ML20206D653

1986 Annual Rept of Univ of Texas at Austin

ML20206D653
Person / Time
Site:	05000192
Issue date:	12/31/1986
From:	Bauer T TEXAS, UNIV. OF, AUSTIN, TX
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 8704130391
Download: ML20206D653 (65)

Text

.

t 1986 ANNUAL REPORT of The University of Texas at Austin Nuclear Engineering Teaching Laboratory Taylor Hall Room 104 January 1, 1986 - December 31, 1986 D. E. Klein, Director 512/471-5136 T. L. Bauer, Supervisor 512/471-5787 January 1987

~

8704130391 86fASI PDR ADOCK 05000192 R PDR

1986 TABLE OF CONTENTS Li s t o f Tab l e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 List of Figures.................................. 4

1. 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..................... 17 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.......................... 29 A. NRC Inspections B. TDH Inspections VI. Public Service Activities....................... 30 VII. Research Activities............................. 31 VIII. Publications from the Nuclear Engineering Teaching Program........................... 39 A. Ph.D. Dissertations B. Masters Thesis C. Reports and Papers 2

i 1966 l

l List of Tables 1

j. IAbit EQ.a. 2AEfL 1

l

1. Administration and Committees 11

2. Facility Personnel 12 3 University Courses 16

4. Reactor Safety System 18

5. Safety System Events 18

6. Performance Data 19

7. Annual Utilization Data 20

8. Summary of Personnel Radiation Exposures 24

9. Radiation Exposure Groups 24

10. Laboratory Radiation Levels 25

11. Laboratory Contamination Levels 25

12. Environmental Surveys 26 13 Monthly Gaseous Waste Discharge 27

14. Monthly Liquid Waste Discharge 28

15. Monthly Solid Waste Disposal 28

16. Research Funding 32 3

1986 List of Figures Firure h f.agg

~1. Site Location of Nuclear Engineering Teaching Laboratory 7

2. Floor Plan of Nuclear Engineering Teaching Laboratory 8 f

3 Organization Chart of the Nuclear Engineering Teaching Laboratory 10

4. Annual Burnup versus Operation Year 21

5. Samples Irradiated versus Year 21 9

4 S

8 4 i

1986 I. INTRODUCTION This report has been prepared by the staff of the Nuclear Engineering Teaching Laboratory (NETL), The University of Texas at Austin, to satisfy the reporting requirements of the U.S. Department of Energy Contract Number At-(40-1)-3919 and 10 CFR 50.59. The report covers the period from January 1, 1986 to December 31, 1986.

The Nuclear Engineering Teaching Laboratory (NETL) is a part of the Mechanical Engineering Department in the College of Engineering at The University of Texas at Austin. The program's major equipment consists of a 250 kW TRIGA Mark 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 Walton 1h MeV neutron generator, a Lockheed Aerojet suboritical assembly, a 750 curie Co-60 irradiator and 150 kilovolt industrial X-ray source. Also available are isotopic neutron sources that include three californium-252 sources and six plutonium-beryllium sources and reference sources for instrument calibrations. A wide array of detectors and electronic equipment are available to provide measurement and analysis capability of laboratory produced or maintained radiation sources.

! Changes in the NETL program occur as a continuing response to achieve effective operation of various NETL projects and program i development. A major planning effort, to move the location of the laboratory activities, was initiated during the 1984 calendar year and a 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.

Project authorization was approved by The University of Texas l System Board of Regents on October 13, 1983 Submittal of the project proposal was made to the Nuclear Regulatory Commission (NRC) on November 9, 1984 for the construction permit and operating license. An NRC site visit January 22 thru 24,1985 was made at the proposed project site prior to evaluation of the application. A construction permit was issued June 4, 1985. Preliminary architectural and engineering plans were approved by The University of Texas System Board of Regents on August 8, 1985. Final plans were approved on April 10, 1966 and bid to ceneral contractor was awarded on December 4, 1986. CIT Construction Inc. of Stafford, Texas, is specified as the general contractor and start of construction is projected for January 15, 1987 Facility completion is scheduled for 16-18 months after start of construction.

5

}{U n, 1986 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 d 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 extead facility capability. These include above ground shield structure

> for adeess to horizontal beam tubes, and increased pcwer and pulse pcraceters. Plans are to utilize the present fuel 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.

4 L

)

i i-6

19db

__ll l l l[

!I I fll g / ll Il 11 l i E

I 11 ILJI ~

I g, ,

25 [iB ikFf'4tQii li -

~~

,dm , Rad 3_,

~

.~.TI, ^ .

y l

s wg,s sm, co e b q I g nmN r

Figure 1 ea b ng borato 7

l 'J UU l .m ..r.

.}....... . .

!.! I.!

N+.. ..

.: 1...

a: t l,. .. :I

=p IH-

[ .

