changes V.

Laboratory Inspections 20 A.

Inspection by the Nuclear Regulatory Commission on Operations and Procedures B.

A Visit by the Nuclear Regulatory Commission on Operating l

License Renewal C.

A Visit by the Nuclear Regulatory Commission on Special Nuclear Materials License Renewal i

VI.

Public Service Activities.................

21 l

A.

Summer High School Science Teachers Symposium B.

Lectures and Presentations C.

Tours and Radiation Monitoring VII.

Research Activities....................

23 VIII.

Publications from the Nuclear Engineering Teaching.

Laboratory 36 I

l 11 l

_.w,_..~._.,.._.--,_.~._____.-

O List of Figures Figure No.

Page 1.

Floor Plan of Nuclear Reactor Laboratory 2

2.

Floor Plan of the Nuclear Engineering Teaching Laboratory 3

3.

Organization Chart of the Nuclear Engineering Teaching Laboratory 5

4.

Comparison Burn up vs year 17 5.

Comparison of number of samples irradiated vs year 18 O

iii

List of Tables Table No.

Page 1.

Reactor Scrams 14 2.

Comparison of Yearly Inadvertant Scrams 14 3.

Nuclear Engineering Teaching Laboratory Performance Data 1980 15 4.

Comparison of Previous Utilization Data 16 5.

Courses Utilizing the Reactor and Associated Facilities 19 6.

Statistical Summary of Radiation Exposure 22 7.

Research Funding 23 l

l l

l IV i

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e 1.

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, 1980 to December 31, 1980.

The NETL is presently equipped with a 250 kW TRIGA Mark I nuclear reactor, a 1500 curie Cobalt-60 f rradiator, two 150 kV Cockcroft-Walton i

14 MeV neutron generators, three Californium-252 neutron sources, a-1 subcritical assembly, and a neutron activation analysis laboratory, with -

i I

various radiation detection systems. The nuclear reactor laboratory is shown in Figure I with adjacent areas of the Taylor Hall engineering building shown in Figure 2.

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

1.

The initial phase of work to improve 1.aboratory physical security has begun with work to be completed in the fi' t part of the 1931 year, 2.

Staff changes at the positions of laboratory' supervisor and technician, 3.

Acquisition of a second 150 kV. Cockcroft-Walton 14 MeV generator, and f

4.

Requests for license renewal of HRC R-92 and SNM-180 licenses

.were initiated, iacluding a revision of the Technical Specifica-i tion to currer.t regulatory forgets.

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II. LABORATORY ADfilciSTRATION A.

Organization The present organizational chart of the Nuclear Engineering Teaching Laboratory is presented in Figure 3.

B.

Personnel The following is a list of personnel of the Nuclear Engineering Teaching Laboratory for the period January 1,1980 to December 31, 1980.

Laboratory Administration and Staff Klein, D.E., Director

+Dauer,T.L., Supervisor (researcher)

+Burack, J. A., Superviser (terminated)

Povio, N., Nuclear Technical Specialist

• Krause, M., Nuclear Technical Specialist Pradzynski, A.H., Radiochemist Garcia-Morrison, M., Administrative Secretary Garvel, L., Parker, T., Smith, R., Secretary (temporary)

Dao, T., and Anaya, P., Laboratory Assistants Hertel, N.E., Researcher Davidson, J.W., Researcher 9

Graduate Assistants Ally, M.

• Ganthner, S.

Gantt, B.

Hamann, J.

• Krause, M.

Kunimoto, Y.

Laucius, R.

Murphie. B.

Razzaque,fl.

+ Sanders, T.

+ Smith, D.

Yang, S.

+--Licensed Senior Operator

• --Licensed Operator 4

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i Dean of Engineering Chairman M. E. Department Director fluclear Engineering s

N Teaching Laboratory' s

N Reactor Radiation

/

Consnittee Safety Consnittee

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Reactor Supervisor j

Reactor Instructors Technicians Experimenters i

i 4

LINE OF RESPONSIBILITY j

_ _ _ _ _ _ _ _ _ _ _ _ C0flSULTATI0tl AND VET 0' POWER l

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FIGURE 3 - ORGANIZATIONAL CHART 3

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C.

Reactor Committee _

l.

Committee Composition Regular Members:

(9/1/80)

Dr. Dale Klein 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 Dr. T. L. Bauer, Supervisor, Nuclear Engineering Teaching Laboratory 2.

Meeting Frequency The Reactor Conmittee met four times during the calendar year of 1980.

3.

The Neclear Reactor Committee Annual Report for September 1979 to August 1980 as presented to the Dean of the College of Engineering is included in the following paragraphs.

Function, Activities, and Membership The Nuclear Reactor Laboratory staff and facility are administered through the Department of Mechanical Engineering of the College of Engineering at The University of Texas at Austin. The Nuclear Reactor Connittee is a requirement of the Nuclear Regulatory Commission and its function is to ensure that the nuclear reactor and its associated facilities are operated in a professional and safe manner.

This objective is met primarily be regularly scheduled quarterly meetings of the Nuclear Reactor Committee. These meetings include a review 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 6

t 4

any unusual occurrences. The connittee also reviews and accepts t

or rejects any special experiments or requested changes in the reactor i

technical specifications 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 r' actor facility, e

as these responsibilities lie with the associated faculty and professional f

staff of the Nuclear Reactor Laboratory.

1 l

Memoership on the committee consists of two categories: members-

{

and ex officio members. The committee members are appointed by the i

j Dean of the College of Engineering, usually after conferring with the i

l Director of the Nuclear Reactor Laboratory and the Chairman of.the j

Department of Mechanical Engineering. The members include faculty I

members having some. knowledge of nuclear engineering and reactor operation, but with no direct involvement in the operation of the 4

reactor facility.

In recent year one or two students have _been added to the committee. The members of the committee as of June 1980 are: Professors H. L. Marcus (Committee Chairman and on the Mechanical l

Engineering faculty), Joseph Ledbetter (Civil Engineering), Nolan Hertel (Mechanical Engineering), and M. Krause (student in Mechanical Engineering).

l The ex officio members are: the Chairman of the Mechanical Engineering Department (H.G. Rylander), the Director of the Nuclear Reactor Labora-l l

tory (Dale Klein), the Reactor Supervisor (T. Bauer), ~and the University j-Radiation Safety -(W. Bryant).

l Activities and Comments The recorded activities of the Nuclear Reactor Committee'and those itemt of busicess pertinent to the committee are included.in_the 1

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t minutes of the quarterly meetings, copies of which are attached. These include minutes for the meetings of July 30, 1979; October 30, 1979; January 30, 1980; and May 2, 1980. An additional meeting will be held this summer.

