ML20210G424

1985 Annual Rept of Univ of Texas at Austin,Nuclear Engineering Teaching Lab

ML20210G424
Person / Time
Site:	05000192
Issue date:	12/31/1985
From:	Bauer T TEXAS, UNIV. OF, AUSTIN, TX
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 8604020480
Download: ML20210G424 (76)

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NUCLEAR REACTOR LABORATORY TECHNICAL REPORT THE UNIVERSITY OF TEXAS COLLEGEOF ENGINEERING DEPARTMENT OF MECHANICAL ENGINEERING d

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I 1985 ANNUAL REPORT of The University of Texas at Austin Nuclear Engineering Teaching Laboratory January 1, 1985 - December 31, 1985 D.E. Klein, Director T.L. Bauer, Supervisor Taylor Hall 104 512/471-5136 January 1986

1985 TABLE OF CONTENTS List of Tab 1es...................................

3 List of Figures..................................

4 I.

Introduction.....................................

5 II.

Laboratory Administration A.

Organization................................

9 B.

Personnel C.

Committees D.

College Report III. Laboratory Development..........................

14 A.

Organization B.

Nuclear Engineering Teaching Laboratory C.

Nuclear Reactor ~ Laboratory D.

Neutron Activation Analysis Laboratory E.

Nuclear Radiation Laboratory IV.

Facility Operations Summary.....................

18 A.

Operating Experience B.

Reactor Shutdowns C.

Reactor Utilization D.

Reactor Maintenance E.

Facility Changes F.

Area Radiation Surveys G.

Radioactive Effluents and Waste V.

Laboratory Inspections...........................

30 A.

NRC Inspections B.

TDH Inspections VI.

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

31 VII. Research Activities.............................

32 VIII.

Publications from the Nuclear Engineering Teaching Program...........................

43 2

1985 List of Tables Table h -

h 1.

Administration and Committees 11 2.

Facility Personnel 12 3

University Courses 17 4.

Reactor Safety System 19 5.

Safety System Events 19 6.

Performance Data 20 7

Annual Utilization Data 21 8.

Summary of Personnel Radiation Exposures 25 9.

Radiation Exposure Groups 25 10.

Laboratory Radiation Levels 26 11.

Laboratory' Contamination Levels 26 12.

Environmental Surveys

-27 13 Monthly Gaseous Waste Discharge 28 14.

Monthly Liquid Waste Discharge 29 15.

Monthly Solid Waste Disposal 29 16.

Research Funding 33 3

1985 List of Figures Finure h h

1.

Site Location of Nuclear Engineer *ng Teaching Laboratory 7

2.

Floor Plan of Nuclear Engineering Teaching Laboratory 8

3 Organization Chart of the Nuclear Engineering Teaching Laboratory 10 4.

Annual Burnup versus Operation Year 22 5.

Samples Irradiated versus Year 22

1965 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 CPR 50.59.

The report covers the period _from January 1,

1985 to December 31, 1985.

The Nuclear Engineering Teaching. Laboratory (HETL) is a part of the Mechanical Engineering Department in the College of Engineering at The University of Texas at Austin.

The program's major equipment consists of a 250 kW TRIGA !! ark I reactor operated in pulsing and steady state modes.

The Nuclear Reactor Laboratory and Neutron Activation Analysis Laboratory areas, shown in Figures 1 and 2,

are located in Taylor Hall on the main university campus.

A Nuclear Radiation Laboratory for other types of experiments is located in another building on the main campus.

Equipment maintained by the NETL program includes a Cockcroft Walt'.4 14 AeV neutron generator, a Lockheed Aerojet s u b c r i ' '. c a l assembly, a 9250 curie co-60 irradiator and 150 k.ovolt industrial X-ray source.

Also available are isotopic neutron sources that include three californium-252 c.arces and six plutonium-beryllium sources and reference s - acces for instrument calibrations.

A wide array of detect s and electronic equipment are available to provide meas.. ament and analysis capability of laboratory produced or maintained radiation sources.

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

A major planning effort, to move the location of the laboratory activities, was initiated during the 1984 calendar year and continued through the 1985 calender year.

The project plans to move the facility location from The University of Texas at Austin main campus to the Balcones Research Center (BRC).

The proposed move is in response to needs for expansion of other educational programs and facilities on the main campus and the development of the research center as a major research and engineering site.

Submittal was made to the Nuclear Regulatory Commission (NRC) in November 1984 for the approval of the new facility location.

An NRC site visit in January 1985 and subsequent evaluation of the license application resulted in the issuance of a construction permit in June 1985.

Preliminary architectural and engineering plans were approved by The University of Texas System Board of Regents in July 1985.

Plans are to complete final drawings and specifications by architects and engineers, obtain regents approval and award of funding in 5

1985 the-spring of 1986.

Facility completion is scheduled for 16-18 months after start of construction.

Fuel elements from the dismantling of the Northrup Aircraft Division TRIGA were obtained by donation during the 1985 year.

Two shipments consisting of a total of 58 elements were added to the fuel inventory'as replacement fuel and supplemental fuel for the proposed facility planned operation at 1.1 Megawatts.

Decommission and dismantling plans for the Taylor Hall facility were submitted in May 1985.

Actual decommission and dismantling work is scheduled to occur after the the movement of key components from the Taylor Hall site to the

~

Balcones Research Center site upon completion of the proposed facility.

The Balcones Research Center facility will provide laboratories for the TRIGA reactor, neutron generator, radiation measurement, preparation and processing of radioactive samples, and office space.

Although the facility move consists primarily of moving the present TRIGA facility and other program activities into a single-building at the Research Center, several improvements to the-reactor facility are planned to extend facility capability.

These include above ground shield structure for access to horizontal beam tubes, and increased power and pulse parameters.

Plans are to utilize the present fu'el and move some other components from the old to the new facility.

Many of the components such as reactor structure, and instrumentation and control system are to be replaced.

A few components such as control rod drives will be reconditioned.

6

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9985 II.

LABORATORY ADMINISTRATION A.

Organization The present organizational chart of the NETL program is presented in Figure 3 Budgeted NETL staff funding is provided for a Supervisor / Assistant Director, research associate, technician / operator, operator, and secretary.

Budget support is divided into full time positions for supervisor, technician and research associate; half time for an operator; end quarter time for a secretary.

B.

Personnel Personnel associated with the laboratory consist of NETL staff, faculty, students, and certain other university personnel.

The personnel involved in the NETL program during the past year are summarized in Table I.

C.

Standing Committees Two committees monitor the activities of the NETL programs.

The Nuclear Reactor Committee functions through the College of Engineering and the Radiation Safety Committee functions through the Office of the President.

1.

Nuclear Reactor Committee The Nuclear Reactor Committee convened to review the activities related to facility operation during each quarter of the calender year.

Committee meeting dates were April 29, July 16, October 31 and January 20.

The committee composition is shown in Table 2.

Committee responsibilities are the reac*or operation, associated facility activities and engineering programs.

2.

Radiation Safety Committee The Radiation Safety Committee convened to review radiological safety practices at the university during each academic term.

Committee meeting dates were April 3 and November 7 The committee composition is shown in Table 2.

Committee responsibilities are the activities of university research programs that utilize radiation source caterials.

9

1985 Office, President University of Texas at Austin Radiation Safety Committee Executive Vice President and Provost Dean College of Engineering Nuclear Reactor Committee Chairman Department of Mechanical Engineering l

Director

, Nuclear Engineering, Teaching Laboratory Supervisor L.

Reactor

_J Operations Responsibility Communication Figure 3 Organization Chart of the Nuclear Engineering Teaching Laboratory 10

1985 Table 1 Administration and Committees Administration The University'of Texas System Board of Regents Chairman Jess Hay Vice Chairman R.B.

Baldwin III Vice Chairman S.H.

Ratliff Executive Secretary A.H.

Dilly Member (1987)

Member (1989)

Member (1991)

J.S.

Briscoe R.B.

Baldwin III J.S.

Blanton B.B.

Hilburn Jess Hay S.H.

Ratliff T.B.

Rhodes Mario Yzaguirre Bill Roden Chancellor Hans Mark The University of Texas at Austin President (app. 9/1/85)

William H.

Cunningham President (term. 8/31/85)

Peter T.

Flawn Executive Vice President and Provost (app. 9/1/85)

Gerhard J.

Fonken Vice President for Academic Affairs and Research (term. 8/31/85) Gerhard J.

Fonken Dean of the College of Engineering Earnest F. Gloyna Chairman of the Department of Mechanical Engineering Grady H.

Rylander Nuclear Reactor Committee Chairperson:

H.

L. Marcus (app: 9/1/77)

Member:

N.

E.

Hertel (app: 4/1/79)

Member:

D.

E.

Klein (app. 9/1/77)

Member:

J.

O.

Ledbetter (app: 9/1/71)

Member, student:

R.

D. Manteufel (app: 9/1/85)

Member, student:

N.

D. Poor (term: 8/31/85)

Ex officio member:

T.

L.

Bauer (app: 6/1/78)

Ex officio member:

H.

W.

Bryant (app: 11/1/73)

Ex officio member:

E.

F. Gloyna (app: 4/1/70)

Ex officio member:

H.

G.

Rylander (app: 9/1/76)

Radiation Safety Committee Chairperson:

E.

L. Sutton (app: 9/1/84)

Member:

K.

J.

Caskey (app: 9/1/83)

Member:

G.

W. Hoffman (app: 9/1/84)

Member:

D.

E.

Klein (app: 9/1/83)

Member:

S.

A.

Monti (app: 9/1/85)

Member:

L.

O. Morgan (app: 4/1/75)

Member:

R.

L. Shipman-(term: 8/31/85)

Ex officio member:

H. W. Bryant (app: 11/1/73)

Ex officio member:

W.

H.

Cunningham (app: 9/1/85)

Ex officio member:

P.

T. Flawn (term: 8/31/85) 11

D 1985 Table 2 Personnel Facility Personnel Staff Director D.E.

Klein Assistant Director / Supervisor T.L.

Bauer Research Associate F.Y.

Iskander Nuclear Technical Specialist M.G.

Krause Nuclear Technical Specialist D.H.

Eppes Administrative Secretary B.J.

Babich Sunoort Personnel Safety Personnel Safety Coordinator H.W.

Bryant Radiation Safety Specialist L.W.

Hamlin 23 searchers College of Engineering T.L.

Bauer Nuclear Reactor Lab.

F.Y.

Iskander Neutron Activation Lab.

N.E.

Hertel Nuclear Radiation Lab.

Assoc. Prof.

University Departments E.M.B. Sorenson Pharmacy Assoc. Prof.

Students Graduate Assistants M.

Ally A.

Gaines L. Grater R.

Hartley E.

Ibrahim B.

Kolda A.

Patterson-Hine N.

Poor R. Savage D.

Smith Student Assistants R.

Clements C.

Dameron L.

Pooser J.

Evans 12

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Y 1985 ~

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Report to the' College of Engineering Each year the Reactor Committee provides a report.to the

Dean of the College of Engineering describing activities of the committee and a review or assessment of the operation of specific portions of the NETL program concerning the reactor and other radiation producing equipment.

Harris Marcus, Reactor Committee Chairman, summarized the activities during this period saying, "A great deal of enthusiasm exists within the Nuclear Engineering Teaching Laboratory in spite of the extensive-paperwork load associated with the proposed move to B.R.C.,

The program has again completed a busy, successful year."

s Specific items of interest included:

1)

The main effort in the program was associated with the development of a new reactor facility at Balcones Resea'rch Center.

A plan has-been developed and preliminary work with NRC personnel has progressed in an orderly manner.

The next few months should lead to approval to proceed to build the new reactor facility at B.R.C.

2)

Northrup donated 59 partially used fuel elements for use in the TRIGA facility.' The transfer of the fuel over two separate delivery dates was well organized and proceeded'with no incidents.

3)

The reactor remained operating efficiently while the rest of Taylor Hall was being torn down around it.

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13 l

1

1985-III.. LABORATORY DEVELOPMENT A.

. Organization Dr. Dale E.

Klein continued as the Director.and Dr.

Thomas L.

Bauer continued as Reactor Supervisor / Assistant Director during the past year.

An administrative change in the Office of the' President replaced Peter T.

Flawn with William H.

Crtningham.as President of The University of Texas at Austin and assigned Gerhard J.

Fonken as. Executive

-Vice President and Provost.

Appointments of part time staff during the year included two. temporary short term student appointments and a longer term appointment.

All facility staff positions became complete with the appointment of R.

Clements as a Laboratory Research Assistant.

Mr. Clements has previous licensed operator experience and should provide an asset to the future program goals of the facility.

Other staff personnel remained unchanged.

One change in the Nuclear Reactor Committee replaced' the-student member on committee.

Other key faculty and university support personnel remained unchanged.

~B.

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

The Nuclear Engineering Teaching Laboratory's central feature is a Mark I TRIGA thermal fission reactor.

Originally licensed by the Atomic Energy Commission to operate at 10 KW in 1963, the nuclear reactor and the associated laboratory equipment have been updated over the past years and the research capabilities of the Laboratory are now more diverse.

In 1968, the facility license was amended to allow the TRIGA reactor to operate at a steady state power level of 250 kW which increased experimental capabilities.