,.:::::{yA=f.: =.dl:

>-

• x--s, ,:

. a.' .

4- .

s

== I,.;) .:

..~, .

... ... ... . r....... , g . .,=A..

_ m 2/; c' ii 'l I: A -

$Yl? lll :l!

f~ -

i,. .i.e

. w cli- -Li,  ! 3 f=='r.:*

• i;13.*.3 k.F:..' ". if.y::::t*.t$.... u t::O, omne i.

t. .H 8

a - _ d' . U  !! -

6.. ,,

.... l .: - -

l TAYLOR 131 N _ ___________{ 1 1

1 JL_ i

• ] Aeoa De.ellshed flH4-ell l Power plaat Ceestrisetton l

-k g Center In Presses, llHS-Mi 0 feel 16tte. g

( 6 i

w .

I n.. in g i

__ _ .m y\

I  % Ih.elset hgtaee. tag Teaching f ,c _..... .

Area tenewsted flH 4.M)

C t., Hi . o.pt. w e.t.. .. . orn...

I a i h TATLOS NALL l

t I

Figure 2 Floor Plan of Nuclear Engineering Teaching Laboratory 8

1986 II. LABORATORY ADMINISTRATION A. Crganization 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 /operatcr, operator, and secretary. Budget support is divided into full time positions for supervisor, technician and research associate; half time for an operator; and 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 KETL 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 23, July 28, October 28 and January

28. The committee composition is shown in Table 2. Committee responsibilities are the reactor operation, associated facility activities.and engineering programs.

2. Radiation Safety Committee The Radiation Safety Committee convened to review radiological safety practices at the university during each academic term. Committee aceting dates were April 18 and November 11. The comuittee composition is shown in Table 2. Committee responsibilities are the activities of l university research programs that utilize radiation source materials.

I 9

.nu Office, President University of Texas at Austin Radiation

-Safety 1

Committee Executive Vice President and Provost Dean College of Engineering Nuclear Reactor Committee Chairman Department of Hechanical Engineering t

Director

, ___ . Nuclear Engineering ,

Teaching Laboratory Supervisor L . Reactor _J Operations Responsibility Communication --

Figure 3 Organization Chart of the Nuclear Engineering Teaching Laboratory 10

1986 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

!! ember (1987) !! ember (1989) Member (1991)

J.S. Briscoe R.B. Baldwin III J.S. Blanton B.B. Milburn Jess Hay S.H. Eatliff T.B. Rhodes  !!ario Yzaguirre Bill Roden Chancellor Hans Mark The University of Texas at Austin President (app. 9/1/85) William H. Cunningham Executive Vice President and Provost (app. 9/1/85) Gerhard J. Fonken Dean of the College of Engineering Earnest F. Gloyna Chairman of the Department of Mechanical Engineerin6 Grady H. Rylander fluclear Reactor Cnnmittee Chairperson: H. L. Marcus (app: 9/1/77)

Member: N. E. Hertel (app: 4/1/79)

Member: D. E. Klein (app: 9/1/77) l' ember: J. O. Ledbetter (app: 9/1/71)

Member, student: R. D. Manteufel (app: 9/1/85)

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 Cnmeittee 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)

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

Ex officio member: W. H. Cunningham (app: 9/1/85) j 11

I 1986 Table 2 Personnel Facility Personnel Staff Director D.E. Klein Assistant Directcr/ Supervisor T.L. Bauer Research Associate F.Y. Iskander

!!uclear Technical Specialist H.G. Krause Nuclear Technical Specialist D.H. Eppes Administrative Secretary B.J. Babich Technical Secretary D.L. Wood Laboratory Research Assistant R. Clements Suonort Personnel Safety Personnel Safety Coordinator H.W. Bryant Radiation Safety Specialist L.W. Hamlin Researchers College of Engineering T.L. Bauer Fluclear Reactor Lab.

F.Y. Iskander Neutron Activation Lab.

N.E. Hertel Nuclear Radiation Lab. Assoc. Prof.

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

J.!!. Freeland flome Economics Assoc. Prof.

Students Graduate Assistants

!!. Ally A. Gaines L. Grater R. Hartley A. Patterson-Hine B. Kolda R. Savage N. Poor R. Manteufel D. Smith A. Heger Student Assistants R. Clements 12

1986 D. 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:

1. The main effort in the program was associated with continuing development of a new reactor facility at Balcones Research Center as well as a decommissioning arrangement of the existing facility.

Plans have been developed and work with NRC personnel has progressed in an orderly manner. Bids for the new facility will be obtained in the near future (see footnote).

2. The reactor remained operating efficiently while construction and destruction contined all around it. In an extensive NRC inspection in April the Nuclear Reactor Teaching Laboratory has imposed on it an extensive paperwork load associated with the proposed move to B.R.C. This will transfer to a great deal of effort associated with both the new faculty and decommissioning of the present one. This phase will require close control to assure adequate and timely resources are available.