Specific items of interest include:

(1) The reactor has had its maximum usage during the reporting period. A wide range of applications-have been identified and vigorously pursued to increase the activity.

(2) A large number of personnel have received their reactor operator licenses. This has assisted in the increased usage of the reactor.

(3) The last NRC inspection showed no items of noncompliance.

(4) Separate funding for the facility has been approved and a request for facility improvenent funds is being processed.

(5) The operating organization has been modified and seems to be operating in a smooth, enthusiastic manner.

(6) The remodeling for security has started and should be vigorously pushed to completion.

In general we feel that this year has been the second consecutive strong year for the activities of the Nuclear Reactor Facility.

D.

Radiation Safety Committee 1.

Committee Composition Dr. P. Riley, Chairman (9/79 - 12/80)

Dr. L. O. Morgan (4/75 - 12/80) l Dr. Joanne Ravel (

- 8/79) l Dr. C. Desjardins (10/79 - 12/80) l Mr. H. W. Bryant, Ex Officio 2.

Meeting Frequency t

The Radiation Sa'...y Comnittee met twice during the calendar year of 1980 (/, ri 10 and November 12).

l 8

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i III. LABORATORY DEVELOPMENT

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A.

Organization Dr. Dale E. Klein continued as the Director during the past year.

Several changes of personnel classification and job requirements of the

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university personnel cleissification system have altered job descriptions

]

with a goal to increase job position effectiveness. Pasitions effected were the Reactor Supervisor, Radiochemist, and Technicians. Combined l

with the changes of job classification, several personnel changes I

occurred during the 1980 year. The responsibilities of reactor supervisor were assumed by Dr. T. L. Bauer and N. Povio accepted the position of

}-

Nuclear / Electronic Technical Specialist III. A graduate student M. Krause accepted as position as Nuclear Technical Specialist II to supplement the j

reactor operation staff.

B.

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

The Nuclear Engineering Teaching Laboratory's central feature is a Mark I TRIGA thermal fission reactor. Originally licensed by the Atomic l

Energy Connission 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 I

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 with a data acquisition system composed of dual Nuclear Data 1024 channel I

9

4 l

multichannel analyzers linked to a Data General Nova 800 minicomputer provided facilities for. analysis of large quantities of data.

Other experinental devices available at the Laboratory are a sub-critical assembly, a neutron beam irradiation facility, a curie cobalt-60 J

irradiator, a Nuclear Chicago sodium iodide coincidence counting system, 4

an n-6 detection system, and numerous other proportional and Geiger-Mueller l

detection and counting systems for radiation.

t 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 i

Nuclear Engineering Teaching Laboratory. Approximately 1000 persons tour 4

t 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, l

the Radiation Safety Committee and the Radiation Control Board of the State of Texas.

4 The use, operation, security and radiation monitoring of the Nuclear i

Radiation Laboratory is controlled by the Director of the Nuclear Engineer-~

ing Teaching Laboratory and the Radiation Safety Officer of The University l

of Texas at Austin.

i C.

Nuclear Radiation Laboratory i

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.

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The primary use of the building was to house and operate a 14 MeV Texas Nuclear neutron generator. To facilitate experiments utilizing the neutron generator, a large quantity of graphite was obtained,- machined and formed into a 8 ft. cube into which was inserted the drift tube of the neutron generator. This device is a very flexible one for investigating neutron migration in matter. When the Nuclear Engineering Teaching Labora-toryacquiredthree-(3) Californium-252sourcesfromLouisianaStateUniver-sity 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 252 the acquisition of Cf

, students and staff can perform experiments utilizing not only the high energy neutrons from the neutron generator 252 but fission spectrum neutrons from Cf In addition to the neutron generator and the Californium sources, other smaller radioactive sources are also used within the confines of the Nuclear Radiation 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 environ-ment from abnonnal radiation levels. Because of the possibility of high radiation doses within the confines of the neutron generator cavity, the Nuclear Radiation Laboratory is a limited access building and all generator i

l cavity doors are wired into the controls of the generator so that any unwarranted entry automatically shuts down the machine.

D.

Subcritical Facility i

In association with the undergraduate nuclear engineering laboratory course (ME 361F) and the graduate nuclear engineering course (ME 389R),

11 f

l the subcritical asser:bly has continued to provide a facility with which the student can perform recsurements that are related to fundamental reactor parameters. Such concepts as age, diffusion, and buckling are demonstrated in individual experiments perforced by each student.

E.

Neutron Activation Analysis facilities The Nuclear Analytical Laboratory has provided support for more than twenty separate projects ranging fron student laboratory support for advanced classes in chemistry, zoology, physics, and engineering to investigative projects in environnental 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 of the state, national and international level.

9 e

12

IV. Laboratory Operation and Utilization A.

Reactor 1.

Operation During this reporting period the reactor operated for a total of 184.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> while supporting numerous nuclear engineering and operation courses, research, and other related activities.

2.

Maintenance During 1980 nost maintenance was limited to routine repair and adjustments.

3.

Inadvertant Reactor Scrats During 1980 there were 17 inadvertant shutdowns as compared with 11 in 1979. Tables 1 and 2 itemize the

" SCRAMS" and compare this year's data to previous years' data.

4.

Utilization Tables 3 and 4 and Figures 4 and 5 show the utilization of the reactor for the year and compares this data with that of previous years.

5.

Courses Offered Using the Reactor Table 5 lists the courses offered at The University of Texas at Austin which utilized the reactor and associated facilities.

B.

Facility Changes 1.

Physical Security Several improvenents of the physical boundaries of the l

laboratory have been made or will be done in early 1981.