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

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

One of the functions of the nuclear reactor and its associated equipment has been to teach and demonstrate the fundamentals of reactor operation.

Another function has been the demonstration of specific applications of nuclear technology.

Several organized classes routinely utilize the' 14

1985 reactor. facility.

Courses utilizing the reactor and associated facilities are listed in Table 3

Classes, organizations and groups are provided tours or demonstrations of the reactor and its associated experimental. facilities.

Approximately 850 persons were admitted into the reactor facility during the past year.

The use, operation, regulation and inspection of the Nuclear Engineering Teaching Laboratory is controlled by the United States Nuclear Regulatory Commission, the Nuclear Reactor Committee of The University of Texas, the Director of the Nuclear Engineering Teaching Laboratory, the Radiation Safety Committee and the Texas Department of Health Division of Radiation Control.

C.

Neutron Activation Analysis Laboratory The Neutron Activation Analysis Laboratory has provided nuclear analytical support for individual projects ranging from student project support for classes to measurements for faculty research projects.

Stu' dent project support is in the areas of engineering, chemistry, physics, geology, biology, zoology, and other areas.

Research project support includes elemental measurements for environmental and investigative research projects.

Scientific articles based upon the results of sponsored and non sponsored research by this laboratory have been published or accepted for publication in several journals and proceedings, and have been presented at conferences at.the state, national and international level.

Radiation measurement systems available include gamma ray spectroscopy with HpGe detector and microcomputer controlled acquisition and analysis system, Si(Li) detector and multichannel analyzer for X-ray measurements, alpha-beta proportional counter, scintillation detectors, neutron detectors and associated electronic modules to accomplish several types of standard nuclear measurements.

An

~important function of the laboratory is to support various research applications with the neutron activation analysis method or other techniques related to nuclear radiation measurements.

D.

Nuclear Radiation Laboratory The Nuclear Radiation Laboratory is utilized by staff and students of the Nuclear Engineering Program at The University of Texas at Austin.

The laboratory is located in an area of the Engineering Science Building.

A 14 MeV Texas Nuclear neutron generator is the main feature of the laboratory.

Three californium-252 neutron sources are also available for use.

The facility, with installed shielding, provides an area where students and staff can perform experiments utilizing not only the high energy neutrons from 15

1985 the neutron generator but fission spectrum neutrons from Cf252.

In addition to the neutron generator and the californium sources, other smaller radioactive sources are also used'within the confines of the Nuclear Radiation Laboratory.

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1985 Table 3 Cour'ses Utilizing the Reactor and Associated Facilities Course Number Course Description Mechanical Enrineerine Denartment ME 361F Introductory Nuclear Laboratory -

studies in radioactive decay, activation, detection and measurement.

ME 361G Reactor' Operations - studies in nuclear reactor parameters, instrumentation characteristics and regulation.

ME 377K Projects in Mechanical Engineering -

individual study and experiment projects for undergraduates.

ME 389R Nuclear Engineering Laboratory -

studies for graduate students in r.uclear methods in measurement and analysis.

ME S389R Special projects course for nuclear engi1eering laboratory studies as a summer course for foreign students.

ME 397 Current Studies in' Engineering -

special projects course for graduate study of selected topics.

Additional Courses in Other Denartments GEO 388L Isotope Geology - graduate course CH 376K Advanced Analytical Chemistry -

senior level course in instrumental and analytical methods.

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

17

1985 IV.

Facility Operations Summary A.

Operating Experience During the period no significant deviations from normal operating conditions were observed.

Pulse reactor operation remains suspended until proper operation of the removed uncompensated ion chamber is confirmed or an appropriate substitute is installed.

Established operatinE procedures and other required procedures remained unchanged.

Licensed activities were performed by two persons with Senior Operator Permits, T.L.

Bauer and M.G.

Krause.

Operating activities were in support of reactor operations, nuclear engineering, sample irradiations, research and education or demonstrations.

No new experiments were proposed or approved.

Excluding operation for demonstration, instruction or routine surveillance, the major experiment performed was neutron activation to support various research activities.

Maintenance during the period consisted primarily of routine equipment repair and adjustments.

B.

Reactor Shutdowns Reactor shutdowns (scrams) occurring during the reporting period are summarized in Table 4,

categorized according to the type of initiating event.

Safety system scrams are protective actions to shutdown the reactor that are caused by the proper operation of the safety system but are not the result of an operator error or an intentional action of the operator.

Operator error scrams are the result of judgement errors or procedural errors.

Instrument and power failure scrams are protective actions that result from loss safety system function.

Intentional scrams are operated initiated scrans such as tests.

Manual action scrams are classified either safety or intentional as determined by the cause of the manual scram action.

Inadvertent scrams are all unintentional shutdowns of the reactor by the protective action of the safety system.

Table 5 compares the number of inadvertent shutdowns during this reporting period to previous reporting periods.

18

1985 Table 4

. Reactor Safety System (scrams)

Safety System 0

-Operator Error-0 Instrument Error 2

Power Failure O

Subtotal 2

Intentional 6

Total 8

Table 5 Safety Systen Events (inadvertent) 1970-11 1980 7

1971 13 1981 7

1972 6

1982 6

1963 to 1973 to 1983 6

1964 9

1974 4

1984 5

1965 3

1975 7

1985 2

1966 4

1976 5

1967 3

1977 9

1968 11 1978 11 1969 15 1979 12 19

1985 Table 6 Performance Data 1985 Reactor Operation Hours, Fuel Burn-up and Irradiated Samples Quarter Reactor Total Burn-up Samples

. Operation Fuel Irradiated (hours)

(kw-bra)

(number)

First 46.7 4985 106 Second 48.8 6945 183 Third 18.0 2720 61 Fourth 26.4 3957 123 Total 139.9 18607 273 Notes 2 (1) Reactor operation hours record'the console key on time or the time power is applied to the rod control system.

(2) One full power hour is 250 kilowatt-hours.

(3) Samples t' hat are irradiated in the experimental facilities of the reactor such as the RSR, PNT or CT.'

20

~

1985 Table 7 Annu'al Utilization Data I.aAc Reactor.

Total Burn-up Samples Operation Fuel Irradiated (hours)

.(kw-bra)

(number) 1967 154.5 846 265

'.1968 342.6 28168 2449 1969

.260.8 49985 1452 1970 222.0 36477 1640 1971 262.5 53912 2990

'1972-222.8 48389 1946 1973 318.6 45794 1347 1974 226.5 27641 778 1975 207.0 20450 363 1976 135 7 11312 468 1977 139 3 7509 164 1978 171 9 26870 178 1979 311.6 72616 1568 1980 184.1 11760 150 1981 258.5 18165 330 1982 247.6 16150 294 1983 260.2 24028 477 1984 179.6 24806 667 1985 139 9 18607 473 Total 4245 7 543485 17999 Note r-(1) Data for 1967 includes all data recorded for previous operation at 10 kW from 1963-1967.

(2) Operation power of 250 kilowatts was initiated in 1968.

21

1985

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Figure 5' Samples Irradiated versus Year

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1985 C.

Utilization Reactor utilization. data for this reporting period is summarized in Table 6.

A summary of reactor utilization since initial criticality is shown in Table 7.

Bar graphs comparing annual burnup and quantities of samples irradiated since initial criticality are shown in Figures 4 and 5.

D.

Maintenance During this reporting period maintenance consistei primarily of routine repair and adjustment.

E.

Facility Changes Operation of the reactor in the pulse mode has been discontinued until the operation characteristics of the compensated chamber as related to~ pulsing is established.

This evaluation is a low priority since current activities of the facility do not require pulsing and future facility operation will be reevaluated in relation to the new facility proposal.

The acquisition of fuel included the installation of additional fuel storage racks in the reactor pool.

Four two section racks with a total of twelve elements each were in installed.

Eight single section racks provide the necessary storage for the remaining fuel elements, temporary storage for fuel removed from the reactor core and storage for other core components.

23

1985 F.

Radiation Exposures A summary of radiation exposures during this reporting period to facility personnel, students, and visitors is shown in Table 8.

The average exposure per individual and the greatest exposure per individual for each group is summarized in Table 9.

No exposures in excess of the limits of 10CFR20 occurred during this period.

G.

Area Radiation Surveys An annual summary of the normal radiation levels measured in the laboratory is shown in Table 10.

The results of routine surface and pool water contamination surveys are summarized in Table 11.

Environmental surveys performed outside the laboratory are summarized in Tab 2o 12.

H.

Radioactive Effluents 1.

Gaseous Wastes Gaseous discharge during the reporting period is limited to leakage of Ar41 from the reactor laboratory.

The total estimated amount of radioactivity released was calculated based on experimental data.

Measurements indicate the equilibrium concentration of Ar41 is 4x 10^-8 Ci/m3 Estimate of the release is calculated from the monthly number of full power hours operated during the period.

Although L - leakage from the laboratory is restricted, an effectivo air change rate of two per hour (.36 m3/sec) is sasamed with dilution at the release point (.14 sec/m3).

A summary of the calculated radioactive gaseous discharges during the reporting period is presented in Table 13 2.

Liquid Waste No liquid radioactive waste was discharged durirg the reporting period.

Efforts are made to avoid liquid waste disposal by appropriate evaporation or absorption techniques for small volumes and purification by resin treatment for large volumes.

3 Solid Waste The activity and amounts of solid waste discharged during the reporting period are summarized in Table 14.

All solid waste materials were packaged and shipped, along with radioactive waste generated in other departments, by the Safety Office.

Waste shipments are performed by Isotex. Friendswood, Texas.

24

1985 Table 8 Summary of Personnel Radiation-Exposures inng.R n1 Ernosurg in RQ[

Number g1 Individuals Staff Students Visitors No measurable exposure 7-18 869 Measurable exposure less than 0.1 1

1 0

0.1 0.25 0

0 0

0.25 - 0.5 0

0 0

0.5 - 0 75 0

0 0

0 75 - 1.0 0

0 0

Table 9 Radiation Exposure Oroups Ernosure agr, Ir dividual in Kram Groun Avernae Greatest Staff 10 10 Students 10 60 Visitors 10 10 25

r 1985 Table 10 Laboratory Radiation Levels Location Average (mR/hri Maximum (mR/hr)

Control Console Area 2x10^-3 3x10^-2 10 ft. from core axis 6 ft. above pool Water System Area 1x10^-2 1x10^-0 12 ft. from core axis 4 ft. above pool Above Core 2x10^-1 2x10*+1 0 ft. from core axis 16 ft. above pool Table 11 Laboratory Contamination Levels Location average Maximum Floors 25 dpm 110 dpm Surfaces 25 dpm 40 dpm Pool Water 200 pCi/l 4850 pC1/1 l

26

1985 Table 12 Environmental Surveys Location Averace Maricum 1

.01

.01 2

.01

.01 3

.02

.02 4

.01

.01 5

.01

.01 6

.01

.01 7

9 pei/1 41 pci/1 27

1985 Table 13 Monthly Gaseous Waste Discharge (argon-41)

Month Isotope Total Point of Release Percent of Release Concentration Maximum (uC1)

-(m"3)

(pCi/m"3)

(5)

Jan Ar-41 420 10500 22

.06 Feb Ar-41 420 10400 22

.06 Mar Ar-41 200 4900 11

.03 Apr Ar-41 620 15400 33

.08 May Ar-41 750 18700 40

.10 Jun Ar-41 60 1400 3

.01 Jul tr-41 10 300 1

<.01 Aug Ar-41 150 3700 8

.02 Sep Ar-41 410 10100 22

.06 Oct Ar-41 10 300 1

<.01 Nov Ar-41 620 15400 33

.08 Dec Ar-41 200 4800 10

.03 Annual 3870 95900 17

.04 Monthly Gaseous Waste DischarSe (gas or particulate)

Month Isotope Total Point of Release Percent of Release Concentration Haximum (uci)

(m"3)

(pCi/m*3)

(> 205)

Jan none Feb none Mar none Apr none May none Jun none Jul none Aug none Sep none Oct none Nov none Dec none Total 28

~

1985 Table 14 Monthly Liquid Was'te Discharge Month -Isotope Total Point of Release Percent of Release Concentration Maximum (uCi)

(m"3)

(pC1/m"3)

(5)

Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Table 15 Monthly Solid Waste Disposal M9 nth. Isotope Total Form Remarks Release Chemical / Physical (uci)

(ft"3)

Jan Feb Mar Apr May Jun Jul Aug i

Sep 26 12 samples, paper 10/31/85 Oct

.Nov Dec i

i 29 1

1985 V.

Laboratory Inspections A.

NRC Inspections No NRC inspections took place during the caler. der year for the R-92 TRIGA reactor operation license.

No NRC inspections took place during the calender year for the SNM-180 special nuclear material license.

A site inspection was made on January 22.for the docket 50-602 application to relocate facility activities to the Balcones Research Center.

Subsequent review or the application and answers to questions from NRC staff led to the issuance on June 6 of a construction permit, CPRR-123 B.

TDH Inspection October 21-22, 1985 The inspection consisted of a review of activities and radioactive materials used at The University of Texas at Austin as authorized by TDH License.

30

1985 VI.

Public Service Activities 1

A.

Summer High School Science Teacher Symposium v'

The NETL staff organizes and supervises an annual two week symposium designed to familiarize high school science teachers with the theory and technology associated with energy resources today.