In general the people involved in the program have maintained a positive attitude during another busy year.

Note: Bids for the facility at the Balcones Research Center were opened October 21, 1966 and award of the general contract was approved December 1986. The University of Texas System Board of Regents entered into a contract with CIT Construction Inc. of Stafford, Texas. Total project cost for the proposed facility was

$5,452,560. An additional $408,140 is being held in reserve for dismantling activities at the Taylor Hall facility. Authorized total cost is $5,860,700.

13

1986 III. LABORATORY DEVELOPMENT

'A. ' Organization Cr. Dale E. Klein continued as the Director and Dr. Thomas L. Bauer j continued as Reactor Supervisor / Assistant Director during the past year. -

One change was made in the facility staff during the 1986 calendar year. The position of technical secretary was created to replace the position of-administrative secretary, Dianne Wood filled the created position to repalce the transfer of Bonnie Babich (Malek).

One change in the Nuclear Reactor Committee replaced the student nember on committee. Other key faculty and university support personnel remained unchanged.

l 1

[

Mr. Bob Clements completed training for the Senior Reactor Operator and successfully passed licensing examinations.

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 I: ark 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 750 curie Co-60 irradiator, vertical neutron beam tube, suberitical assembly, industrial x-ray source, 14 MeV neutron generatcr, 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 reactor facility. Courses utilizing the reactor and associated facilities are listed in Table 3 Classes, organizations and troups are provided tours or demonstrations of the reactor and its associated experimental facilities. Approximately 1100 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 Huclear Regulatory Commission, the Nuclear Reactor Counittee of The University of Texas, the Director of the Nuclear Engineering Teaching 14

1986 Laboratory, the Radiation Safety Committee and the Texas Department of Ecalth 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.

Student 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 gamna ray spectroscopy with an HpGe detector coupled to a microcomputer controlled acquisition and analysis system, Si(L1) 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.  !!uclear Radiation Laboratory The Nuclear Radiation Laboratory is utilized by staff and students of the Nuclear Engineering Program at The University cf Texas at Austin.

The laboratory is located in an area of the Engineering Science Duilding. A 14 lieV 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 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.

I 15

1986 Table 3 Courses Utilizing the Reactor and Associated Facilities Course Number Course Description

!!echanien1 Enaineerine 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.

HE 377K Projects in Mechanical Engineering - individual study and experiment projects for undergraduates.

ME 389R Nuclear Engineering Laboratory - studies for graduate students in nuclear methods in measurement and analysis.

HE S389R Special projects course for nuclear engineerirc 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 ja 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 PilR 370K Nuclear Pharmacy - senior level course in measurement and analysis methods with nuclear pharmaceuticals.

16 u

1986 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 operating procedures and other required procedures remained unchanged.

Licensed activities were performed by three persons with Senior Operator Permits, T.L. Bauer, M.G. Krause and R. Clements. 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 L

performed was neutron activation to support various research activities.

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

B. Reactor Shutdowns Reactor shutdowns (scrams) occurring during the reporting period are sunmarized 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 operater initiated scrams 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 l during this reporting period to previous reporting periods.

I 17

1986 Table 4 Reactor Safety System (scrams)

Safety System 0 Operator Error 1 Instrument Error 8 Power Failure O Subtotal 9 Intentional 3 Total 11 Table 5 Safety System Events (inadvertent) 1971 13 1981 7 1972 6 1982 6 1963 to 1973 10 1983 6 1964 9 1974 4 1984 5 1965 3 1975 7 1985 2 1966 4 1976- 5 1986 9 1967 3 1977 9 1968 11 1978 11 1969 15 1979 12 1970 11 1980 7 18

1986 Table 6 Performance Data 1986 Reactor Operation Hours, Fuel Burn-up and Irradiated Samples Quarter Reactor Total Burn-up Samples Operation Fuel Irradiated (hours) (kwhrs) (number)

First 56.3 6118 224 Second 38.8 4022 138 Third 57 7 7748 255 Fourth 30 3 772 16 Total 183 1 18660 633 Notest (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 that are irradiated in the experimental facilities of the reactor such as the RSR, PNT or CT.

19

1986 l

Table 7 Annual Utilization Data Igat Reactor Total Burn-up Samples Operation Fuel Irradiated (hours) (kwhra) (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 1986 183 1 18660 633 Total 4428.8 562145 18632 Notei (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.

20

1986 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 consisted primarily of routine repair and adjustment.

E. Facility Chan6es Operation of the reactor in the pulse mode remains discontinued until the operation characteristics of the compensated chamber as related to pulsing is established. This evaluation is 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.

No other facility changes were made during this reporting period.

4 21

I' 1986.