13 l

l

TABLE 1 REACTOR SCRAMS Intentional

-- 0 Operator Error

-- 4 Instrument Error -- 3 Power Outage

-- 0 Safety

-- 0 Total

-- 7 TABLE 2 COMPARIS0fl 0F YEARLY INADVERTAfiT SCRAMS

'63

'64

'65

'66

'67

'68

'69

'70

'71

'72

'73 10 9

3 4

3 31 15 11 13 6

10

'74

'75

'76

'77

'78

'79

'80 4

7 5

9 14 11 7

4 14

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I Al:11 I fiUCLEAP. ErlGifiEERifiG TEACitif1G LABORATORY l'Litl0lTAflCE DAT A,1980 I

Total llours Total fiumlier of Reactor in Burn-up Samples C?eration*

( LW-brs )

Irradiated Iirst Quarter 57 4,781.1 26 1980 Second Quarter 42.8 2,374.6 60 1980 Third Quarter 13.5 54.2 6

1980 fourth Ilud rter 70.8 4.613.5 58 1980 TOTAL 184.1 11,760.4 150

• Includes experimental setup time, maintenance, etc.

l 15 l

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+

TAfilf 4 COMPARISON OF PREVIOUS UTILIZATION OATA Total llours Tntal Number of Reactor in Burn-up Samples Operation *

(kW-nrs)

Irradiated Year 1965-66**

104.5 251 63 1966-67 150.0 595 202 1967-68***

342.6 28,168 2449 1968-69 260.8 49,985 1452 1969-70 222.0 36,477 1640 1970-71 262.5 53,912 2990 1971-72

???.R 38,624 1946 1973 318.6 45,794 1347 1974 226.1 27,641 778 1975 206.90',

20,450 363 1976 135.74 11,312 468 1977 139.29 7,509 164 1978 171.9 26,870 178 19/9 3!1.61 72,616 1568 1980 184.1 11,760.4 150

• 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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T/Bi f 6 COURSES UTILIZIfiG THE REACTOR AtlD ASSOCIATfD tar.IlITifS Lourse Nunber fourse 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 measu rement.

ME $389R A special projects laboratory course for foreign nuclear engineers.

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

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

ME 3P.9R A required laboratory course for students pursuing a Master of Science in the Nuclear Program.

Cil 376K A senior level course in instrumental analytical methods which utilizes the Nuclear Engineering Teaching Laboratory facilities to study Neutron Activation Analysis.

CE 390L This is a graduate course in environmental analysis for environmental health engineers.

Students use neutron activation analysis and energy dispersive.X-ray emission spectro-retry to analyze samples for toxic contaninants.

19

The mi.ior iteur, are t he replanwns of windows on two sides of the laboratory with concrete block and brir6...m.:en, tion.

2.

V_entilation System An exhaust has been partially installed to increase control of room and air pressure and air leakage rates.

A pre-filter, high efficiency particulate filter, and pneumatically controlled damper havi? been installed.

The damper was installed in the closed position until license modifications allow operation of the exhaust system. The fan, exhaust stack, and control system are to be installed in 1981.

V.

IAf!0RATORY INSPECTION A.

An inspection by a member of the Nuclear Regulatory Commission of the activities authorized by HRC Operating License R-92 occurred during April 16-10, 1980 in which no items of non-compliance were found.

B.

A visit by a member of the NRC regarding the renewal of

~

NRC Operating License R-92 occurred during July 9,1980 to cather infors'iation on the facility and license renewal.

C.

A visit by members of the NRC regarding activities authorized by NRC Special Nuclear Material License SNM-180 occurred during December 3,1980 in which information regarding the license renewal and use of licensed caterial was obtained.

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 1980, teachers participated in the program.

B.

Lectures and Presentations On numerous occasions during 1980 the NETL staff gave talks on subjects including: " Nuclear Reactor Safety," " Nuclear Engineer-ing and Society," "Research and Development of Energy Resources,"

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

C.

Tours and Radiation Monitoring During the calendar year of 1980 over 1,000 persons visited the lab. Most of these persons represented educational, civic, or industrial organizations, while others were part of formal engi-neering laboratory groups. All persons working in or around the laboratory are provided with personal radiation monitoring devices while tour group members are randomly monitored. Measurable ex-posure to tour group members was in the non-measurable exposure range as indicated by pocket dosimeters. Persons employed by or working in the laboratory are issued film badges. The annual statistical summary of those badges is found in Table 6.

21

TABLE 6 STATISTICAL

SUMMARY

OF RADIAT10fl EXPOSURE 1980 Range of Exposure flumber of in REM Individuals Non-measurable exposure 20 0.0 0.1 30 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

4 6

22

~.

r VII. RESEARCH ACTIVITIES The Nuclear Engineering Teaching Laboratory..is pursuing research o

.ir. numerous areas which are sponsored by the organizations listed below.

Major research funding is shown in Table 7.

4 A.

The U.S. Department of Energy has I!avided 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.

High 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 Biota."

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 sub-i contracted to the Nuclear Engineering Teaching Laboratory a part of a project on " Ecological Investigations of Petroleum Production Platforms. in the 4

Central Gulf of Mexico." The project was performed under SWRI's contract-4 with the Bureau of Land Development, Department'of the Interior No.- AA550-i' RP8-2. Most experimental work for 3WRI was performed in 1979 with some of the project concluded in and submitted to SWRI in 1980.

D.

Development'of a Preconcentration Method for Field Sampling o'f Uranium Personnel : Dale Klein, NETL Mohanced Ally, NETL Sponsored by: Nuclear Engineering Teaching Laboratory 23 s

_ _ _. ~,

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TABLE 7 RESEARCH FUNDING Texas Atomic Energy Research Foundation

$35,000 (5/1/79 4/30/81)

Department of Energy -- Fuel Program Center for Energy Studies 27,500 (9/1/80 - 8/31/81)

National Science Foundation (5/15/80 - 10/31/82) 39,975 Department of Energy (3/30 - 4/81) 14,000 Institute of Nuclear Power Operations (9/1/80 - 8/31/81) 8,000 TOTAL

$124,475 S

24

- a

==

Description:==

Two basic techniques are-used presently at 'the Nuclear

' Engineering Teaching Laboratory at The University of Texas-at: Austin

+

for the determination of trace elements (e.g. uranium). These include

.I neutron activation analysis and x-ray fluorescence. When the elements

.j to be examined are present in' trace quantities,.either a large. sample must be measured or the sample must be preconcentrated. There are several advantages of a preconcentration method and the objective of this project i

is to develop a suitable method for the analysis of trace elements, in-1 cluding uranium, in water. In previous years a method was developed for transition elements in water. Experiments were extended to Cr..Mn, Th and U.