Graduate college course credit is given to all participants who successfully complete the course.

The program is funded by various electric utility companies in Texas.

Approximately thirty (30) teachers attend the symposium every year.

B.

Lectures and Presentations On numerous occasions during 1985 the NETL staff talked to various organizations about subjects including but not limited to.

" Nuclear Reactor Safety," " Nuclear Engineering and Society," "Research and Development of Energy Resources," and " Energy and the Environment."

C.

Reactor Facility Tours During 1985, 870 persons visited the laboratory.

The largest group visiting the laboratory were persons attending the Texas Energy Science Symposium.

Numerous high school students also toured the facility during an ovent called The World of Engineering, designed to recruit students into the field of Engineering.

Students from several local high schools and students from several non engineering related 4

i.

college courses visited the facility.

Numerous college engineering related classes and several student engineering organizations also toured the facility.

Safety personnel such as Austin Fire Department, UT Police Department. UT Safety Office and the Texas Department of Health also visited the facility to remain familiar with the laboratory and emergency response procedures unique to the facility.

D.

Fuel Transfer Cask Loan A three element transfer cask was obtained as part of the fuel element acquisition from the Northrup Corporation.

t The donated cask is designed for standard elements of TRIGA fuel and is to be available for loan to other university I

reactor programs.

A container to ship the empty cask is also available.

Charges for the cask use will apply only to shipment costs.

s a

4 l

31

1985 VII..Research Activities The Nuclear Engineering Teaching Laboratory pursues research of both sponsored and non sponsored projects in several different areas.

The following section lists research projects in which.the laboratory has participated.

Major research funding or grants are presented in Table 16.

A.

Fuel Assistance Sponsor:

U.S.

Department of Energy Personnel:

Dale Klein, NETL Thomas L.

Bauer, NETL

==

Description:==

The U.S.

Department of Energy has provided research support by providing reactor fuel cycle assistance for the currently operating reactor core at The University of Texas at Austin TRIGA reactor.

B.

Summer Science Teachers Symposium Sponsor:

Electric Utility Companies of Texas Personnel:

Dale Klein, NETL The Electric Utility Companiec of Texas have sponsored Summer High School Science Teachers Symposium, a program designed to familiarize these teachers with the theory and technology of energy sources.

32

1985 Table 16 Research Funding

. Department of Energy Fuel Assistance Program Texas Energy Research Foundation 22,000 6/85 - 8/85 Electric Power and the Environment 20,000 6/85 - 8/85 National. Science Foundation 14;,626 9/85 - 8/87 Sandia National Laboratories 90,000 2/85 - 9/87 Texas Low Level Radioactive Waste Disposal Authority 9,736 9/84 - 8/85 University Research Institiute 6,000 9/84 - 9/85 Northrup Aircraft Corp.

Grant of TRIGA Fuel Elements (85 value) 258,515 Orant of Racks and Cask 3,600 4/85 TOTAL 426,477 r

33

- _ = _ - - -

1985 Heat Transfer and Friction Factor Analysis for Artt*1cially Roughened Surfaces Sponsor:

Center for Energy Studies National Science Foundation University Research Institute Personnel:

Dale Klein, NETL J.

Parker Lamb, Mech. Eng.

Mike Krause, NETL

==

Description:==

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

Two major aspects are to be examined in that this is both an experimental and an analytical investigation.

Values of R(h+) and G(h+) in the universal I

velocity and temperature profiles will be examined.

New i

experimental techniques have been developed at The University of Texas at Austin to measure local heat transfer values surrounding discrete roughness elements.

A test assembly to examine artificially roughened surfaces is being designed.

In addition, a new analytical method has also i

been developed to determine R(h+) and G(h+) values without making detailed velocity and temperature profile measurements.

Analytical predictions will be rade utilizing fundamental parameters in boundary layer theory coupled with the latest information on rough surfaces using integral l

techniques.

Results from the experimental and analytical methods will be compared in order ~to gain insight as to the i

dominant mechanism involved for the use of discrete rough surfaces.

This research has fundamental application for heat transfer augmentation.

Fission Product Absorption in Continuously Processed Fission Suppressed Fusion Hybrid Reactor Blankets Sponsor Department of Energy Fellowship Center for Fusion Engineering i

Personnel:

Dale Klein, NETL J.W.

Davidson, NETL Ann Patterson-Hine, NETL Description The effect on blanket performance of fission product absorption in lithium / molten salt hybrid reactor blankets is being investigated.

Neutron flux spectra in blankets of varying fuel and fission product compositions are being determined using the discrete ordinates codes, ANISN, and DOT-IV with multigroup oross section data from VITAMIN-C.

34

1985 Flux levels and spectrally weighted cross section libraries for the blanket materials, fuel, and fission products will l

be established for use in the depletion analyses.

Generation and depletion of the various isotopes in the blanket will be calculated using ORIGEN.

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

In addition to full and partial reprocessing of the molten salt, alternative processing concepts will be i

investigated.

A parametric study of the effects of processing performance will be carried out.

This study will result in the characterization of the fission product concentration in the molten salt with respect to isotopics, neutron absorption, and the effects on blanket parameters such as the tritium and fissile breeding ration.

I i

i Pressure Drop and Heat Transfer Measurements of Liquid Metal Flowing in a Packed Bed Under the Influence of a J

Magnetic Field i

Sponsor:

Center for Fusion Engineering Texas Atomic Energy Research Foundation Personnel:

Dale Klein, NETL Tom Sanders, NETL Larry Grater, Mech. Eng.

Mike Crawford, Mech. Eng.

==

Description:==

4 The flow of electrically conducting fluids through porous media in the presence of a magnetic field has recently begun to generate significant interest due to potential applications for fusion reactors.

This study is designed to examine the pressure drop and heat transfer from a liquid metal (NaK) flowing through a packed bed of stainless steel spheres under the-influence of a transverse magnetic field.

Results of this investigation should have direct applications on the design of fusion breeder blankets using liquid metal flowing around spheres of fertile material.

i Co2 Production for Enhanced Oil Recovery Using Texas Lignite and Nuclear Process Heat i

Sponsor Center for Energy Studies Personnel:

B. Kolda, NETL l

Dale Klein, NETL Descriptions i

l l

35

1985 Carbon dioxide miscible displacement is one method of enhanced oil recovery which can increase ultimate production beyond that obtained from primary and secondary methods.

Current sources of CO2 for this application are obtained from natural CO2 wells, by-product CO2 and on-site generation of CO2.

This project is to examine the feasibility of obtaining CO2 and other valuable by-products from Texas lignite using a high temperature gas-cooled nuclear reactor for process heat.

An integrated concept will be developed to include the nuclear process heat and the valuable by-products converted from the Texas lignite.

Thermal Analysis of Nuclear Shipping Containers Sponsor:

Sandia National Laboratories Personnel:

Randy Manteufel Dale E.

Klein

==

Description:==

The thermal analysis of shipping containers to be used in the transport of spent nuclear fuel is an important safety issue.

Sandia National Laboratories has been involved in safety issues for the transport of nuclear material for many years.

The University of Texas at Austin (NETL) has been involved in the specific issucc of thermal analysis of these containers for several years.

The current project is intended to benchmark a thermal analysis computer code (Q/TRAN) and pre and post processing software PATRAN-G using four standard model problems.

Comparisons will be made with other applicable codes currently available at UT (including HEATING 5).

Sensitivity studies will be perforced to further evaluate Q/TRAN's suitability for thermal analysis.

Enhancements, if any, that will increase the current capabilities of the software will'be suggested and developed if feasible.

Application of COBRA for shipping Cask Analysis Sponsor:

Sandia National Laboratories Personnel:

Tom Dolbear, Hochanical Engineering Dale Klein, NETL

==

Description:==

A thermal hydraulic computer code, COBRA, has been applied for both steady state and transient analysis.

Previous research at The University of Texas at Austin involved the modification of the CODRA code and created a new version COBRA'GCPR 4P/UT.

The current research is directed towards 36

1985-t modifying.CO3RA*GCFR 4P/UT so that it may be applied to i-transient conditions for shipping cask analysis.

One i

speciific modification will be to develop a more i

sophisticated model for analyzing radiation heat transport.

Results using this code will be compared with the resulta from Q-TRAN and HEATING-6 where possible.

In addition, recommendations will be made regarding COBRA's use for dry storage analyses.

i l

Transportation Analysis of Spent Fuel & High Level l

Wastes I

Sponsor:

Nuclear Engineering Teaching Laboratory j

Personnel Danny Smith, NETL j

Dale Klein, NETL Thomas L.

Bauer, NETL 1

{

==

Description:==

i r

The current methodology (i.e.,

overall plan for analysis j

which integrates discrete computer codes and other j

computational elements) for analysis of high-level waste and spent fuel transportation is not directed toward minimizing i

radiation exposure but rather is an attempt to demonstrate minimum compliance with statutory and regulatory requirements.

The current models (i.e.,

algorithms and f

computer codes) exhibit deficiencies and the thesis to be j

examined for this work is that more representative and i

credible models can be developed for radioactive waste transportation analyses and those models can be integrated into a methodology that allows selection of routes resulting in minimum radiation exposure.

This work will also examine options for cost-effective enhancement of transportation i

operations with the intent of minimizing public and j

occupational exposure to radiation as well as exposure to I

radiation and non-radiation transportation risks i

(recognizing that elimination of risk is neither possible j

nor nocessary but that achievement of exposures as low as I

reasonably achievable, ALARA, is prudent).

t i

Neutron Transport Studies:

Neutron !!ultiplication by j

Beryllium t

i j

Sponsor:

National Science Foundation Personnel:

Nolan E.

Hertel, Center for Fusion Engineering i

Descriptions l

l 37 t

1965 The use of beryllium as a neutron multiplier is central to the current fusion breeder design.

Recent measurements of beryllium neutron multiplication and reevalutions of beryllium nuclear data indicate that the multiplying performance of beryllium previously has been overestimated, possibly by as much as 255.

If beryllium's performance as a neutron multiplier has indeed been overestimated even by as much as 10%, the direction of the fusion breeder program in the United States might well change.

It is tantamount to the current fusion breeder concepts that the issue of beryllium neutron multiplicction be resolved.

Therefore, an experiment using a spherical shell of beryllium is being proposed.

The beryllium experiment has been designed to measure multiplication resulting from DT, DD, PuBe, and 252Cf neutron sources being placed in a spherical shell. By doing so the sensitivity of the multiplication to spectral shape can be observed.

In addition, the use of these four sources helps to simulate the effect of neutron source degradation in a fusion reactor.

The neutron multiplication will be obtained directly from summing weighted Bonner ball measurements of the neutron leakage.

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

Neutron Therapy Beam Hensurements Sponsor:

National Institute of Health

- Public Health Service Personnel:

Nolan Hertel, Hechanical Engineering Robert Graves. Universtiy of Rochester

==

Description:==

The energy spectra of the new neutron beam at H.D.

Anderson Hospital will be measured.

This will be done by using two techniques (1) the foil activation technique in which neutron energy spectra are obtained by unfolding threshold foil activation data, and (2) the pulse height unfolding method in which both neutron and photon energy spectra are obtained by one-dimensional pulse height unfolding using experimentally measured response functions for mono-energetic photons and neutrons.

Spectra will be measured in air and in tissue-equivalent liquid phantom as a function of field size, depth along central axis, off-axis distance, and beam modifying devices.

Data measured under these conditions will be used to compute kerma ration and ionization chamber sensitivity factors needed to calibrate the therapy beams.

The results will also provide information on both the dosimetric and biological i

38

1985 significance of the variations in the energy spectra within a phantom.

Calcium and Cadmium Uptake Studies Sponsor:

John Hopkins Center for Alternatives to Animal Testing Personnel:

E. Sorenson, Pharmacy Dept.

D.

Acosta, Pharmacy Dept.

T.

Bauer, NETL

==

Description:==

Radioactive tracers of Cd104, Ca45, and Cd115 were employed in studies of binding and transport related to cell uptake mechanisms.

Several experimonts with cell cultures of rat hepatocyte cells were perforoud to determine the effect of calcium presence on the intake of the toxic element cadmium.

Analysis of Parcioulate Samples.Related to Dust and Air.

Sponsor:

Nuclear Enginec'ing Teachi ng Laboratory Columbia Scientific Industries Personnel:

T.L.

Bauer, NETL. -

~

F.Y.

Iskander, NEIL J.

Rhodes, CSI

==

Description:==

Samples of particulate materials from unspecified origin were analyzed for element components and trace elements detectable by neutron activation techniques.

Data is to be supplemented with energy dipersive x-ray flouresence measurements.

. Determination'i.f 25 E19ments in Texas Hard Red Winter Wheat and Itr Hilling Fractions l

Sponsor:

Nuclear C7.gineering. Teaching Laboratory Texas AiH Univecrsity Personnel:

F.Y.

7,ukander M,14 ', !!c r e d

==

Description:==

Five varieties of hard red winter wheat (Scout 66, Coker 767, Vona, TAH101 and TAH105) grown in Texas, 1982 were milled and separated into six fractions using U.S.

standard sieves.

Twenty-five eierents were determined in each 39

1985 fraction as well as in the whole wheat.

Protein, in vitro protein digestibility and ash content of each fraction were also determined.

Correlation between the results was studied.