Burnup a

(Dousands)

Totat Ye-80 7 50; 40k f i 19 b ' ": n h O 20j .I,p ! I .

j *[! q - p n p ~l f

~~

8 67 68 69 73 7172 73 74 75 76 77 78 79 BB 31 S2 33 El 35 ff Annual Burnup versus Operation Year Figure 4 Samples . -

J 75g, in n 3000* __

q 2!30- .  !;'

2230i -

1500-l

[ f _, O 1002- 4 i- .  ! .1 c-l 5095 , ,' ; .

f-~ qp_ !j , ., y

] n t]

O-67 68 69 70 71 72 73 74 75 76 77 78 79 83 31 82 43 34 35 h Figure 5 Samples Irradiated versus Year i

22

1986 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 Table 12.

II . Radioactive Effluents

1. Gaseous Wastes a

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

Although air leakage from the laboratory is restricted, an effective air change rate of two per hour (.36 m3/see) is assumed 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 during the reporting period. Efforts are made to avoid liquid waste disposal by appropriate evaporation or absorption te'chniques for small volumes and purification by resin treatment for large volumes.

3 Solid Waste l The activity and amounts of solid waste discharged during the f reporting period are summarized in Table 14. All solid waste l materials were packaged and shipped, along with radioactive waste generated in other departments, by the Safety Office. Waste l shipments are performed by Isotex, Friendswood, Texas.

l l

l l

23

1966 Table 8 Sumelary of Personnel Radiation Exposures Rang;g af Exoonure gg h gf Individunis .

Staff Students Visitors No measurable exposure 6 17 1089 Measurable exposure less than 0.1 0 3 0 0.1 - 0.25 1 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 Groups Excosure agr. Individuni h ErfJR Croun Average Greatest Staff < 20 100 Students < 20 20 Visitors < 10 < 10 24

1986 Table 10 Laboratory Radiation Levels Location Averare (mR/hri Maximum (mR/hr)

Control Console Area 2x10^-3 6x10^-2 10 ft. from core axis l 6 ft. above pool t'ater System Area 1x10^-2 1x10^+1 12 ft. from core axis 4 ft. above pool Above Core 1x10^-1 7x10^-1 0 ft. from core axis 16 ft. above pool Table 11 Laboratory Contamination Levels Location Average F.animum Floors 25 dpm 269 dpm Surfaces 25 dpm 57 dpm Pool Water 500 pC1/1 4820 pCi/l 25

1986 Table 12 Environmental Surveys Location Average ILuisa 1 .01 mR/hr .01 mR/br 2 .01 nR/hr .01 mR/hr 3 .02 mR/hr .02 mR/hr i

4 .01 mR/hr .01 mR/hr 5 .01 mR/hr .01 mR/br 6 .01 mR/hr .01 mR/hr

7 6 pci/1 32 pci/l i

b 1

i l

r i

26

i 1986 Table 13'

!!onthly caseous Waste Discharge (argon-41)

Release p Ci m3 RPC  %!!ax Jan 575 14400 32 0.085 Feb- 15 370 1 0.003 Mar .680 16940 38 0.095 Apr 540 13480 30 0.075

!!ay 20 570 10 0.003 J u r. ' 295 7370 17 0.043 Jul 1520 37890 85 0.213-Aug 35 910 2 0.005 Sep 55 '1360 3 0.008 Oct 85 2100 5 0.013 11ov 75 1905 4 0.010 Dec ,,_._ Q 0 0 0 Total 3895 97295 17 0.043 Monthly Gaseous Waste Discharge (gas or particulate)

!!cnth Isotope Total Point of Release Fercent of Release Concentration Maximus (uci) (m*3) (pCi/m*3) () 205)

Jan .none Feb none

!!ar none Apr none

!!ay. none Jun none Jul none Aug none Sep none Oct none f,'o v none Dec none Total --

27

1986 Table 14 Honthly Liquid Waste Discharge Month Isotope Total Point of Release Percent of Release Concentration Maximum (uC1) (m'3) (pCi/m*3) (%)

Jan -

Feb -

Mar -

Apr -

!!ay -

Jun -

Jul -

Aug -

Sep -

Oct -

Nov -

Dec -

Table 15

!!onthly Solid Waste Disposal Unnih Isotope Total Form Remarks Release Chemical / Physical (uC1) (ft*3)

Jan -

Feb -

!!ar -

Apr -

!!ay -

J ur. -

Jul -

Aug -

Sep -

Oct -

Nov -

Dec -

28

s 1 as> +a. , A 1986 V. Laboratory Inspections A. NRC Inspections An NRC inspection was conducted by Messrs. G. L. Constable, R. C.

Stewart, and J. G. Luehman of Region IV and Messrs. D. Tondi and J. Dosa of the Office of Nuclear Reactor Regulation (NRR) during the period April 10-11, 1986, of activities authorized by NRC Operating License R-92 and Construction Permit CPRR-123 for the University of Texas.