E.

Preconcentration of Trace Elements in water for X-Ray. Fluorescence.

Analysis Personnel:

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

==

Description:==

In cooperation with the University of Monterey, Mexico, l

samples of water spiked with trace elements 'were prepared for analysis j

by X-Ray Fluorescence Spectronetry for several trace elements. Experi-5 ments were perforved by a group of students from the University of Monterey.

i F.

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

~l Pe_rsonnel :

A. H. Pradzynski..NETL

'~

Sponsored by: Nuclear Engineering Teaching Laboratory i

25

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==

Description:==

Previous work on determination of trace elements in' water by XRF and NAA was continued.

Investigation of a preconcentration. method-comprising APDC coprecipitation and pressure filtration was performed.

The investigation was extended to samples of waste water and industrial

~

ef fluent.

1 G.

Advanced Analytical Che;nistry - CH 376K I

Personnel:

J. Holcomb, Chemistry

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

==

Description:==

i Undergraduate students in chemistry performed qualitative

l and quantitative detenninations cf several elements in samples by neutron i

activation analysis. The program of the class included: (a) s' ample pre-paration and encapsulation, (b) two irradiations in the TRIGA reactor, one for long half-life and another for short half-life _ radioisotopes, '(c) measurements using a Ge-Li detector gamma spectrometer, (d) data processing using an on-line computer and (e) data evaluation and discussion of practical-applications of NAA in analytical chemistry.

H.

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' con-taminated lake, another toxic element, Se has been found in the samples.

Determinatiois of Se were done by Neutron Activation. Analysis and Gamma 26 1

s

. L :,,

4 Spectronetry. Results were prepared for publication. Further experiments will be performed.

1.

Analysis of Corrosion Material Accumulations on Structural Steel Personnel:

A. H. Pradzynski, NETL Sponsored by: School of Architecture (Professor W.H. Hilbertz)

==

Description:==

A steel grid samples showing accummulations of white corrosion products was examined by neutron activation analysis. Mg was determined quantitatively. Qualitatively Cl, Na, Mn and Cu were shown.

J.

Determination of Br in RNA Personnel :

A. H. Pradzynski, NETL Dr. B. Hardesty (Departrent of Chemistry)

Sponsored by: Department of Chemistry

==

Description:==

Bromine in samples of RNA conbined with cosine was determined by neutron activation analysis.

~

K.

Determination of Sb in Styrene Personnel:

A. H. Pradzynski, NETL Sponsored by: Department of Chemistry

==

Description:==

Sb was determined in styrene samples by neutron activation l

analysis. Gamma photons of Sb and Sb were used for quantitative determinations. This was a fesibility study.

27

4-

-!i L.

Construction of a large Benjamin Counter-i Personnel: Nolan E. Hertel, NETL.

Richard Savage, NETL Sponsored by: Texas Atomic Energy Research Foundation

~i

==

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 obtained with the detector filling

{

gas (methane or hydrogen) at various _ pressu'res, an unknown neutron energy 1

spectrum can be reconstructed. This detector will be used wit'h an existing l

l NE-213 spectrometry system to make possible neutron spectral measurements

/

l from 20 MeV down to approximately 10 kev. The two' detection systems will then be employed in fusion energy related neutronics studies.

1 H.

Measured Neutron and Gamma-Ray Spectra in a. Tissue-Equivalent Mediun j

Personnel: Nolan E. Hertel, NETL William E. ffurphie, NETL Sponsored by: Texas Atomic Energy _Research Founation i

Bureau of Enoineering Research-

/

i

==

Description:==

6-

. l l

An experimental fusion-neutron irradiation facility at Balcones-Research Center was used to measure neutron and gamma-ray fields in a tank of tissue-equivalent liquid. A neutron generator was used to produce 14-MeV neutrnns which impinge on one face of the tank. An NE-213 spectrometer was -

used to measure neutron and gamma-ray fluxes at various locations in the i_

T tank as a fune. tion of incident neutron flux. The project was useful in 4

assessing the neutron-induced gamma-ray spectrum in tissue as well as the quality of the neutron and gamma-ray doses. The results provided taforma-t tion of relevance in cancer radiotherapy as well as in the determination i

of dose equivalent indices due to fusion neutrons.

28 l^

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

t N. Measurement of Gamma-Ray Spectra Resulting in Tissue from i

Bombardment with Neutron Radiotherapy Beams i

Personnel: Nolan E. Hertel, NETL James B. Smathers, UCLA i

Robert G. Graves, University of Rochester -

}

i Sponsored by: National Institutes of Health: Public Health Service Grant CA12542 from the National Cancer Institute i

Mechanical Engineering Department f

==

Description:==

j 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 i

Variable Energy Cyclotron using an NE-213 spectrometer. Analysis of the measurements will help to determine ganina-ray spectral distribution in tissue during radiotherapy treatment. These spectral distributions are currently.

j being used to calculate the average gamma-ray energy as well as the average gamma-ray mass-energy-absorption coefficient.

O.

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 elet. tron volts (MeV). An effective means of per-forming 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 -

29

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 unfbiding codes to recon-struct unknown energy spectra. High-energy spectral measurements could be mam.e using this technique at neutron radiotherapy facilities and intense neutron source facilities such as fusion materials radiation damage facilities.

P.

An Analysis of the High-Level Waste-Streams from Fuel Cycles Using Fissile-Fuel Producing Fusion Reactors Personnel:

fl.E. Hertel, flETL J.W. Davidson, NETL-Sponsored-by: Texas Atomic Energy-Research Foundation j

==

Description:==

Fissile fuel may be produced or bred in fusion reactors by surrounding the fusion neutron source with a blanket containing a fertile material such as Th. The end product of neutron absorption 233 in this material is the fissile nuclide U which may be used to fuel-fission power reactors. A by-product of breeding this fuel is the -

j accompanying fission of the fertile and fissile materials. Both neutron l

capture and fission reactions produce radionuclides which would constitute a high-level waste stream similar to that from fission reactors. ' The fission level can be inaximized by appropriate blanket designs to increase the power of the fusion reactor; such a device is called a fusion-fission j

i l

hybrid. The fission level could be minimized to reduce fission product i' :.