~

Vanadium Absorption by Crude Oil Sponsor:

Nuclear Engineering Teaching Laboratory University of Old Dominion (Virginia)

Personnel:

F.Y.

Iskander F. Jacobs

==

Description:==

Crude oil and ashphaltenes samples were equilibrated with vanadium salt solutions then separated into petroleum and aqueous phases.

Each phase was analyzed for vanadium by INAA.

Absorption of V02+ occurs to a greater extent than the absorption of VO+.

The effect of pH, presence of other ions and oil-to-aqueous volume ratio was studied.

Three crude oil samples were used (Jobo, Tia Juana and Bachaquero) and one asphaltene (Jobo).

Determination of Toxic and Other Elements in Rain Sediment Collected in Nigeria Sponsor:

Nuclear Engineering Teaching Laboratory University of IFE (Nigeria)

Personnel:

F.Y.

Iskander 0.I.

Asubiojo

==

Description:==

Rainfall, after drought season, washes out the suspended dust and air particulates.

Twenty-nine (29) elements were determined in six samples collected at different locations.

Element concentrations concluded that the Nigerian dust components are similar to those reported in urban dust l

collected from U.S.

cities.

l Evaluation of Elemental Content of Corn-Nuts Sponsor:

Nuclear Engineering Teaching Laboratory Dept. of Soil and Crop Sciences, Texas A&M University Personnel:

F.Y.

Iskander H.H.

Horad i

Descriptions 40 6

=_

1985 The project was designed to evaluate the potential usefulness of Corn-Nuts corn in alkaline cooked and other products,'and to determine its chemical composition, physical and processing properties relativ'e to existing food corn.

In this regard Corn-Nuts was compared versus commercial white dent corn (Asgrow 405W), a yellow dent corn hybrid (Asgrow 404), a quality protein maize and high lysinc corn.

Heasurement of.Nutrional and Other Elements in Bread Sponsor:

Nuclear Engineering Teaching Laboratory Food Research Center, University of Idaho Personnel:

F.Y.

Iskander K.R. Davis

==

Description:==

Egyptian bread samples were collected from several locations across the country.

Cereal and other components used for bread making depend on location (city, village or nomad).

The objective of the study is to determine the concentration of nutritional elements in the different bread samples and to study a possible correlation between the iron content of bread and cases of iron deficient anemia.

d Determination of Rare Earth and other Elements in Botton Sediments from the Mediterranean Sea 4

Sponsor:

Nuclear Engineering Teaching Laboratory.

Oceanography Dept., Alexandria University Personnel:

F.Y.

Iskander N. Dowider

==

Description:==

Silt is deposited directly in front of the Rosetta and Damietta mouth of the Nile where distribution of sediments

(

is not governed by the. bottom configuration.

Fine sediments are distributed in deep depositional environments as well as in shallow water areas.

The distribution of the sediments thus seems to'be mainly affected by acting currents in the area.

Sediments passing through the Rosetta and Damietta branches are distributed asymmetrically on either side of the mouths of the two branches.

In this study.the concentration of 30 elements were determined in twenty different samples.

Comparison Between Imported and Locally Manufactured 41

1985 Baby Food in Nigdria Sponsor:

Nuclear Engineering Teaching Laboratory Dept. of Chemistry, University of IFE, Nigeria Personnel:

F.Y.

Iskander 0.I.

Asubiojo The concentration of nutritional, probably nutritional and toxic trace elements in baby food locally produced in Nigeria'were compared to imported brands.

Based on the total element content no significnnt difference was observed between local and imported baby foods.

However, mineral bio-availability from the different brands may vary.

Effect of Maturation the Mineral Content of Soybeans Sponsor:

Nuclear Engineering Teaching Laboratory Personnel:

F.Y.

Iskander

==

Description:==

Soybeans contain up to 40% protein and 20% oil, and are considered as the meat substitute in less fortunate countries.

The effect of maturation on mineral content (Al, Br, Cu, C1, Fe, K,

Mg, Mn, Na, Rb and Zn) has been studied.

Three soybean varieties at different maturations states were investigated.

In general, no differences in the mineral content was observed at the different maturation stages.

Chemical Evaluation of Alkali Cooked Corn using Traditional and Presoaking Procedure Sponsor:

Nuclear Engineering Teaching Laboratory Cereal Quality Laboratory, Texas A&M University l

Personnel:

F.Y.

Iskander M.M. Morad R.W.

Rooney i

==

Description:==

Alkali cooking is the base for most corn snack food.

Treatment is essential for product quality and nutritional l

value.

In this study alkali procedure versus laboratory i

prepared instant flour and a. commercial flour were compared.

Samples were analyzed for physical properties and i

nutritional minerals along with the performance in producing a quality product (tortillas and tortilla chips).

42 l

VIII.

Publications From the Nuclear Enrineerina Teaching Laboratory 1.

K.L. Gilbert, " Neutron Flux Mapping of a Subcritical Reactor Core with a Polyethylene Reflector", Mastern Thesis, Physics (Nuclear Engineering) Department, The University of Texas at. Austin, 61 pp., June 1961.

2.

T.T.

Doss, " Neutron Density Distribution in an Unre-flected Suberitical Reactor Core", Masters Thesis, Physics (Nuclear Engineering) Department, The University of Texas at Austin, 63 pp.,

June 1961.

3 J.M. Norwood, "The Point Source Transport Solution for the Position and Velocity Dependent Neutron Dis-tribution in a Spherical Body of Non-Multiplying Material", Masters Thesis, Physics (Nuclear Engin-eering) Department, The University of Texas at Austin, 75 pp. June 1962.

4.

R.W.

Reed, "Effect of a Cadmium Control Rod on the Neutron Density in a Suberitical Reactor", Masters Thesis, Physics (Nuclear Engineering) Department, The University of Texas at Austin, 85 pp.,

August 1962.

5.

P.

Berananda, " Neutron Flux Distribution of a Sub-critical Reactor Core with a Graphite Reflector",

Masters Thesis, Physics (Nuclear Engineering)

Department, The University of Texas at Austin, 40 pp.,

January 1962.

6.

T.A.

Fredericks, " Thermal Neutron Flux Distribution Due to a Plane Wave Source in an Unreflected Reactor Assembly", Masters Thesis, Physics (Nuclear Engin-eering) Department, The University of Texas at Austin, 107 pp.,

August 1963 t

i 7

D.G.

Martin, " Film Detector for a Neutron Spectro-meter", Masters Thesis, Physics (Nuclear Engin-eering) Department, The University of Texas at Austin, June 1963 8.

M.L. West II, " Flux Decay Rate in a Reflected Sub-critical Reactor", Masters Thesis, Physics (Nuclear Engineering) Department, The University of Texas at Austin, 55 pp.,

August 1963 43

=..

f 4

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 at Austin, 186 pp.,

January 1965 4

I 10.

B.E.

Thompson, Sr.,

"Cryogenio Neutron Spectra Mea-i surements-Across a Discontinuity in Temperature and Properties", Ph.D. Dissertation, The University of i

Texas at Austin, 149 pp.,

January 1965.-

i 11.

R.S.

Kolflat, "An Experimental Approach to the Study of Nucleonic Fundamentals", Masters Thesis, Mechan-ical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, 190 pp., May 1965.

12.

D.G.

Anderson, "A Technique for Recoil Fission Frag-

. ment Range Measurements", Health Physics, 1211, 558 (April 1966).

i 13 J.B. Whitworth, "A Cryogenic Irradiation Device for the TRIGA Mark I Nuclear Reactor", Masters Thesis, Hechanical Engineering (Nuclear Engineering) ~

Department, The University of Texas at Austin,

'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) Department, The University of Texas at Austin, January 1967 i

15.

G.F.

Malan, " Transfer Function Analysis of Temper-ature and Xenon Feedback in Coupled-Core Nuclear Reactor Systems", Masters Thesis, Mechanical.Eng-

+

insering (Nuclear Engineering) Department, The l

University of Texas at Austin, 69 pp.,' August 1967 16.

M.G. Stevenson, " Investigations on the Macroscopic l

Nodal Approach to Space-dependent Huclear Reactor Kinetics", Ph.D. Dissertation, The University of Texas at Austin, 203 pp.,

August 1968.

17 F.H.

Antunez-Castillo, " Gamma Radiation Dosimetry Techniques and Application to Mapping of The Uni-versity.of Texas Cobalt-60 Irradiation Facility",

Masters Thesis, Physic" (Nuclear Engineering)

Department, The Univeisity of Texas at Austin, 60 pp.,

September 1968.

18.

R.

Valiente, " Neutron Radiography with The University of Texas TRIGA Nuclear Reactor", Masters Thesis, Physics (Nuclear Engineering) Departmeat, The Univer-sity of Texas at Austin, August 1968.

19 P.J.

Rodriguez and D.H.

Nguyen, " Time Decay Constants in Pulsed Multiplying Media", Trans. Amer. Nucl.

h.L1 LL, 289 (June 1968).

20.

P.J.

Rodriguez and D.H.

Nguyen, "The Maximum Eigen-value in the Pulsed-Neutron Initial-Value Problem",

Trans. Amer. Nucl. Soc. 1112, 578 (November 1968).

21.

P.J.

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

Soc. 1112, 582 (November 1968).

22.

G.D.

Bouchey and S.J.

Gage, " Neutron Radiography with a Small Suberitical Reactor", Trans. Amer. Nucl.

Soc. 12, 462 (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", Proc. of the Offshore Technolony conference, Dallas, Texas, 1969.

24.

J.A.

Villalobos, "A Study of. Gamma Radiation Dos-f imetry Techniques-and Application to Radiation Field-Mapping", Masters Thesis, Physics (Nuclear Engin-eering) Department, The University of Texas at Austin, January 1969.

25.

M.A.

Zuniga, " Delayed Neutron Counting Technique for Uranium Determination", Masters Thesis, Physics (Nuclear Engineering) Department, The University of Texas at Austin, January 1969 26.

V.

Chanto, S.J.

Gage, and D.F.

Barker, " Chlorine and Bromine Concentrations in Some Haliburton-Bancroft Rocks and Minerals Oy Neutron Activation Analysis",

1969.

l

27 H.

Galiardo, S.J.

Gage, and D.F.

Barker, " Trace Elements in Quartz by Nondestructive Neutron Activa-tion Analysis", 1969.

28.

G.D.

Atkinson, Jr.,

" Investigation of the Dynamic Behavior of a Two-Region Subcritical Reactor",

Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, January 1969.

29.

M. Gallardo, " Trace Elements in Six Quartz Samples by Nondestructive Neutron Activation Analysis Tech-nique", Masters Thesis, Physics (Nuclear Engineering)

Department. The University of Texas at Austin,

' January 1969.

30.

F.A. Rodriguez, S.J.

Gage, and K.H.

Ralls, "Nonde-structive Neutron Activation Analysis for Trace Impurities in Niobium", presented at the Seventh Synposium 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 Irradiation", Radiation and Isotope Technology in Latin American Development, American Nuclear Society Topical Meeting, San Juan, Puerto Rico, May 1969.

32.

R.H. Richardson, " Migration and Enzyme Polymorphisms in Natural Populations of Drosophila", Jao.

J.

Gen.,

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 Poten-tial Utilization of a Neutron Radiography Facility at The University of Texas Nuclear Reactor Labor-atory", presented at the Seventh Symposium on Nondestructive Evaluation of Components and Materials in Aerospace, Weapons Systems and Nuclear Applica-tions, San Antonio, Texas, 1969 e

4 d

35 G.D.

Bouchey and S.J.

Gage, " Utilization of The Uni-versity of Texas TRIGA Reactor for Neutron Activa-tion Analysis Service", ANS/CNA Transactions ll, 287 (1968).

36.

G.D.

Bouchey and 3.

Gjerstad, " Chemical Studies of II. Inorganic Ingredients",

Alce Vera Juice Quarterly Journal of Crude Drum Research, 311, (1969).

37 S.J.

Gage, R.H.

Richardson, and G.D.

Bouchey,

" Neutron Activation Techniques for Labeling of In-sects with Stable Elements", Trans. Amer. Nucl.

Iim., 12, 495 (1969).

38.

F.G.

Pasos, "Nondispersive X-Ray Fluorescence Anal-ysis using a Lithium Drifted Germanium Detector",

Masters Thesis, Physics (Nuclear Engineering)

Department, The University of Texas at Austin, 54 pp.,

January 1969.

39 P.J.

Rodriguez, " Time and Energy Dependent Neutron Distribution in a Pulsed Multiplying Medium", Ph.D.

Dissertation, The University of Texas at Austin, 205 pp.,

January 1969 40.

G.D.

Bouchey, B.V.

Koen, and C.S.

Beightler, "The Optimal Allocation of Energy in Industrial and Agro-Industrial Complexes Using Dynamic Programming",

Nucl.- Sci. and Ener., al, 70 (1970).

41.

G.F.

Malan and B.V.

Koen, "A Nonlinear Programming Approach to Optimal Control of Nuclear Reactors",

Trans. Amer. Nucl.

Soc.,

(1970).

42.

M.G.

Stevenson and S.J.

Gage, " Application of a Coupled Fission Mode Approach to Modular Reactor Kinetics", Journal of Nuol. Enerevi 23, 1 (1970).

43 G.D.

Bouchey and S.J.