Areas examined during the inspection included plant status; I&E Information Notices; logs, records, and organization; review and audit; requalification training; procedures; experiments; surveillancel emergency plan; health physics; transportation activities; and plans to build a new reactor facility. Within these area, the inspection consisted of selective examination of procedures and representative rcccrs, interviews with personnel, and observation by the inspectors.

Ilithin the scope of the inspection, no violations or deviations yere identified. The NRC did suggest that in order to meet the increased demands of the new facility (CPRR-123) and the decommissioning of the

, present facility (R-92), the level of NETL staffing be closely evaluated to assure adequate resources to meet commitments to the NRC, No NRC inspections took place during the calender year for the SHtf-180 special nuclear material license.

B. TDH Inspection November 20-21, 1986 The inspection consisted of a review of activities and radioactive '

materials used at The University of Texas at Austin as authorized by TCH License.

29

~ _ _ _ - - _ - ~ - - _ - - - _

1966 i.

1 VI. Public Service Activities A. Summer High School Science Teacher Symposium 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.

D. Lectures and Presentations On numerous occasions during 1986 the NETL ataff 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 I During 1986, 1089 persons visited the laboratory. The largest group visiting the laboratory were persons attending the Texas Energy Science Symposium. Numerous high school students also toured the facility during an event called The World of Engineering, designed to recruit students into the field of Engineering. Students from several local high schools and students from several non engineering related colle6e courses visited the facility. Numerous college engtpooring related classes and several student engineering organizatissa e430 toured the facility. Safety personnel such as Austin Fire Department, UT Police Department, UT Safety Office and the Texas Departnert 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 4

olement acquisition from the Northrup Corporation. The donated cask is designed for standard elements of TRIGA fuel and is to be available for loar. to other university reactor programs. A container to ship the l capty cask is also available. Charges for the cask use will apply only to shipment costs.

l i

i I

30

~

i 11986 VII. Research Activities

=The staff and users of the Nuclear Engineering Teaching Laboratory

. perform research, .as .both sponsored and non sponsored projects, in coveral different areas. Equipment and personnel are provided by the

. laboratory to' supplement the research efforts of facility users, that include students, faculty and others. The followinE section lists research projects active during the calendar year. Major research funding or grants are presented ~in Table 16 for users of the facility.

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

C. Texas Energy Science Symposium Sponsor: Texas Atomic Energy Research Foundation Persennel: Dale Klein, NETL Orlan Ihms, Texas Utilities Electric Company The Texas Atomic Energy Foundation has sponsored a symposium for outstanding high school science students for over 25 years. The program is intended to encourage students to pursue careers in the sciences or engineering. Yearly attendance for the 4 day symposium consists of about 250 students and 150 high school science teachers.

31

1986 Table 16 Research Funding Ecpartment of Energy Fuel Assistance Program New Nuclear Engineering Teaching Laboratory (includes D&D for existing facility) 5,860,700 Clectric Power and the Environment 20,000 6/86 - 8/86 Texas Energy Science Symposium 6/86-8/86 22,000 National Science Foundation 141,626 9/85 - 8/87 Sandia National Laboratories 90,000 2/85 - 9/87 TOTAL 6.134,326 32

1986 Heat Transfer and Friction Factor Analysis for Artificially 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 velocity and temperature profiles will be examined. New experimental techniques have been developed at The University of Texas at Austin to measure local heat transfer values surrounding discrete roughness elements. A test assembly to examine artificially roughened surfaces is being designed. In addition, a new analytical method has also been developed to determine R(h+) and G(h+) values without caking detailed velocity and temperature profile measurements. Analytical predictions will be made utilizing fundamental parameters in boundary layer theory coupled with the latest information on rough surfaces using ir.tegral techniques. Results from the experimental and spanyt&eal methods will be compared in order to gain insight as to the dominant mechanism involved for the use of discrete rough surfaces. This research has fundamental application for heat transfer augmentation.

Pressure Drop and Heat Transfer Measurements of Liquid !!etal Flowing in a Packed Bed Under the Influence of a tiagnetic Field Sponsor: Center for Fusion Engineering Texas Atomic Energy Research Foundation Personnel: Dale Klein, NETL Tom Sanders, NETL Larry Grater, Mech. Eng.

Mike Crawford,liech. Eng.

Description:

1he flow of electrically conducting fluids through perous media in the

, renonce of a magnetic field has recently begun to cencrate significar.t interest due to potential applications for fusion reactors. This study is designed to examine the pressure drop and heat transfer from a liquid petal (HaK) 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 raterial.