30 5

1-j i;

)

--.--..--,-.--.-_----a-_._-a....

waste; this type of device would be a symbiotic fusion reactor. The fuel bred in either of these devices could be used to fuel existing fission reactors. The high-level waste streams from fuel cycles incorporating a fissile-fuel producing fusion reactor and its client fission reactors 2 Th 2330 fuel cycle.

are being investigated for the Q.

Modification of COBRA-4 Personnel: Dale Klein, NETL Tom Sanders, flETL Sponsored by: General Atomic Company Center for Energy Studies

==

Description:==

The transient version of the thermal-hydraulic computer code COBRA-4 is being modified. Considerable modifications have been nade to C08RA-4 to enhance its application for analyzing Gas Cooled Fast Breeder Reactor (GCFR) transients. This includes new numerical techniques to speed up calculations. Further analysis of the model is needed prior to the examination of long transient GCFR applications. This is the second year of a three-year project.

R.

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

==

Description:==

A thermal analysis using the computer code HEATING 5 is under-way to predict the temperature distribution in a nuclear fuel shipping cask.

Results fo m this detailed model will be compared with data from a full 31

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. This is the second year of a two year study.

S.

Heat Transfer through Randon Packed Beds by Using the Monte Carlo l'ethod Personnel : Dale Klein, NETL John R. Howell, Mechanical Engineering Sam Yang, NETL Sponsored by: Center for Energy Studies

==

Description:==

This study examines the constricted heat flow in packed beds of spherical particles. The packing pattern is obtained by a numericcl simulation that provides the bulk solid fraction, the contact-number frequency function and the angular distribution of contacting spheres.

The contact resistance is calculated by the Holm formula based on the packing simulation.

The effective conductivity can be determined by statistical methods. Results from this investigatior will be applied to a thermal analysis of a pebble bed nuclear reactor core.

T.