Gage, "Neutr'on Radiography at The University of Texas Nuclear Reactor Laboratory",

Isotones and Radiation Technology, 1, 294 (1970)..

l 44.

D.G.

Jopling, "The Politics of Nuclear Reactor Siting", Masters Thesis, Hechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, December 1970.

45.

A'.H.

Urdaneta, "A Programmed Associative Analyzer",

Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The. University of Texas at Austin, December 1960.

46.

G.D.

Bouchey and S.J. Gage, " Detection and Location of Leaking TRIGA Reactor Fuel Elements", GA Publi-cation T-117, Papers and Abstracts, TRIGA Reactors Owners' Seminar, Denver, Colorado, February 1970.

47 G.D.

Bouchey and S.J. Gage, " Neutron Radiography with a Small Suberitical Assembly", International Journal of Nondestructive Testine, 1970.

48.

G.D.

Atkinson, Jr.,

J.B.

Whitworth, and S.J.

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

4 9..

S.J.

Gage, G.D.

Atkinson, Jr.,

J.B.

Whitworth, and A.H.

Pradzynski, " Computer-Aided Multielement Gamna Ray Analysis with a Compton Suppressed'Ge(Li) Radi-ation Source", presented at the Ninth National Society of Applied Spectroscopy, New Orleans, Louisiana, October 1970.

50.

K.R.

Waid, " Solid State Radiation Detection Devices:

Fabrication, Techai. ques and Application to Nuclear Engineering", Masters Thesis, Hechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, January 1970.

51.

V.H.

Chanto, " Neutron Activation Analysis of Chlorine and Bromine in Some Haliburton-Bancroft Rocks and Minerals", Masters Thesis, Physics (Nuclear Engin-eering) Department, The University of Texas at Austin, January 1970.

i 52.

J.J.

Chromik and E.L.

Draper, Jr.,

" Energy Integral l

Tests of Differential Fission Cross Section Data",

Trana. Amer. Nucl. Soc-, 1312, 755 (1970).

53 R.J. Gramatges-Figueras, " Neutron Waves in Cylindri-cal Geometries for a Suboritical Reactor", Masters Thesis, Mechanical Engineering (Nuclear Engineering)

Department, The University of Texas at Austin, 98 pp.,

May 1970.

j I

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

54.

E.

Delkers, Jr.,

"A Learning Method for Identifica-tion of Nuclear Reactor Point Dynamics", Masters Thesis, Mechanical Engineering'(Nuclear Engineering)

Department, The University of Texas at Austin, 165 pp.,

August 1970.

55 F.A.

Rodriguez-Gonzalez, " Application of Neutron Acti-vation Analysis to the Study of Interstitial Solid Solution of Oxygen in Niobium and in Niobium-Titanium Alloys", Ph.D. Dissertation, The University of Texas at Austin, 131 pp.,

August 1970.

56.

J.R.

Deen, " Calculation of Resonance Integrals Using the Intermediate Resonance Approximation", Masters Thesis, Mechanical Engineering (Nuclear Engineering)

Department, The University of Texas at Austin, 140 pp.,

January 1970.

57 C.T.

Rombough, " Application of Queueing Theory to Closed-Loop Computer-Reactor Control Systems",

Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, 78 pp., December 1970.

58.

A.H.U.

Bohorquez, "A Programmed Associative Anal-yzer", Masters Thesis, Mechanical Engineering (Nu-

~

clear Engineering) Department, The University of Texas at Austin, 98 pp.,

December 1970.

59 S.J.

Gage and D.G.

Jopling, The Nuoler Concent!

Potential for the SINB Rerion, Southern Interstate Nuclear Board, 250 pp.,

March 22, 1971.

60.

G.F.

Malan and B.V.

Koen, " Application of Nonlinear Programming to the Optimal Control of a Poir.t Model Nuclear Reactor", Nucl. Sci. and Ener.,

(1971).

61.

G.D.

Bouchey, B.V.

Koen, and C.S.

Beightler, "Optimi-zation of Material Safeguards Sampling System",

Trans. Amer. Nucl. Soc., Winter Meeting, 1971.

62.

A.H.

Pradzynski and S.J.

Gage, " Nondestructive Iden-tification of Material by Nondispersive X-Ray Fluor-escence Spectrosocpy Using Si(Li) Detectors and Radio-isotopic Sources", Proc. Eighth Symoosium on Nondes-tructive Evaluation in Aerosoace. Weaoons Systems.

and Nuclea:- Anolications, San Antonio, Texas, 1971.

l 63 G.D.

Atkinson, Jr. and S.J.

Gage, " Uranium Assay by Delayed Gamma Ray Analysis Following Cf-252 Neutron Interrogation", Proc. Twelfth Annual Meetine Insti-tute of Nuclear Materials Manacement, Palm 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 ADolications, CONF-710402, 2, Proc. of ANS Topical Meeting,. Augusta, Georgia, April 1971.

65 D.G.

Jopling and S.J. Gage, "Public Resistance to Nuclear Reactor Siting", Nuclear News, 1A13, 32 (March 1971).

66.

J.B. Whitworth, G.D.

Atkinson, and S.J. Gage, "Some Recent Applications of Nuclear Analysis Techniques to Typical Forensic Evidence" presented at the 23rd Annual Program American Academy for Forensic-Sciences, Phoenix, Arizona, February 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 Tech-nique", Trans. Amer. Nucl. S o c._, 14:2, 667 (October 1971).

68.

G.D.

Bouchey, B.V.

Koen, and C.S.

Beightler, "The Optimization of Nuclear Systems by Geometric Pro-gramming, Nucl. Sci. and Ener., 31, 267 (1971).

69 G.D.

Bouchey, B.V.

Koen, and C.S.

Beightler, "Opti-mization of Nuclear Materials Safeguards Sampling by Dynamic Programming", Nuclear Technolory, 12, 18 (1971).

70.

S.J.

Gage, G.D.

Atkinson, Jr.,

and G.D.

Bouchey,

" Cyclic Eeutron Activation Analysis with a Cf-252 Neutron Source", Trans. Amer. Nucl.

Soc.,

(October 1971).

i 71.

E.

Linn Draper, Jr.,

" Integral Reaction Rate Deter-mination Part I: Tailored Reactor Spectrum Prepar-ation and Me1surement", Nucl. Sci. and Ener., 11, 22 (1971).

l l

l

72.

E.

Linn Draper, Jr.,

" Integral Reaction Rate Deter-mination Part II: Fission Rate Measurements", Nucl.

Sci. and Ener., 31, 31 (1971).

73 G.D.

Bouchey and S.J. Gage, " Detection and Location of Leaking TRIGA Reactor Fuel Elements", Nuclear Technolorv, la, 211 (1971).

74.

G.D.

Bouchey and S.J.

Gage, " Neutron Radiography with a Small Subcritical Reactor", Int.

J.

of Nondestruc-tive Testine, 2, 335 (1971).

75.

G.D.

Bouchey and S.J.

Gage, "The Economics of Suberit-ical Radiography", Trans. Amer. Nucl.

Soc., 11, 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 Photographic Images", Neutron Sources and Aeolications, CONF-210402, 2, Proc. ANS Tonic Meeting, Augusta, Georgia, April 1971.

77 G.D.

Atkinson, Jr.,

J.B.

Whitworth, and S.J.

Gage,

• Computer-Assisted Analysis of Gamma-Ray Spectra",

Comouter Physics Communications, 2, 40 (1971).

78.

S.J.

Gage, E.

Linn Draper, Jr.,

and G.D.

Bouchey, "Recent Developments in Radioisotopic Source Neutron Radiography", Proc. Eighth Symoosium on Nondestrue-tive Evaluation in Aerosence. Weaoon Systems. and Nuclear Acolications, San Antonio, Texas, 1971.

79 G.D.

Atkinson, Jr.,

" Nondestructive Uranium Assay by Delayed Gamma Ray Analysis Following Californium-252 Neutron Interrogation", Ph.D. Dissertation, The University of Texas at Austin, 183 pp.,

August 1971.

80.

G.D.

Bouchey, "The Optimization of Nuclear Systems",

Ph.D. Dissertation, The University of Texas at Austin, 231 pp.,

August 1971.

81.

J.B.

Whitworth, "The Development and Application of a Systematic Approach to Elemental Analysis in For-ensic Investigations", Ph.D. Dissertation, The Uni-versity of Texas at Austin, 223 pp.,

December 1971.

e 82.

J.J.

Chronik, " Experimental Determination of the Neutron Flux in The University of Texas' Californium-252 Irradiation Facility", Masters Thesis, Mechanical ~

Engineering (Nuclear Engineering) Department, The University of Texas at Austin, 85 pp., December 1971.

83 E.

Linn Draper, Jr., Mary Elizabeth Foster, and G.D.

Bouchey, "X-Ray Fluorescence Analysis and Neutron Activation' Analysis in an Analytical Chemistry Lab-oratory", presented at the Combined Meeting of the Texas Association for Radiation Research and South Central Photobiology Group, Houston, Texasi November 1971.

84.

E.

Linn Draper, Jr. and G.D.

Bouchey, " Utilization of a Portable Californium-252 Source for Neutron Activation Analysis and Neutron Radiography", pre-santed at the Combined Meeting of the Texas Associ-ation for Radiation Research and South Central Photo-biology Group, Houston, Texas, November 1971.

85.

E. Linn Draper, Jr. and J.J. Chronik, " Production

.and Measurement of a Reference Spectrum in a Versa-tile Experimental Facility", Trans. Amer. Nucl.

Soc.,

.15.L1, 157 (1972).

86.

E. Linn Draper, Jr. and Andrzej J.

Pradzynski, "Iden-tification of Alloys by Energy Dispersive X-Ray Spec-troscopy", presented at the Ninth Symposium on Nondestructive Evaluation, 1972.

87 M.B. Owen, " Fuel Management Using Dynamic Program-sing", Masters Thesis, Mechanical Engineering (Nu-clear Engineering) Department, The University of Texas at Austin, 59 pp.,

May 1972.

88.

C.E.

Brauer,." Thermal Neutron Radiography with a Lith-ium-Lead Collimator-Filter", Masters Thesis, Mech-anical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, 64 pp.,

May-1972.

89 J.L.

MacDonald, "Heutistic Learning Control for Nuc-lear Reactors", Mastears Thesis, Mechanical Engin-eering (Nuclear ~ Engineering) Department, The University of Texas at Austin, 131 pp.,

August 1972.

90.

J.

Freim, " Theoretical and Experimental Evaluation of Nuclear Data and Calculation Techniques for Fu-sion Reactor. Blanket Design", Ph.D. Dissertation, The University of Texas at Austin, 210 pp.,

Decem-ber 1972.

91.

S.G.

Barbee, "Neutronic Calculations in a Simulated Fusion Reactor Blanket", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, 259 pp.,

November 1972.

92.

D.G.

Anderson, " Fission Product Mass-Yield Measure-ments from Intermediate Energy Neutron Fission of Plutonium-239 and Plutonium-241", Ph.D. Dissertation, The University of Texas at Austin, 125 pp.,

Decem-ber 1972.

93 D.M.

Williams, " Identification of Thermal Feedback Parameters for a TRIGA Mark I Reactor", Masters Thesis, Electric Engineering Department, The Univer-sity of Texas at Austin, 53 pp., December 1972.

94.

G.D.

Atkinson, Jr.,

E.

Linn Draper, Jr.,

and G.D.

Bouchey, "Suboritical TRIGA Reactivity Measurements Using the Source Jerk Technique", presented at the TRIGA Owners' Conference II, College Station, Texas, 1972.

95.

G.D.

Atkinson, Jr. and E.

Linn Draper, Jr.,

"Tran-sient Rod Failure in a Pulsing TRIGA Mark I Reac-tor", presented at the TRIGA Owners' Conference II, College Station, Texas, 1972.

96.

G.D.

Atkinson, Jr.,

"A Safeguards Minicourse",

l presented at the 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 Ampli-fication Using a Heterogeneous Suboritical Assembly",

Proc. 18th Annual Meeting of the American Nuclear i

Society, Las Vegas, Nevada (1972).

98.

E.

Linn Draper, Jr. and G.D.

Atkinson, Jr.,

"Trans-ient Rod Failure in a Pulsing TRIGA Mark I Reactor",

published in Proc. of 2nd TRIGA Owners' Confer-ence, February 1972.

I

99.

E.

Linn Draper, Jr.,

John W.

Davidson, S.J. Gage, and G.D.

Bouchey, "A System for Reduction of 41A Release from a Research Reactor Facility", Trans. Amer. Nucl.

h, 15.: 1, 4'(1972).

100.

E.

Linn Draper, Jr.,

et al, " Standard for the Develop-ment of Technical Specifications for Research Reac-tors", Trans. Amer. 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", Eroe. of the American Nuclear Society "loolications of Californium-292" National Tooloal Meetine, September 1972.

102.

E.

Linn Draper, Jr.,

G.D.

Bouchey, G.D.

Atkinson, Jr.,

and S.J.

Gage, "A Versatile Suberitical Assembly for Undergraduate Nuclear Engineering Instruction",

Proc. of the American Nuclear Society "Acolications of Californium-292" National Tooical Meetine, September 1972.

103 E. Linn Draper, Jr. and S.

J.