33

1986 Co2 Production for Enhanced Oil Recovery Using Texas Lignite and Huclear Process Heat ,

Sponsor: Center for Energy Studies ,

/ )

Personnel: D. Kolds, NETL

, Dale Klein, NETL  :

s 4

Description:

Carton dioxide miscible displacement is one method of enhanced oil i 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.

i Thermal Analysis of Nuclear Shipping Containers Sponsor: Sandia National Laboratories Personnel: Randy Manteufel 1 Dale E. Klein '

Description:

The thermal analysis of shippinE containers to be used in the transport of spent nuclear fuel is an important safety issue. Sandia National Laboratcries has been involved in safety issues for the  :

transport of nuclear material for many years. The University of Texas ,

at Austin *(NETL) has been involved in the specific issues of thermal analysis of these containers for several years. The current project is '

intended to benchmark a thermal analysis computer code (Q/TRAN) and pre and post proc'essinE sof tware PATRAH-G using four standard model problems. Comparisons will be mada with other applicable codes currently available at UT (including HEATING 5). Sensitivity studies will be performed to further evaluate Q/TRAN's suitability for therr.al analysis. Enhancements, if any, that will increase the current capabilities of the software will be suggested and developed if

. feasible. .

t T

Application of COBRA for shipping Cask Analysis ,

Sponsor: Sandia National Laboratories Personnel: Tom Dolbear, Hechanical Engineering Dale Klein, NETL

Description:

34 ,

__. . _.a r -- - - - - t - _ _ . .,. . +~_ _. .. . . - . .

l 1986 A thermal hydraulic computer code, COBRA, has been applied for both steady state and transient analysis. Previous research at The University of Texas at Austin involved the modification of the COBRA code and created a new version COBRA'GCFR 4P/UT. The current research is directed towards modifying COBRA *GCFR 4P/UT so that it may be applied y

to transient conditions for shipping cask analysis. One speciiric modification will be to develop a more sophisticated model for analyzing  ;

radiation heat transport. Results using this code will be compared with the results from Q-TRAN and HEATING-6 where possible. In addition, recommendations will be made regarding COBRA's use for dry storaEe analyses.

Transportation Analysis of Spent Fuel & High Level Wastes i Sponsor: Nuclear Engineering Teaching Laboratory Personnel: Danny Smith, NETL Dale Klein, NETL Thomas L. Bauer, NETL

Description:

j The current methodology (i.e., overall plan for analysis which

integrates discrete computer codes and other computational eleser.ts) for analysis of high-level waste and spent fuel transportation is not~

directed toward minimizing radiation exposure but rather is se attempt 4 to demonstrate minimum compliance with statutory and regulatory requirements. The current models (i.e., algorithms and ocepu$er codes) exhibit deficiencies and the thesis to be examined for this work is that more representative and 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 operations with the inter.t cf minimizing public and occupational exposure to radiation as well as exposure to radiation and non-radiation transportation risks '

(recognizing that elimination of risk is neither possible nor necessary but that achievement of exposures as low as reasonably achievable, ALARA, is prudent).

n Ieutron Transport Studies: Neutron Multiplication by Beryllium Sponsor: National Science Foundation Personnel: Nolan E. Hertel, Center for Fusion Engineering

Description:

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

]

1 35

1986 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 night well change. It is tantamount to the current fusion breeder concepts that the issue of beryllium neutron multiplication be resolved.  !

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

The beryllium experiment has been designed to measure uultiplication 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 measurementa 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.

Measurecent cf Nutrional and Other Elements in Eread 1

i 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.

Determination of Rare Earth and other Elements in Bottom Sediments from the Mediterranean Sea 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 flile where distribution of sediments is not governed by the bottom configuration. Fine sediments are distributed in deep depositional 36

l 1986 environments as well as in shallow water areas. The distribution of the sedinents 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 Baby Food in Nigeria ,

1 Sponsor: Nuclear Engineering Teaching Laboratory I 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 significant difference was observed between local and imported baby foods. However, nineral 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 roaturation on mineral content ( Al, Br, Cu, Cl, Fe, K, Mg, Mn, Na, Rb and Zn) has been studied. Three soybean varieties at different maturations stages were investigated. In general, no differences in the mineral content was observed at the different maturation stages.

How Method for the Determination of Iodine Value by Instrumental Ucutron Activation Analysis Sponsor: Nuclear Engineering Teaching Laboratory Personnel: F.Y. Iskander

Description:

Measuring the degree of unsaturation for oils and fats, as expressed by iodine value (I.V.), is an important step in the production of shortenings and margarine fats. Measuring I.V. is also of great 37

1986 iuportance to detect adulteration of vegetable oils with highly saturated animal fats and mineral oils. Early methods for the determination of I.V. depend on mixing a halogenating agent with the oil sample for a certain period of time, then titrating the residual unreacted halogenating agent. Most of these methods require preparation of special reagents, large sample size, and handling of corrosive or toxic chemicals. In addition, a long time (up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />) is required to prepare fresh reagents before starting the analysis.

A new microanalytical method has developed to measure the I.V. of oils and fats. Bromine vapor was used to saturate the ethylenio double bond in the oil samples. The quantity of Br reacted was determined by instrumental neutron activation analysis (INAA). The analysis of 50 samples was completed in 75-100 minutes (compared to several days by other methods).