Heat Transfer and Friction Factor Analysis for Artifically Roughened Surfaces Persannel: Dale Klein. NFTI

~~~~~

J. Parker Lanb, tiechanical Engineering Mike Krause, NETL Gary Polansky, Mechanical Engineering Sponsored by: Center for E0ergy Studies National Science Foundation 32

4 i

==

Description:==

1 The proposed research is to determine the heat transfer and-friction characteris'scs for surfaces with discrete roughness geometry; Two major aspects are to be examined in that this is both an experimental and an analytical investigation. Values of R(h*) and G(h*) in the 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 valves surrounding discrete roughness elements.

A test assembly to examine artifically roughened surfaces is being-designed.

In addition, a new analytical method has also been developed to determine R(h*) and G(h*) values without making detailed velocity and teccterature profile measurements. Analytical predictions will be made utilizing funda-mental parameters in boundary layer theory coupled with the latest informa-tion on rough surfaces using integral techniques. Results from the experi-mental and analytical methods will be compared in order to gain insight as to the dominant mechanism involved for the use of discrete rough surfaces.

This research ves fundamental application for heat transfer augmentation.

Primary application incitdes heat exchangers and the Gas Cooled Fast j

Breeder Reactor (GCFR). The modeling will be directed towards the GCFR design conditions..This is the fourth year of a seven year study.

l U.

Structural Activation in Fusion Devices Personnel: Dale Klein, NETL Danny Smith, NETL i

Sponsored _by: Texas Atomic Research Foundation

==

Description:==

t The primary thrust of the current. work in the area of structure i

activation in fusion devices involves the development of capabilities for 33 i

l'

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

,,.__..,m.

' characterizing the neutron flux in the various regions of the devices to

~

be examined. Computer codes are available for one-dinensional 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 specific devices to be investigated, formulation of better metho'ds for characterizing -the poten-tial hazard of the radioisotopes generated and examination of techniques for minimizing the total hazard of the radioisotopes generated.

V.

Finite Elements in Radiative Heat Transfer in Asborbing/ Emitting Medium Personnel : Dale Klein, NETL Muhammad Razzaque~, NETL Sponsored by: Texas Atomic Energy Research' Foundation

==

Description:==

The transfer of heat through materials that attenuate radiation is 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 devicas of their associated heat transfer components'.

W.

Pebble Bed Breeding Blanket for a D-T Fusion Reactor personnel:

J.ll. Davidson, NETL Dale Klein, NETL Brian Gantt, NETL Sponsored by: Texas Atomic Energy Research Foundation

==

Description:==

An analysis is underway to examine the feasibility of incor-porating an advanced fuel handling scheme to the blanket region of a' hybrid 34

fusion reactor. The fuel is that used in a Pebble Bed Reactor (PBR) and both initial enrichment and regeneration of the fuel is being considered.

i The Th-232/U-233 fuel cycle used in the PBR would. require' a fresh or spent l

thorium feed to the hybrid blanket. The fertile material would be circulated through the blanket, removed, and returned to a position determined by both

'l the current U-233 concentration and the available neutron spectra and flux.

levels in the blanket. Problems involve integrating a pebble bed blanket to currently envisioned fusion reactor designs and determination of optimum.

recirculation schemes. Detailed neutronic analysis for the various blanket concepts will be made using computer codes presently available in the Nuclear Engineering Teaching Laboratory.

X.

Neutronic and Heating Analysis of Accelerator Targets and Blankets Personnel :

J.W. Davidson, NETL' Sponsored by: Texas Atomic Energy Research Foundation Center for Energy Studies

==

Description:==

Both the breeding of fissile material and the transnuation of high-level nuclear waste appear to be attractive uses for neutrons produced with accelerators. Neutrons produced through spallation reactions in an accelerator target offer potentially high source strengths at a modest energy input. Recent advances in accelerator technology should allow con-struction of smaller, lower cost accelerators with increased beam currents.

Calculation of the neutron transport in the target and surrounding blanket for incident particle energies of several hundred GeV require a complex computational ability. This research involves the development of a computa-tional package with which neutron and charged particle transport'in targets and neutron transport in blankets may be accurately determined in a coupled mode along with heat deposition rates in both regions.

3C

VIII. Publications From the Nuclear Engineering Teaching Laboratory K.L. Gilbert, " Neutron Flux Mapping of a Subcritical Reactor Core with-a Polyethylene Reflector", Masters Thesis, Physics Department, The University 1.

of Texas, 61 pp., June 1961.

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

J.M. Norwood, "The Point Source Transport Solution for the Position and Velocity Dependent Neutron Distribution in a Spherical Body of Non-Multiplying :

3.

Material", Masters Thesis, Physics Departmc.,t, The University of Texas, 75 pp.

June, 1962.

R.W. Reed, "Effect of a Cadmium Control Rod on the Neutren Densi y in a Subcritical Reactor", Masters Thesis, Physics Department, The University of 4.

Texas, 85 pp., August 1962.

P. Berananda, " Neutron Flux Distribution of a Subcritical Reactor _ Core with a Graphite Reflector".. Masters Thesis, Physics Dopartment, The University 5.

of texas, 40 pp., January 1962.

T.A. fredericks, " Thermal Neutror Flux Distribution Due to a Plane Wave 6.Source in and Unreflectal l<eactor As.mbly", M.mters Thesis, Physics Department, The University of Texas,107 pp., August 1961.

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

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

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

8.

R.D. O' Dell, "The Angular Thermal Neutron Spectrum in the Vicinity of the 9.Interface Between Two Media", Ph.D. Dissertation, The University of Texas,.

186 pp., January 1965,

10. B.E. Thompson, Sr.

" Cryogenic Neutron Spectra Measurements Across a Discontinuity in Temperature and Properties", Ph.D. Dissertation, The Univer-sity of Texas,149 pp., January 1965.

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

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

Health 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.

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. So_c., 11:2, 582 (November 1968).

22.

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

23.

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

24.

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

25.

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

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

26.

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

1969.

27.

M.'Gallardo, S.J. Gage, and D.f'. liarker, " 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, Physic:-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 Sympositsn 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, "Developnent 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_,495-49G,(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.

)

i i

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 Progranning",

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

41.

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

42.

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

Printed in Northern Ireland.

i 43.

G.D. Bouchey and S.J. Gage, " Neutron Radiography at The University of Texas Nuclear Reactor Laboratory", Isotopes and Radiation Technology l_,

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 Progranmed Associative Analyzer", Masters Thesis.

Mechanical Engineering (Nuclear Engineering), The University of Texas, December

.I l

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, "NAACOL--A Spectrum Analysis Routine for the Small Laboratory", 21st Mid-America Symposium on Spectroscopy, Chicago, Illinois (1970).

49.

S.J. Gage, G.D. Atkinson, Jr., J.B. Whitworth, and A.H. Pradz." ski, "Camputer-Aided Multielement Ganma Ray Analysis with a Compton Sule essed Ge(Li) Radiation Source", Ninth National of the Society of Appliec Spectros-copy, New Orleans, Louisiana, October 5-9, 1970.

50.

K.R.

faid, " Solid State Radiation Detection Devices: Fabrication, Techniques and Appluation 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.

1

52.

J.J. Chromik and E.L. Draper, Jr., " Energy Integral Tests of Differential Fission Cross Section Data", Trans. Am. Nucl. Soc., Vol

,13_, No. 2, p. 755 (1970).

53.

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

54.

E. Delkers, 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 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 Rescnance 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 Sptems", Masters Thesis, Mechanical Engineering Department,.

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

58.

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

59.

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

60.

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

(1971).

61.

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

62.

A.H. Pradzynski and S.J. Gage, " Nondestructive Identification of Material by Nondispersive X-Ray Fluorescence Spectroscopy using Si(Li) Detectors and Radioisotopic Sources", Proc. Eighth Symposium on Nondestructive Evaluation in Aerospace, Weapons Systems, and Nuclear Applications, San Antonio, Texas l1971).

63.

G.D. Atkinson, Jr., and S.J. Gage," Uranium Assay by Delayed Gama Ray.

Analysis Following Cf-252 Neutron Interrogation", Proc. Twelfth Annual Meeting Institute of Nuclear Materials Management, Plam Springs, Florida (July 1971),

I

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. Eitworth, G.D. Atkinson, and S.J. Gagc, "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. Bouchev, B.V. Koen, and C.S. Beightler, "The Optimization of Nuclear Systems by Geometric Prograntning, Nucl._ Sci.-and Engr. 44, 267-272 (1971).

69.

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

70.

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

71.

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

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

72.

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

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

73.

G.D. Bouchey and S.J. Gage, " Detection and Location of. Leaking TRIGA Reactor Fuel Elements", Nuclear Technology, 10, 211-214 (1971).

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., H, 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, ApriT 19-21.1971.

77.