Gage, "The Fusion-Fission Breeder: Its Potential in a Fuel Starved Thermal Reactor Economy", presented at the 93rd Annual Meeting of ASME, New York, 1972.

104.

.E.

Linn Draper, Jr.,

" Technological Innovation and Assessment: A Novel Course for Nuclear Engineering",

presented at the Winter Meeting of the American Nuclear Society, November 1972.

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 Univer-sity of Texas at Austin, December 1972.

106.

P.S.

Schmidt and G.G.

Park, " Heat Dissipation in a Power Plant 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 Re-actor Blankets", Proc. of the Texas Symoosium of Tech-nolony of Controlled Thermonulaar Fusion Eroeriments and Engineerine Asoects of Fusion Reactors, Austin, Texas, November 1972.

108.

E.

Linn Draper, Jr. and Charles Brauer, " Lithium-Lead Collimator Fabrication for Radioisotopic Source Neu-tron Radiography", Trans._ Amer. Nucl. Soc., 1511, 142 (1972).

109 E.

Linn Draper, Jr. and James B.

Freim, " Theoretical and Experimental Evaluation of Nuclear Data and Calculation Techniques for Fusion Reactor Blanket Design", presented at the Texas Symposium on the Technology of Controlled Thermonuclear Fuet o Experiments and the Engineering Aspects of Ptaion Reactors, November 1972.

110.

E.

Linn Draper, Jr.,

" Status of CTR Related Integral Experiments" presented at the Conference on Nuclear Data and Neutronics of CTR Blankets held in Seattle, Washington, September 1972.

111.

E.

Linn Draper, Jr.,

" Fusion Reactor Engineering in the Nuclear Engineering Curriculum at The University of Texas at Austin", Trans. Amer. Nucl. Soc., (1972).

112.

E.

Linn Draper, Jr..and 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 Thermo-nuclear Fusion Experiments and the Engineering Aspects of Fusion Reactors, November 1972.

113 James B.

Freim and E.

Linn Draper, Jr.,

" Experimental Determination of the Fusion Spectrum in Graphite",

Trans. Amer. Nucl.

Soc.,

(1972).

114.

G.D.

Atkinson, Jr.,

S.J.

Gage, and G.D.

Bouchey,

" Cyclic Activation with a Californium-252 Source",

Nuclear Technolony (1972).

115.

G.D.

Atkinson, Jr.,

"What You Always Wanted to Know about Californium Source Facilities", Invited Paper, National Topical Meeting on the Applications of Californium-252, Austin, Texas (1972).

116.

T.L.

Bauer and G.D.

Atkinson, Jr.,

" Discrimination De-tween Plutonium and Uranium by Gamma Ray Analysis Following Cf-252 Interrogation", presented at the National Topical Meeting on the Applications of Californium-252, Austin, Texas, 1972.

117 E. Linn Draper, Jr., Editor, Proc. of Texas Symoosium on the Technology of Controlled Therno-nuclear Fusion Eroeriments and the Engineerine Asoects of Fusion Remeters, published by USAEC.

118.

E.

Linn Draper, Jr.,

Editor, Proc. of the Imolications of Nuclear Power in Texas, published by the Texas Atomic Energy Research Foundation.

119 E. Linn Draper, Jr.,

J.R.

Deen, and J.J.

Chronik, "Heasurement of the Integral Fission Cross Section of Th-232 in a Cf-252 Fission Neutron Spectrum",

Trans. Amer. Nucl. Soc.,

(1973).

120.

D.G.

Anderson and E.

Linn Draper, Jr.,

" Fission Pro-duct Mass-Yield Measurements from Intermediate Energy Neutron Fission of Plutonium-239 and Plu-tonium-241", Trans. Amer. Nucl. Soc.,

(1973).

121.

E.

Linn Draper, Jr. and James B. Freia, "Experi-mental Determination of the Fusion Spectrum in Graphite", Trans. Amer. Nucl.

Soc., li, 9 (1973).

122.

E.

Linn Draper, Jr.,

" Fusion Reactor Engineering in the Nuclear Engineering Curriculum at The Uni-versity of Texas at Austin", Trans. Amer. Nucl.

Soc., 15, 16 (1973).

123 E.

Linn Draper, Jr.,

Theodore A.

Parish, and Brian J.

McArdle, "A Neutronic-Photonic Comparison of Vanadium and Niobium Containing Fusion Reactor Blankets", Trans. Amer. Nucl.

Soc.,

(November 1973).

124.

John H.

Vanston, Jr.,

"Use of Partitive Analytical Forecasting (PAF) Techniques for Fusion Develop-ment Analysis", Trans. Amer. Nucl.

Soc.,

(November 1973).

1

125.

Theodore A Parish and E.

Linn Draper, Jr.,

"Neu-tronic and Photonic Analyses of Fusion Reactor Blankets Containing Thorium", presented at the Fifth Symposium on Engineering Problems of Fusion Research, Princeton, New Jersey, November 1973 l

126.

C.E.

Locke and D.R.

Paul, " Graft Copolymer Modifi-cation of Polyethylene-Polystyrene Blends.

I.

Graft Preparation and Characterization", Journal of Aeolied Polymer Science, II, 2597 (1973).

127 C.E.

Locke and D.R.

Paul, " Graft Copolymer Modifica-tion of Polyethylene Dolystryene Blends. II. Proper-ties of Modified Blends", Journal of Aeolied Polveer Science, 11, 2791 (1973).

128.

J.R.

Deen, "Heasarement of Fission Product Yields from Thorium-232 in a Californium-252 Fission Neutron Spectrum", Ph.D. Dissertation, The University of Texas at Austin, 141 pp.,

May 1973 129.

L.D.

Hansborough, "Overall Tritium Considerations for Controlled Thermonuclear Reactors", Masters Thesis, The University of Texas at Austin, 154 pp.,

May 1973 130.

H.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. Hac-

Donald, C.T.

Rombough, L.D.

Hansborougn, S.G.

Barbee, and J.H.

Vanston, Jr.,

"A University's Involvement ~1n Municipal Decision-Making on Nuclear Power", Trans.

Amer. 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. Amer. Nucl.

Soc.,

(1973).

133 R.E.

Henry, " Forensic Applications of Neutron Activa-tion Analysis", presented at the Combined Meeting of the Texas Association for Radiation Research and South Central Photobiology Group, San Marcos, Texas, November 1973

134.

G.D.

Atkinson,.Jr., " Applications of Neutron Activa-tion Analysis to the Life Sciences", presented at the Combined Meeting of the Texas Association for Radia-tion Research and So*4th Central Photobiology Group, San Marcos, Texas, November 1973 135.

S.P.

Nichols, " Experimental Determination of Neutron Fermi Age from Californium-252 Fission Spectrum to Cadmium Covered Indium Resonance in a Graphite Med-ium", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, 101 pp.,

January 1974.

136.

T.A.

Parish, "Neutronic and Photonic Analyses of Sim-ulated 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 Ef-facts of Various Funding and Administrative Strate-gies on Nuclear Fusion Power Plant 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, Lenomis cyane11us", Ph.D. Dissertation, The University of Texas at Austin, 233 pp.,

May 1974.

139.

E.

Linn Draper, Jr. and J.R.

Deen, " Measurement of Fission Product Yields from Thorium-232 in Californ-ium-252 Fission Neutron Spectrum", Trans. Amer. Nucl.

Soc., II, 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 l

Photonic Analyses of Fusion Reactor Blankets Contain-ing Natural Uranium", CONF-740402, USAEC, April 1974.

142.

G.D.

Atkinson, Jr.,

B.D.

Adams, and S.J.

Gage, "A

Programmable and Automated System for Gamma and X-Ray Analysis", Proc. IEEE 1079 Nuclear Science Symoosium, San Francisco, California, 1973 l

143 G.D.

Atkinson, Jr. and R.E.

Henry, " Neutron Activa-tion Analysis: Environmental and Biolgical Applica-tions", presented at the Sixth Annual Meeting of the Texas Association for Radiation Research, San Marcos, Texas, 1973, 144.

M.

Etzion, R.G.

Spangler, and E.

Linn Draper, Jr.,

" Multiple Foil Activation Measurement of the Californium-252 Fission-Neutron Spectrum, Trans.

Amer. Nucl.

Soc.,

(October 1974).

145.

A.H.

Pradzynski, " Determination of Selenium in Water on the ppb level" presented at the Texas Associ-ation of Radiation Research, Dallas, Texas, November 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 Inter-rogation Source", Masters Thesis, Mechanical Engineer-ing (Nuclear Engineering) Department, The University of Texas at Austin, 178 pp.,

August 1974.

147.

Olan D.

Thompson, " Optimization of Shipping Con-tainers for Radioisotopic Neutron Sources", Masters Thesis, Mechanical Engineering (Nuclear Engineering)

Department, The University of Texas at Austin, 30 pp.,

(August 1974).

148.

J R.

Deen and E.

Linn Draper, Jr.,

" Measurement of the Fission Product Yields and the Energy Integral Fission Cross Section of Thorium-232 in a Californium-252 Fission-Neutron Spectrum", Nuclear Technolorv, 25, 416 (1975).

149 E.

Linn Draper, Jr.,

T.A.

Parish, and M.

Etzion,

" Utilization of a Small Accelerator for Fusion Reactor Blanket Design", Proc. of the Third Small Accelerator Conference, USAEC, CONF-741021, 1974 150.

R.G.

Spangler, E.

Linn Draper, Jr.,

and T.A.

Parish, "14 MeV Cross Section Measurements of Threshold Reactions for Seven Metals", Trans. Amer. Nucl.

Soc.,

22, 818 (November 1975).

s t

151.

W.R. Smith, Jr. and E.

Linn Draper, Jr.,

" Measured and Calculated Fast Neutron Spectra in a Grapnite Med-ium", Trana. Amer. Nucl. Soc., 22, 800 (November 1975).

152.

J.W.

Davidson and E.

Linn Draper, Jr.,

" Costs for Partitioning Strategies Involved in High-Level Nuclear Waste. Management", Trans. Amer. Nucl. Soc.,

22, 348 (November 1975).

153 M.J.

Voltin, Jr. and E.

Linn Draper, Jr.,'"Sensiti-vity of Total Fuel Cycle Cost to Variations in Enrich-ment Tails Assay Strategies", Trans. Amer. Nucl.

h, 22, 322 (November 1975).

154.

T.A.

Parish, J.W.

Davidson, and E.

Linn Draper, Jr.,

" Transmutation of Fission Products in Fusion Reactor Blankets", Trans. Amer. Nucl. Soc., 22, (November 1975).

155.

T.A.

Parish, J.W.

Davidson, and E. Linn Draper, Jr.,

"The Effects of the D-T Fusion Neutron Energy Spec-trum on High Energy Reaction Rates", submitted to the Sixth Symposium on Engineering Problems of Fusion Research, San Diego, California, November 1975.

156.

A.H.

Pradzynski, R.E.-Henry, and J.L.S.

Stewart,

" Determination of Selenium in Water on the ppb Level by Coprecipitation and Energy Dispersive X-Ray Spectrometry", Radiochem. Radionnal. Letters, 2115, 277 (1975).

157 B.E.

Bulla, E.

Linn Draper, Jr.,

R.E.

Henry, M.J.

Voltin, Jr.,

et al, Terms Nuclear Power Policies!

A Study of Alternatives. Volume IIr Methodology.

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

158.

A.H.

Pradzynski, R.E.

Henry, and J.L.S.

Stewart

" Determination of-Transition Metals by Radioisotope-Excited Energy Dispersive X-Ray Spectrometry",

Trans. Amer. Nucl. Soc., 2113, 34 (1975).

i

159 A.H.

Pradzynski, R.E.

Henry, and J.L.S.

Stewart, "Non-destructive Determination of Toxic Elements in Toys",

Proc. of 10th Svanosium on Nondestructive Elements, San Antonio, Texas, April 1975.

160.

R.E.

Henry, " Determination of ppb-Levels of Salec-ted Elements in. Natural Water Using Radioisotope-Excited Energy Dispersive X-Ray Fluorescence Anal-ysis", presented at the Eighth Annual Meeting of the Texas Association for Radiation Research, Austin, Texas, October 1975.

161.

S.P. Nichols, " Application of the Partitive Analyti-cal Forecasting (PAF) Technique to the United States Controlled Thermonuclear Research Effort," Ph.D.

Dissertation, Mechanical Engineering (Nuclear Engin-eering) Department, The University of Texas at Austin, December 197.5.

162.

C.T.

Rombough, "The Total Energy Investment in Nuc-lear Power Plants", Ph.D. Dissertation, The Uni-versity of Texas at Austin, January 1975.

163 J.L. MacDonald, aInvestigation of Pattern Recog-nition Techniques for the Identification of Split-ting Surfaces in Monte Carlo Particle Transport Calculations", Ph.D. Dissertation, The University of Texas at Austin, August 1975.

164.

J.W.

Davidson, "A Cost-Benefit Analysis for Parti-tioning Strategies Involved in High-Level Nuclear Waste Management", Masters Thesis, Mechanical En-gineering (Nuclear Engineering) Department, 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 Trans-mutation 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", presented at the U.S.-U.S.S.R.

Symposium on Fusion-Fission Reactors, Lawrence Livermore Laboratories, July 1976.

)

167.

T.A.

Parish, J.W.

Davidson, and E.