Determination of Selenium. A prestudy to evaluate the minimum detection limit.

Sponsor: Department of Parks and Wildlife, State of Texas Personnel: T. L. Bauee F.Y. Iskander

Description:

The Department of Parks and Wildlife for the State of Texas is ir.terested in determining the concentration of seleniun, in fish, in several lakes across the state. To evaluate the quality of analysis, the department requested the participant laboratory to analyze a number of tiological material for selenium content. No significant variation was observed between the results reported from NETL and the certified values (except for one sample). Results of the analysis were intended to provide quality assurance information to the department on the measurement methods performed by several laboratories.

Selenium and Other Metals in Fish Tissues Sponsor: Department of Parks and Wildlife, State of Texas Personnel: T.L. Bauer F.Y. Iskander

Description:

Tissue from muscle and liver are to analyzed for several elements known to be toxic. Elements of interest are selenium, arsenic, mercury and zine.

38

VIII. Publications From the Nuclear Engineerine Teachine Laboratory Ph.D. Dissertations

1. R.D. O' Dell, "The Angular Thermal Neutron Spectrum in the Vicinity of the Interface Between Two Media", Ph.D. Dissertation, The University of Texas at Austin, 186 pp., January 1965.

2. B.E. Thompson, Sr., " Cryogenic Neutron Spectra Measurements Across a Discontinuity in Temperature and Properties", Ph.D.

Dissertation, The University of Texas at Austin, 149 pp., January 1965 3 M.G. Stevenson, " Investigations on the Macroscopic Nodal Approach to Space-dependent Nuclear Reactor Kinetics", Ph.D. Dissertation, The University of Texas at Austin, 203 pp., August 1968.

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

S. F.A. Rodriguez-Gonzalez, " Application of Neutron Activation Analysis to the Study of Interstitial Solid Solution of Oxygen in Miobium and in Miobium-Titanium Alloys", Ph.D. Dissertation. The University of Texas at Austin, 131 pp., August 1970.

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

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

Dissertation, The University of Texas at Austin, 231 pp., August 1971.

8. J.B. Whitworth, "The Development and Application of a Systematic Approach to Elemental Analysis in Forensic Investigations", Ph.D.

Dissertation, The University of Texas at Austin, 223 pp.,

December 1971.

9 J. Freim, " Theoretical and Experimental Evaluation of Nuclear Data and Calculation Techniques for Fusion Reactor Blanket Design", Ph.D. Dissertation, The University of Texas at Austin, 210 pp., December 1972.

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

11. J.F. Deen, "lieasurement 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 39

12. T.A. Parish, "Neutronic and Photonic Analyses of Simulated Fusion Reactor Blankets Containing Thorium and Natural Uranium", Ph.D.

Dissertation, The University of Texas at Austin, 329 pp., January 1974.

13 J.H. Vanaton, Jr., "Use of the Partitive Analytical Forecasting (PAF) Technique for Analysis of the Effects of Various Funding and Administrative Strategies on Nuclear Fusion Power Plant Development", Ph.D. Dissertation, The University of Texas at Austin, 459 pp., January 1974.

14 E.M.B. Sorensen, " Thermal Effects on the Biological Magnification of Arsenic in Green Sunfish, Lepomis Cyanellus", Ph.D.-

Dissertation, The University of Texas at Austin, 233 pp., May 1974.

15. S.P. Nichols, " Application of the Partitive Analytical Forecasting (PAF) Technique to the United States Controlled Thermonuclear Research Effort," Ph.D. Dissertation, Mechanical Er.gineering (Nuclear Engineering) Department, The University of Texas at Austin, December 1975.

16. C.T. Rombough, "The Total Energy Investment in Nuclear Power Plants", Ph.D. Dissertation, The University of Texas at Austin, January 1975.

17. J.L. MacDonald, " Investigation of Pattern Recognition Techniques for the Identification of Splitting Surfaces in Monte Carlo Particle Transport Calculations", Ph.D. Dissertation, The University of Texas at Austin, August 1975.

18. S. A. Hodge, " Determination of Friction Factors and Heat Transfer coefficients for Flow Past Artificially Roughened Surfaces",

Ph.D. Dissertation, Mechanical Engineering (Nuclear Engineering)

Department, The University of Texas at Austin, December 1979

19. Y. Yang, " Heat Transfer Through A Randomly Packed Bed of Spheres by the Monte Carlo Method", Ph.D. Dissertation, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, December 1981.

20. M.M. Razzaque, " Finite Element Analysis of Combined Mode Heat Transfer, Including Radiation in Gray Participating Media", Ph.D.

Dissertation, Mechanical Engineering (Nuclear Engineering)

Department, The University of Texas at Austin, May 1982.