G.D. Atkinson, Jr., J.B. Whitworth, and S.J. Gage, _" Computer-Assisted Analysis of Gama-Ray Spectra", Computer Physics Comunications, 2, 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-ti_ons, 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 19/1.

81.

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

82.

J.J. Chromik, " Experimental Determinatiun 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, I!ouston, Texas, November 5-6, 1971.

85.

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

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

86.

E. Linn Draper, Jr. and Andrzej 11. Pradzynski, " Identification of Alloys by Energy Dispersive X-Ray Spectroscopy", Ninth Symposium on Nondestructive Evaluation (1972).

87.

M.B. Owen, " Fuel Management Using Dynamic Programing", 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.

(19. J.I. Mar sfonalif. "lieuri'.I n 'I earnimi fontiof 1or Nucle.ir Reartors", Masters Ihe',i.. Methan b a i i nyince Ing liepar(ment, Ihe lloiveru Ly of icxas, 131 pp.

August 1972.

'Hl.

J. I r cin, "lhcoret o.al anil l xpes imental 1 valuation of Nuclear Data and Calculation 'echniques for fusion Reactor Blanket Design", Ph.D. Dissertation, lhe University of Texas, 210 pp., December 1972.

(:1.

S.G. Barbee, "Neutronic Calculatiore. in a ';imulated fusion Reactor Blanket", Masters Thesis, Mechanical Lnyineering Ocpartment,.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 Thennal Feedback Parameters for ai 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. Ilouchey, "Subcritical 1RIGA Reactivity Measurnnents lising t_he '.ourt.e Jert Technique", TRIGA Owner's Lonference II, College Stat. ion Iexas (19/2).

95.

G.D. Atkinson, Jr., and I. Linn Draper, Jr.

" Transient Rod failure in a Pulsing IRIGA Mark I Reactor", IRIGA Dwner's Conference 11, College Station, Texas (1972).

96.

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

57.

G.D. Atkinsoi, Jr., I.

l. inn tiraper. Jr., G U. I!outhey, and S.J. - Gage,

" Radioisotopic Source Amplification Using a lieterogeneous Subcritical Assembly",

Froc.18th Annual Meeting of the American Nuclear Society, Las Vegas, Nevada 3

(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 ?nd TRIGA Owner's Conference, February 19/7.

1

99. E.LinnDrapg,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 i

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 American 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 Instruct ion", Procmdinals of t hi Aerii an H+ 1Nr Sfe( lory " Applications of I.a l l ien n ism.".c" Hal inn.7 I lopi. al M. eq nig, :.epirmbri lI 13.-19/2.

~

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-l the ASME, New York, New York (1972).

104.

E. Linn Draper, Jr., "Tet hnological innova t mn and Assessment: A Novel Course for Nuclear Engineering", Winter Meeting of the American Nuclear Society,

'1 November 12-16, 1972.

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 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, s

p. 142-143, (1972),

r 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 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.

i 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 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 i*

Fusion Spectrum in Graphite", Trans. Am. Nucl. Soc., (1972).

i

114.

G.D. Atkinson, Jr., S.J. Gage, G.O. L'ouchey, " Cyclic Activation with a Cali fornium-257 ';ource". Tiurlear Te hnology (197?).

I t 's.

ti.D. At k inson,.h., "What hi. lw.i y s Wante<1 to Enow About Californium

^

Source l at il i t ies", invited Ppaer, Nat oinal lopi< il Meetinq on the Applicatforis of Cal if ornium-?5?, Aust in. Jew,(19/?)

116.

T.L. Bauer, G.D. Atkinson, Jr., "Distc;minetion Between Plutonium and Uranium by Gamia Ray Analysis Fol10 wino Cf M2 Interrogation", flational Topical Meeting on the Applications of Californiu"-IV, Tustin, Texas (1972).

1I/.

f. I inn Draper..fr,Iditor, Pren.vd iwr..!

lemas >ym y sium on the Tech-nology of Cont. rolled lhermonuclear l'usio(i_Exper_ir.ients and the Tngineering_

Aspects of Fusion Reactors, published by USALC.

118.

E. Linn Draper, Jr., Editor, Proceedinos of t he implications of Nuclear Power,in_Texat, publishod by the Texas Atomic Inorqy Research Foundation.

119.

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

Trans. Am. flucl. Soc. (1973).

120.

D.G. Anderson, f. Iinn Draper,..' r "I i.sion l's oduct Mass-Yield Measure-ments f roni Int encediate tnergy fleutron I mion of Plutonium-239 and Plutonium-241", Trans. Am. :lucl. Soc., 1973.

121.

E. Linn Draper, Jr., and Janes S. Frein, " Experimental Detennination of the Fusion Spectrum in Grarhi te", Trans. An. Thci. Soc.,,16,9,(1973).

122.

E. Linn Draper, Jr.. "fu'.ir.n Roartor I mi r, or iny in the fluclear Engineer-irej Cur rituluni a t The lin i.'er.i t y of ler-ai /w. t i n '*, I r,any Ani., f6c l. Soc.,.

li. 16 (19/3).

123.

E. Linn Draper, J, Theodore A. Parish, and Crian J. McArdle, "A Neu-tronic-Photonic Comparison of Vanadium and Niobivii Containing Fusion Reactor Blankets", Trans. Am. Nucl. Soc., (iiovember 1973).

124. John H. Vanston, Jr, "Use of Part it ive An ilytital Forecasting (PAF)

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

125.

Theodore A. Parish and i Iinn Draper, Jr., 'Neutronic and Photonic Analyses of Fusion Reac tor liianha. Containing ihnri:2ni, " I ilth Symposiim nn Engineering Problems of lusinn Rc*.oartli, Princet on, New Jer sey, Noveniber 5,1973.

l 126.

C.E. Locke and D.R. Paul, "Graf t Copolymer M:dification of Poly-ethylene-Polystyrene Blends. I. Graft Preparation and Characterization".

Journal of Applied Polymer Sc_ience, Vo!

17, pp. 2597-2617 (1973.)

7

127.

C.E. Locke and 0.R. Paul. "Gra t t r.opoi,w r Mmlifica' ion of Poly-erhylene Poly.Iyiene I:len.t.

Ii 1eop..tto-of M".l i t i e.1 I; t en.l. ". Jou r na l o f

' t i ce r. ", /ol. ti, pp. Ji'll-IDIO (19/ 8).

Apglj,n!,Polper 128.

J.P. Deen, " Moo.orement o f I i s i.a.11 odne i Yield. trom Thorium-232 in a

( a l i f or n inw 3? I i., ion Mon ti on '.pe. i rian", l'h.li. Ili.sertat ion, The Uni-versity of Texas at Austin, 141 pp., (Miy 197'i).

129.

L.D. Hansborough, "Overall Tritturi Considerations for Controlled Ther-monuclear Reactors", Masters Thesis, The U uversity of Texas at Austin, 154 pp. (Riy 1973).

130.

"M.L. Senglaub, "Li vss Section ',tudies Bastd on the Stat istical Model",

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

131.

I.1. inn ih aper, Jr. H.J. Voltiei, Ji.,

,1.1 Macdonald, C.T. Rombough, L.D. llansborough, 5.G. Ikirhee, and J.H. Vanston, Jr., "A University's In-volvement in Municioal Decision-Making on tiuclear Power", Trans. Am. flucl.

Soc.,(1973).

132.

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

Coal: An Economic Comparison of Power llant four m ir. i n T e x a s", T ra n s,._ Am.

' o<., (19/3).

Nuti.

133.

R.E. Henry, " Forensic Applications of fieutron Activation Analysis",

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

I _to.

(.. it At i in..,n

.h "Appie a' mer, of IFoi <. 9 A. I iva t son Ana lysis to the Life Sciente.", prosent ed a t tier hon,birn ! Me"! inq of the Texas Association for Radiat ion Resear ch an t

• out h I.cnt ra l I hot obiolog/ Group, San Marcos, Texas, fkwemla r 9 - 14, 19/t.

135.

5.P. Nichols, "f xperiment il 0"terminat ion et Neutron Fermi Age from Californium-?5? fis. ion Spects om 1 o ':.elnom Lover ed in<lium Re.onance in a Graphi te Medimi" Ma,ters Thesis. i he if r. i vei s i l.y o f lesas at Austin,101 pp.,

January 1974.

l 136.

T.A. P. irish, "Neuturnie and Phot onic Analyses of Limulated Fusion Reactor Blankets Containing Iborium and Natural Uranium", Ph.D. Dissertation, The University of Texas at Austin, 329 pp. January 1974.

137. J. li. Va n". ton, Jr, "the of t he l'a rti t ive An.ilyt ical forecasting (PAF)

Technique for Analysis of the Li f etts of Various f unding and Administrative Strategies on Nuclear f usion Power -lant Development", Ph.D. Dissertation.

The University of Texas at Austin, 459 pp., January 1974.

138.

E.M. B. Sorensen, "Themal Effects on the Biological Magnification of Arsenic in Green Sunfish, Lopomis Cyanellus", Ph.D. Olssertation, The Univer-sity of lexas at Austin, ?31 pp., Riy 19/4.

L

151.

W.lf. Smith, Jr., l' Iinn tiraper,.Ir., " Mea <.ured and Calculated Fast

.]

th utron *, pes.tra in a Graphite Medium". I rarr.. Am. Nut i. 'oc., 22, t100 (November 1975).

157. - J.W. Ilavi P.on, I. I inn' Uraper, Jr.. "Ge.t' f or Part illoning Strategies involved in liigh-level Nuclear Waste Management", Irans. An. Nucl. Soc., 22, 348 (November 1975).

"* en'.it iv ity of Total fuel' Cycle.

153. M.J.-Voltin, Jr.. I

1. inn tiraper, Jr.,

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 liigh 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.f. 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.

11.F. Bulla, E. Linn Draper, Jr., R.E. Ilenry, M.J. Voltin, Jr., et.al'.,

Texas _ Nuclear Power Polities: A Study _of Alternatives, Volume II: Methodology.

The University of Texas at Austin Center for Energy Studies, Policy Alternative-Study No. I (1975).

158.

A.H. Pradzynski, R.E. llenry, 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 li. Pradzynski, R.E. Henry, J.L.S. Stewart, " Nondestructive Determination of Toxic Elements in Inys", Proc. of 10th Symposium on Nondestructive Elements, San Antonio, Texas, 257-765(April 23-25,1975).

160.

R.E. llenry, " Determination of ppb l evels of Selected Elements 'in Natural-Water Using Radiosiotope-Lxcited 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).

8 161.

S.I'. Nichuis, " Application of the Partitive Analytical Forecasting (PAF)

Technique = to the United States Cnntrolled 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).-

9 163.

J.L. Macdonald, " Investigation of Pat tern Recognition Techniques for the

'~

Ident 11 le at inn nt '.plilI ine: '.n r 1.u e. in Monte I.arin Part itle Ironsport 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 L. I inn Draper, Jr.:, "The Minimization of the llazard Resulting from Transmutation of Fission Products," Transactions -

of the American Nuclear Society, 23, 59, June 1976.

3 166.

T. A. Parish, " Fusion-Fission liybrid 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 1129," Second ANS Topical Meeting on the Technology of Controlled Thermonuclear Fusion, Richland, Washington, September 1976.

l 168.

T. A. Parish, J. W. Davidson and J. 3. Cornwell, "The Effectiveness of i

a Sr90 fusion Reactor Transmutation Waste Management Program," Transactions of the American Nuclear Society, 24, November 1976.

i 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, 32, 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 Preconcentri. tion and Radinisotope 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.

172.

A. H. Pradzynski, R. E. Henry and E. L. Draper, Jr., "Detennination'of Trace Elements of Hydrogeochemical Prospecting by APDC-Coprecipitation and X-Ray Spectrometry," invited paper at The International Conference on World Nuclear Energy a Status Report. Transactions of Am. Nuclear Society, 24,