Linn Draper, Jr.,

"Neutronic Performance of Graphite Fusion Reactor Blankets Containing Sr90 and I 129", presented at the 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, 23, November 1976.

169 A.H.

Pradzynski and J.R.

Rhodes, " Development of Syn-thetic Standard Samples for Trace Analysis of Air Particulates", ASTM Special Technical Publication, Sal, 320 (1976).

170.

A.H.

Pradznyski, R.E.

Henry, and J.S.

Stewart, " Deter-mination of ppb Concentrations ^of Transition Metals by Radioisotope-Excited Energy-Dispersive X-Ray Spectrometry, Journal of Radionnalytical Chemistry, 32, 219 (1976).

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 Precon-

~

centration and Radioisotope Excited X-Ray Emission Spectrometry", Proceedings of ERDA Symnosium on I-knd Gamma-Ray Sources and Anolications, Ann Arbor, Michigan, May 1976.

172.

A.H.

Pradzynski, R.E.

Henry, and E.L.

Draper, Jr.,

" Determination of Trace Elements of Hydrogeochemical Prospecting by APDC-Coprecipitation and X-Ray Spectro-metry", Invited Paper at The International Conference on World Nuclear Energy a Status Report.

Transac-tions of Amer. Nuclear Society, 21, 119 (1976).

173 R.R.

Gay, G.F.

Brockett, and R.T.

Johnson, "Two-Phase Flow Measurement Techniques for Nuclear Safety Re-search", Two-Phase Flow and Heat Transfer Symposium-Workshop, Miami Beach, Florida, 1976.

174.

C.W.

Savery and R.R.

Gay, "Effect of Entrained Drop-let Phase Upon Predicted Compartmental Pressures in Nuclear Containments", Two-Phase Flow and Heat Trans-fer Symposium-Workshop, Miami Beach, Florida, 1976.

175.

Rodney R. Gay, " Reactor Hydrodynamics During the Re-flood Phase of Loss-of-Coolant Accident", Nuclear Technolony, 3112, 229 (December 1977).

176.

D.E.

Klein, S.R.

Bull, and J.B. Miles, " Flow Visual-ization Around GCFR Fuel Rod Roughness Elements",

Trans. Amer. Nucl. Soc., 23, (June 1978).

177 D.E.

Klein, S.R.

Bull, and J.B.

Miles, " Pressure Drop for GCFR Fuel Rod Roughness Elements", Trans. Amer.

Nucl. Soc., 3A, (November 1978).

178.

E.M.B.

Sorensen, R.E.

Henry, and R.

Ramirez-Mitchell,

" Time Dependent Localization of Arsenic in Subcel-lular Hepatocyte Fractions",

J.

of Patholory and Toxicolony, 211, 1161 (1979).

179 E.M.B.

Sorensen, R.E.

Henry, and R.

Ramirez-Mitchell,

" Arsenic Accumulction, Tissue Distribution, Cytotox-ity in Teleosts Following Indirect Aqueous Exposure",

Bulletin of Environmental Contamination and Toxicol-s.g.I, 21, 162 (1979).

180.

J.W.

Davidson and T.A.

Parish, " Fission Product Toxi-city Reduction via Transmutation Using D-T Fusion Neutrons", presented at the Eighth 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. Amer. Nucl. Soc., 33, (No-vember 1979).

182.

S.A.

Hodge, J.P.

Sanders, and D.E.

Klein, "Determin-ation of Friction Factors and Heat' Transfer Coeffi-cients for Flow Past Artificially Roughened Sur-faces", Oak Ridge National Laboratory Report, ORNL-5599, November 1979.

183 D.E.

Klein, " Nuclear Problems and Prospects", Na-tional Energy Policy Issues, Council on Energy Re-sources, The University of Texas at Austin, May 1979.

e 184.

D.E.

Klein, H.H. Woodson, and J.W.

Davidson, "Com-mercial 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 Paren-chymal Hepatocytes", Tennessee Academy of Science Annual Meeting, Nashville, TN, November 16-17, 1979.

186.

A.H.

Pradzynski, " Determination of V had Ba in Marine Sediments and Biota", Internal Report, Nuclear Engineering Teaching Laboratory, Mechanical En-gineering (Nuclear Engineering) Department, The University of Texas at Austin, 1979 187 N.E.

Hertel, B.W.

Wehring, and J.J.

Dorning, "Integ-ral Test of ENDF/B-IV High-Energy Neutron Cross Sec-tion Data for Tungsten", Trans. Amer. Nucl. Soc.,

32, 632 (1979).

188.

R.H.

Johnson, K.R.

Koch, B.W. Wehring, and N.E.

Hertel, "TDL Measurements in an Iron Sphere Con-taining a DT Source", Trans. Amer. Nucl. Soc., 32,.

632 (1979).

189.

B.W.

Wehring, J.J.

Dorning, N.E.

Hertel.

D.T.

Inger-soll, and R.H.

Johnson,." Benchmark Shielding Problems Obtained from Integral Tests of Neutron Cross Sec-tions", Trans. Amer. Nucl.

Soc., 33, 666 (1979).

190.

N.E.

Hertel, R.H.

Johnson, J.J.

Dorning, and B.W.

l Wehring, "Hearsurements and Analyses of Neutron Transport Through Iron", Proc. Conf. Nuclear Cross Sections and Technolony, Knoxville, TN, October 22-26, 1979, NBS Special Publication #594, pp. 568-571.

191.

J.P.

Percy, " Experimental Determination of Local Convective Heat Transfer Coefficients Over a Ribbed Surface", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, May 1979.

4 192.

G.A.

Taylor, 'The Analysis of the Grid Spacer

~

Pressure and Temperature Effects in SAGAPO",

Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, August 1979.

193 D.D. Hau, " Determination of the Relative Toxicities of the Fission Products Produced in the Transmu-tation of Actinide Wastes", Masters Thesis, Hech-anical Engineering (Nuclear Engineering) Depart-ment, The University of Texas at Austin, December 1979.

194.

S.A.

Hodge, " Determination of Friction Factors and t

Heat Transfer Coefficients for Flow Past Artificially Roughened Surfaces", Ph.D. Dissertation, Hechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, December 1979.

195.

M.A.

Ross, " Electrical Power Generation and Process Heat Application for Coal Gasification and Lique-faction Using a Very-High Temperature and Gas-Cooled Reactor", Masters Thesis, Hechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, May 1980, 196.

N.E.

Hertel and B.W. Wehring, " Absolute Monitoring of DD and DT Neutron Fluences Using the Associated-Particle Technique", Nucl. Instr. Meth., 122, 501 (1980).

197 S.A.

Hodge, J.P.

Sanders, and D.E.

Klein, " Slope and Intercept of the Dimensionless Velocity Pro-files for Artificially Roughened Surfaces", Int.

J.

Heat Mass Transfer, 22, 135 (February 1980).

l 198.

N.E.

Hertel, J.B.

Smathers, and R.G, Graves, " Gam-ma-Ray Spectra Measured in a Tissue-Equivalent Medium Irradiated with Neutron Radiotherapy Sources", Trans. Amer. Nucl.

Soc., 25, 457 (1980).

199.

N.E.

Hertel, W.E.

Murphie, and R.J.

Calhoun, " Mea-surements of Neutron and Gamma-Ray Spectra in a Phantom Irradiated with 14-HeV Neutrons", presented at the Health Physics Society Annual Meeting, Louisville, KY, June 21-26, 1981.

t

?

l 200.

D.E.

Klein, S.R.

Bull, and J.B.

Miles, " Pressure Drop Measurements and Flow Visualization Surrounding Roughness Elements", Journal of Enerry, 313, 112 (1980).

201.

D.E.

Klein, "ANS Student Involvement in Public Infor-nation - The University of Texas at Austin",

Invited Paper, Trana. Amer. Nucl'. Soc., 31 (1980).

202.

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.-

203 J.E.

Hamann, D.E.

Klein, R.B.

Pope, and H.R.

Yoshi-aura, "Modelling of Pool Fire Environments Using i

Experimental Results of a Two-Hour Test of a Rail-car / Cask Systen", Paper #147, PATRAM-80, West Berlin, FRG., November 1980.

204.

M.A.

Ross and D.E.

Klein, " Synthetic Fuel Production Utilizing Texas Lignite and a VHTR for Process Heat", Trana. Amer. Nucl. Soc, 35, (1980).

205.

J.W.

Davidson and D.E.

Klein (co-editors), Proc.

of the International Conference on Nuclear Waste Transmutation, The University of Texas at Austin Press, March 1981.

206.

T.L.

Sanders, "An Alternative Numerical Method for-the Steady State and Transient Thermal-Hydraulic Analysis of Gas-Cooled Fast Breeder Reactor Arrays",

Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, May 1981.

l-207.-

Y.

Yang,." Heat Transfer Through A Randomly Packed Bed l

of Spheres by the Monte Carlo Method", Ph.D. Disser-tation, Mechanical Engineering (Nuclear Engineering)

Department, The University of Texas at Austin, Decem-ber 1981.

208.

M.M.~Razzaque, " Finite Element Analysis of Combined Mode Heat Transfer, Including Radiation in Gray Participating Media", Ph.D. Dissertation, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, May 1982.

t

.n

,---.~.,,-.,g,,,,n,-.,,-,..,,

,.n

.,.n., -,..,,... -,,,,-,.

3-y

/

/*

/.

t

~

r

+

j

+

209 M.A.

Ross and D.E.

Klein, " Synthetic Fuel Production Using Texas Lignite and a VHTR for. Process Heat",

Nuclear Technolony,63113, ( M a r,t h 1982).'

T.L'.5 anders and D.E.

Klein, "A Modit,ied Nunerical S

,210.

Scheme for GCFR Flow Transient Analyais f a

Trans.

% Amar.,Nucl.

Soc., 33, (November 1981).

211.

H.A.

Ross and D.E. Kle'in, " Synthetic hael Production Using Texas Lignite and a Very High Temperature, Gas Cooled Reactor for Process Heat and Electrical Power Generation", The University of Texas at f.ustin Centar,for Energy Studies Research Report, la, May 1

1981.

212.

M.M. Razzaque, J.R.

Howell, and D.E.

Klein,," Finite Element Solution of Heat Transfer for Gas Flow Through a Tube", AIAA Journal 20:7, July 1982.

213 S.

Yang, J.R.

Howell, and D.4, Klein, " Radiative Heat Transfer Through-a Randomly Packed Bed of Spheres by the Monte Carlo' Method", AIAA/ASME 3rd Joint Thermo-physic's, Fluids, Plasma & Heat Transfer Conference, ASME S2-HT-5, St. Louis, Missouri, Jun'e '1982.

214.

J. Andersen and D.E.'Klein, bt al.,l" Peer Review of the Preliminary Design and Program Interfaces for the Iransuranic Waste Eggkage Iransporter,(TRUPACT)",

Sandia Report, SAND 81-2405, June 1982.

215.

T.L. Sanders and D.E.

Klein,'" Transient Thermal-Hy-demolic Analysis Using n Modified Version of COBRA-IVS, 7tn International Heat Transfer Conference, Musion, Germany 82-IHTC-104, September 1982.

I 216.

S.

Yang, J..R.

Howe 31, and D.E.

Klein, " Monte Carlo Simulation of Thermal Conduction Through a Randomly Packed Bed of Spheres", 7th International Heat Transfer Conference, Munich, Germany, 82-IHTC-91, September 1982.

217 T.L.

Sanders and D.E.

Klein, " Comparison Analysis of Savere Flow Blockages for Computational Efficiency Using COBRA", Proc. from Gas-Cooled Reactor 2 Today Conference, British Nuclear Energy Society, London,' England, September 1982.

J

218.

M.M.

Razzaque, J.R.

Howell, and D.E.

Klein, " Finite Element Solution of Radiative Heat Transfer in a Two-Dimensional Rectangular Enclosure with Gray Participating Media", 82-WA/HT-51, ASME Annual Meet-ing, Phoenix, Arizona, November 1982.

219 J.B. Smathers, N.E.

Hertel, and R.G.

Graves, "In Phan-tom Photon Spectra Measurements for High-Energy Neu-tron Therapy Sources", Proc. from the Fourth Symoosium on Neutron DosimetrvtBeam Desimetry, Neuherberg/ Munich, Germany, June 1981.

220.

N.E.

Hertel, B.W.

Wehring, and J.J. Dorning, " Measure-ments and Analyses of High-Energy Neutron Transport Through Tungsten", accepted for publication (subject to revision) in Nucl. Sci. and Enar., November 1981.

221.

Y. Kunimoto, J.W.

Davidson, and N.E.

Hertel, "A Core Inventory Model for Fuel Trajectory Analysis in Fu-sion-Fission Symbiotic Systems", Trans. Amer. Nucl.

Soc..

41, 1978 (June 1982).

222.

N.E.

Hertel and W.E..Murphie, "The Use of Neutron and Gamma-Ray NE-213 Spectral Measurements and Calcu-lations to Obtain Dosimetric Information for DT Neu-trons", Medical Physics, 10r66, (.1983).

223 R.

Laucius, J.W.

Davidson, and N.E.

Hertel, "Calcu-lation of the Differential Efficiencies of Organic Scintillators to Neutrons Above 10 MeV", Trans. Amer.

Nucl.

Soc., 33, 625 (November 1982).

224.

J.W.

Davidson and N.E.

Hertel, "Bonner Ball Detection Responses for Neutrons from Thermal Energies to 17 3 MeV", Health Physics Society Annual Meeting, Balti-more, Maryland, 1983 225.

N.E.

Hertel, J.W.

Davidson, and R.M.

Laucius, "NE-213 Response Matrix for Neutron Spectrometry Up to 50 MeV", Health Physics Society Annual Meeting, Balti-more, Maryland, 1983 226.

N.E.

Hertel, J.W.

Davidson, and R.H.

Laucius, "An NE-213 Response Matrix to 50 MeV", Trans. Amer.

Nucl. Soc, AS, 607 (1983).

..-=

l E

4 i

227 J.W.

Davidson and N.E.

Hertel, "An Equal Probability-Neutron Detection System Using Bonner Spheres",

Trann. Amer-Nucl-Soo, 15, 609 (1983).

228.

J.E. Hamann, " Thermal Analysis of a Spent Fuel Rail-car Shipping Cask in an Engulfing Fire", Masters

+

Thesis, Mechanical. Engineering (Nuclear Engineering) 4 Department, The University of Texas at Austin, May 1983 7

229.

M.

Ally, "Preconcentration Method for the Determin-ation of Uranium, Thorium and Transition Elements Using X-Ray Fluorescence and Activation Analysis",

Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, May 1983 j

230.

G.F.'Polansky, "A Finite Element Analysis of Incom-pressible Laminar and Turbulent Flow with Heat Trans-for past Irregular Surfaces", Ph.D. Dissertation, j --

Mechanical Engineering (Nuclear Engineering)' Depart-ment, The University of Texas at Austin, May 1983.-

i 231.

M.M.

Razzaque, J.R. Howell, and D.E.

Klein, " Coupled Radiative and Conductive Heat Transfer in a Two Dimensional Rectangular Enclosure with Gray Partici-pating. Media Using Finite Elements", ASME/JSME F

Thermal Engineering Joint Conference, ASME-H-35 Honolulu, Hawaii, March 1983 232.

S.

Yang, J.R.

Howell, and D.E.

Klein, " Radiative

~

Heat Transfer Through a Randomly Packed Bed of Spheres by the Monte Carlo Method", Journal of Heat Transfer, 12512, 325 (May 1983).

i' 233.

M.M.

Razzaque,' J.R.

Howell, and D.E.

Klein, " Finite Element Solution of Radiative Heat Transfer in a L

Two Dimensional' Rectangular Enclosure with Gray l-Participating Media",-(accepted by the Journal 21 l

Heat Transfer).

l 234.

M.M.

Razzaque, J.R.

Howell, and D.E.

Klein, l

" Coupled Raciative and Conductive Heat Transfer i

in a Two Diadnsional Rectangular Enclosure with Gray Participating Media Using Finite Elements",

Journal'of Heat Transfer, 121, 613 (1984).

u.

.~..

235.

E.M.B. Sorensen, C.W.

Harlan, M.D.,

T.L.

Bauer, and A.

Pradzynski, " Hepatocyte Changes Following Selenium Accumulation in a Freshwater Teleost",

The Amer. Journal of Forensic Medicine and Patholozy, 313, 8 (1982).

236.

E.M.B.

Sorensen and T.L.

Bauer, "A Correlation Between Selenium Accumulation in Sunfish and Changes in Condition Factor and Organ Weight",

Evironmental Pollution Series A,

0141, 357 (1984).

237 E.M.B. Sorensen, T.L.

Bauer, J.S.

Bell, and C.W.

Harlan, " Selenium Accumulation and Cytotoxicity in Teleosts Following Chronic, Environmental Exposure",

Bulletin of Environmental Contamination and Toxicolorv, 23, 699 (1982).

238.

E.M.B. Sorensen and T.L.

Bauer, " Selenium Induced Hematological Dyscrasia in Teleosts", Archives Environ. Contam. and Toxicology, 12, 135 (1983).

239 E.M.B.

Sorensen, P.M.

Cumbio, T.L.

Bauer, J.S.

Bell, and C.W.

Harlan, " Histopathological, Hematological, Condition Factor and Organ Weight Changes Associated with Selenium Accumulation in Fish from Belews Lake, North Carolina", Archives Environ. Contam. gad Toxicology, 13, 153 (1984).

240.

E.M.B.

Sorensen, R.R.

Hitchell, A.

Pradzynski, T.L.

Bauer, and L.

Graham, "Sterological Analyses of Hepat-ocyte Changes Parallel Arsenic Accumulation in the Livers of Green Sunfish", (accepted by The Journal of Environmental Pathology. Toxicology and Oncolory).

241.

N.E.

Hertel and J.W.

Davidson, "The Effect of Cad-mium Covers on Bonner Sphere Responses", to appear in the Proc. of the Personnel Radiation Dosi-metry Symoosium, Knoxville, Tennessee, October 1984.

242.

N.E.

Hertel and J.W.

Davidson, "The Responseoor Bon-ner Spheres from Thermal Energies to 17 3 MeV", (ac-cepted for publication Nuclear Instruments and Methods, (February 1985).

t_

243 A.

Patterson-Hine, J.W.

Davidson, and D.E.

Klein,

" Characterization of Product Buildup in Continuously Processed Molten Salt Fusion Breeder. Blankets",

Trann. Amer. Nuol. Soc., ji, (1983).

244.

A.

Patterson-Hine, J.W.

Davidson, and D.E.

Klein,

" Contributions to the Thermal Power of Continuously Processed THHR Molten Salt Blankets", 10th Sympo-sium on Fusion Engineering, Philadelphia, Pennsyl-vanie, December 5-9, 1983

^245.

G.F.

Polansky, J.P.

Lamb, and D.E.

Klein, "A Fin-ite Element Analysis of Incompressible Laminar and Turbulent Flow with Heat Transfer", presented to the 5th International Symposium on Finite Elements and Flow Problems, The University of Texas at Austin,.

L Austin, Texas, January 23-26, 1984.

246.-

M.

Ally, D.E.

Klein, and T.L.

Bauer, "Preconcentra-tion Methods of Trace-Elements in Water for EDXRF and INAA", 5th International Conference on Nuclear Methods in Environmental and Energy Research, Mayaguez, Puerto Rico, April 2-6, 1984.

247.

A. - Patterson-Hine, " Characterization of the Effects of Continuous Salt Processing on the Performance of Molten Salt Fusion Breeder Blankets", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Depart-ment,'The University of Texas at Austin, May 1984.

248.

E.

Ibrahim, " Determining the Minimum Plasma Minor Radius for a Power Balanced Reversed Field Pinched Device at Ignition", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, December 1984.

249 M.G.

Krause, " Design and Fabrication of a Texas As-sembly for~the Evaluation of Heat Transfer in Flow Past Discrete Roughness Elements", Masters Thesis, Mechanical Engineering (Nuclear Engineering) De-partment, The University of Texas at Austin, December 1984 250.

D.E.

Klein and.W.H. Miller, " Student ANS Branch Involvement in Public Information", Invited Paper, Trann. Amer. Nucl.

Soc., June 1984.

251.

F.Y.

Iskander, D.E.

Klein, and T.L.

Bauer, " Toxic and Other Elements in American Cigarette Tobacco Compared.with International Brands", 17th Annual Meeting of Texas Association for Radiation Research, Denton,_ Texas, November 1984.

252.

F.Y.

Iskander and R.H. Filby, " Formation of Anatase from Ti(IV)-pre-asphaltene Complexes under. Coal Liquefaction Conditions", Fuel, 13, 280 (1984).

253 F.Y.

Iskander and R.H.

Filby, "Speciation of Titan-ium in Solvent Refined Coal Using SESC-INAA", Proc.

of American Nuclear Society Meetina, Fifth Inter-national Conference, Mayaguez, Puerto Rico,.

April 2-6, 1984.

254.

T.L.

Sanders, D.E.

Klein, and H.E.

Crawford, "A

4 Liquid Metal Facility for the Analysis of Phenomena Related to the Magnetohydrodynamics of Fusion Related Systems", Sixth Topical Meeting on the Technology of Fusion Energy, San Francisco, Cali-fornia, March 1985.

255.

T.L.

Sanders, D.E.

Klein and M.E.

Crawford, "A

Liquid Metal Facility for the Analysis of HHD Ef-fects in Fusion-Related Systems", Fusion Technolorv, 111. (1985).

256.

T.L.

Sanders, "Magnetohydraulic Flow Through a Packed Bed of Electrically Conducting Spheres", Ph.D. Dis-sertation, Mechanical Engineering (Nuclear Engineer-ing) Department, The University of Texas at Austin, May 1985.

257 A.

Patterson-Hine, J.W.

Davidson, D.E.

Klein, and J.D.

Lee, " Characterization of the Effects of Con-tinuous Salt Processing on the Performance of Molten Salt, Fusion Breeder Blankets", accepted to J.

of l

Fusion Enerav.

258.

F.Y.

Iskander, " Neutron Activation Analysis of an Egyptian Cigarette and its Ash",

J.

Radionnal.

Nucl. Chem., 33, 511 (1985).

i 259 F.Y.

Iskander, " Egyptian and Foreign Cigarettes.

1.

Determination of Trace Elements in Cigarette-Filter Before and After Smoking",

J.

Radionnal.

Nucl. Chem., 31, 191 (1985).

I

i e

260.

F.Y.

Iskander, " Cigarette Ash as a Possible Source of Environmental Contamination", Environ. Pollut.

(Series B), 11, (1986).

261.

F.Y.

Iskander, " Egyptian and Foreign Cigarettes.

2.

Determination of Trace Elements in Tobacco, Ash, and Wrapping Paper",

J.

Radionnal. Nucl. Chem., 31, 107 (1986).

262.

F.Y.

Iskander, T.L.

Bauer, and D.E.

Klein, " Deter-mination of 28 Elements in American Cigarette Tobac-co by Neutron Activation Analysis", Analyst, 111, 107 (1986).

263 F.Y.

Iskander, D.E.

Klein and T.L.

Bauer, " Deter-mination of Trace Impurities in Aspirin Tablets N

by Neutron Activation Analysis",

J.

Radioanal.

Nuol. Chom, SI, 353 (1986).

264.

M.M. Morad, F.Y.

Iskander, L.W.

Rooney, and C.F.

Earp, "Physico-chemical Properties of Aikali-cooked Corn Using Traditional and Presoaking Procedures",

accepted to Cereal Chem.

265.

F.Y.

Iskander and M.M. Morad, " Neutron Activation Analysis of Texas Hard Red Winter Wheat and its Milling Fractions", American Association of Cereal Chemistry, 70th Meeting, Orlando, Florida, paper 151, 1985.

266.

F.Y.

Iskander, " Neutron Activation Analysis for Assessing the Concentration of Trace Elements in Laboratory Detergents", accepted to Int.-J.

Anol.

Radiat. Isotones, i

267 F.Y.

Iskander, T.L.

Bauer, and D.E.

Klein, "Some Considerations of Elements Content of cigarette Wrapping Paper", accepted to TAPPI.

268.

F.Y.

Iskander, M.M.

Morad, D.E.

Klein, and T.L.

Bauer, " Protein, In-Vitro Protein Digestibility and Minerals Content of Hard and Soft Red Wheat Varieties", submitted to Cereal Chem.

269.

J.A.

Adepetu, 0.I.

Asubiojo, F.Y.

Iskander, and T.L. Bauer, " Elemental Composition of Nigerian Harmattan Dust", submitted to Environmental Science and Technolorv.

270.

F.Y.

Iskander and M.M.

Morad, " Minerals and Pro-tein Contents in Texas Hard Red Winter Wheat and Its Milling Fractions", submitted to Food Science.

271.

F.Y.

Iskander,-D.E. Klein, T.L.

Bauer, and M.M.

Morad, " Protein and Nutritional Elements Content in Texas Wheat", 18th Annual Meeting of Texas Association for Radiation Research, San Antonio, Texas, November 1985.

272.

F.Y.

Iskander and M.M.

Morad, "Multielement Deter-mination in Wheat and Bran", submitted to Radiaochem.

y';

Radionnal. Letters.

273 O.I. Asubiojo, J.A.

Adepetu, and F.Y.

Iskander,

" Determination of the Chemical Composition of Ni-gerian Harmattan Dust by Instrumental Neutron Acti-vation Analysis", The 7th International Conference, Modern Trends in Activation Analysis, Copenhagan, Denmark, 1986.

274.

F.Y.

Iskander, "Effect of Maturity on the Mineral Content of Soybeans", submitted to Food Chem.

I i

y 9

1. '92 COLLEGE OF ENGINEERING

1. m 'l i+)pl').Y C

i THE UNIVERSITY OF TEXAS AT AUSTIN l'

P y

\\.

A.

DepartmentolAiechanicalEnginaring N:sclearEngineeringProgram Austin, Texas 7S712 (312)471-3136 March 26, 1986 Director of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C.

20555

Dear Sir:

Enclosed are twelve (12) copies of the calendar year 1985 Annual Report. These are being submitted according to 10CFR Section 50.59.

Sincerely, f

')<), I.%-

Dr. T.L. Bauer Assistant Director Nuclear Engineering Teaching Laboratory TLB:bjm Enclosures cc:

Dr. Dale Klein 1

%.