~~~

1976, p. 119.

173.

R. R. Gay, G. F. Brockett and R. T. Johnson, "Two-Phase Flow Measurement Techniques for Nuclear Safety Research," Two-Phase Flow and Heat Transfer Symposium-Workshop, Miami Beach, Florida (1976).

174.

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

l i

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.

g 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 an'd R. Ramirez-Mitchell, " Time Dependent Localization of Arsenic in Subcellular Hepatocyte Fractions," J. of Patholooy 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.

4 180.

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

4 33, November 1979, 182.

S. A. Hodge, J. P. Sanders, and D. E. Klein, " Determination of Friction c

Factors and Heat Transfer Coefficients for Flow Past Artifically Roughened Surfaces, Oak Ridge National Laboratory Report, ORNL-5599, November 1979.

I 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 i

Generation," Council on Energy Resources, The University of Texas at Austin, i

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, i

November 16-17, 1979, i

186.

A. H. Pradzynski, " Determination of V and Ba in Marine Sediments and l

Biota," Internal Report, Nuclear Engineering Teaching Laboratory, The University of Texas at Austin, Department of Mechanical Engineering (1979).

187.

N. E. Hertel, B. W. Wehring, and J. J. Dorning, " Integral Test of l

ENDF/B-IV High-Energy Neutron Cross Section Data for Tungsten," Trans. Am.

Nucl. Soc. 32, 631 (1979).

i h

188.

R. H. Johnson, K. R. Koch, B. W. Wehring, and N. E. Hertel, "TOL 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.

191.

N. E. Hertel, B. W. Wehring, " Absolute Monitoring of DD and DT Nuetron Fluences Using the Associated-Particle Technique," Nucl. Instr. Meth. 172, 501(1980).

192.

S. A. Hodge, J. P. Sanders, and D. E. Klein, " Slope and Intercept of the 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 Sources," Trans. Am. Nucl. Soc. 35, 457 (1980).

194.

N. E. Hertel, W. E. Murphie, and R. J. Calhoun, " Measurements of Neutron and Gamma-Ray Spectra in a Phantom Irradiated with 14-VaV Neutrons " to be presented at the Health Physics Society Annual Meeting, Louisville, KY, June 21-26, 1981.

195.

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

196.

D. E. Klein, "ANS Student Involvement in Public Information-The University of Texas at Austin," Trans. An. 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.

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 Railcar/ Cask System, " Paper #147. PATRAM-80, West Berlin, FRG., Nov.1980.

199.

M. A. Ross and D. E. Klein " Synthetic Fuel Production Utilizing Texas Lignite and a VHTR for Process Heat," Trans. Am. Nuclear Soc., 31., Nov.1980.

.