21. G.F. Polansky, "A Finite Element Analysis of Incompressible Laminar and Turbulent Flow with Heat Transfer past Irregular Surfaces", Ph.D. Dissertation, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, May 1983 40

22. T.L. Sanders, "Magnetohydraulic Flow Through a Packed Bed of Electrically Conducting Spheres", Ph.D. Dissertation, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, May 1985.

Masters Thesis

1. K.L. Gilbert, " Neutron Flux Mapping of a Subcritical Reactor Core l with a Polyethylene Reflector", Masters Thesis, Physics (Nuclear  !

Engineerint) Department, The University of Texas at Austin, 61 (

pp., June 1961. l

2. T.T. Doss, " Neutron Density Distribution in an Unreflected Subcritical Reactor Core", Masters Thesis, Physics (Nuclear Engineering) Department, The University of Texas at Austin, 63 pp., June 1961.

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

4 H.W. Reed, "Effect of a Cadmium Control Rod on the Neutron Density in a Suboritical Reactor", Masters Thesis, Physics (Nuclear Engineering) Department, The University of Texas at Austin, 85 pp., August 1962.

5. P. Derananda, " Neutron Flux Distribution of a Subcritical Reactor Core with a Graphite Reflector", Masters Thesis, Physics (Nuclear Engineering) Department, The University of Texas at Austin, 40 pp., January 1962.

6. T.A. Fredericks, " Thermal Neutron Flux Distribution Due to a Plane Wave Source in an Unreflected Reactor Assembly", Masters Thesis, Physics (Nuclear Engineering) Department, The University of Texas at Austin, 107 pp., August 1963 7 D.G. Martin, " Film Detector for a Neutron Spectrometer", Masters Thesis, Physics (Nuclear Engineering) Department, The University of Texas at Austin, June 1963

8. M.L. West II, " Flux Decay Rate in a Reflected Subcritical Reactor", Masters Thesis, Physics (Nuclear Engineering)

Department, The University of Texas at Austin, 55 pp., August 1963

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

41

.~ .

10. J.B. Whitworth, "A Cryogenic Irradiation Device for the TRIGA Mark I Nuclear Reactor", Masters Thesis, Mechanical Engineering (Nuclear Engineerinr ' Department, The University of Texas at Austin, 52 pp., Ja .ary 1967

11. 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

12. G.F. Malan, " Transfer Function Analysis of Temperature and Xenon Feedback in Ccupled-Core Nuclear Reactor Systems", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, 69 pp., August 1967 13 F.H. Antunez-Castillo, " Gamma Radiation Dosimetry Techniques and Application to Mapping of The University of Texas Cobalt-60 Irradiation Facility", Masters Thesis, Physics (Nuclear Engineering) Department, The University of Texas at Austin, 60 pp., September 1968.

14. R. Valiente, " Neutron Radiography with The University of Texas TRIGA Nuclear Reactor", Masters Thesis, Physics (Nuclear Engineering) Department, The University of Texas at Austin, Auguct 1968.

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

16. M.A. ZuniEa, " Delayed Neutron Counting Technique for Uranium Determination", Masters Thesis, Physics (Nuclear Engineering)

Department, The University of Texas at Austin, January 1969 17 G.D. Atkinson, Jr. , " Investigation of the Dynamic Behavior of a Two-Region Subcritical Reactor", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, January 1969.

l 18. M. Gallardo, " Trace Elements in Six Quartz Samples by Nondestructive Neutron Activation Analysis Technique", Masters Thesis, Physics (Nuclear Engineering) Department, The University of Texas at Austin, January 1969 19 F.G. Pasos, "Nondispersive X-Ray Fluorescence Analysis using a Lithium Drifted Germanium Detector", Masters Thesis. Physics (Nuclear Engineering) Department, The University of Texas at i

Austin, 54 pp., January 1969

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

42

21. A.H. Urdaneta, "A Programmed Associative Analyzer", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, December 1960.

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

23 V.H. Chanto, " Neutron Activation Analysis of Chlorine and Bromine in Some Haliburton-Bancrof t Rocks and Minerals", Masters Thesis, Physics (Nuclear Engineering) Department, The University of Texas at Austin, January 1970.

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

25. E. Oelkers, Jr., "A Learning Method for Identification of Nuclear Reactor Point Dynamics", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, 165 pp., August 1970.

26. J.R. Deen, " Calculation of Resonance Integrals Using the Intermediate Resonance Approximation", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas et Austin, 140 pp., January 1970. .

I

27. C.T. Rombough, " Application of Queueing Theory to closed-Loop Computer-Reactor Control Systems", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, 78 pp., December 1970.

28. A.H.U. Bohorquez, "A Programmed Associative Analyzer", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, 98 pp., December 1970.

29. J.J. Chromik, " Experimental Determination of the Neutron Flux in The University of Texas Californium- 252 Irradiation Facility",

Masters Thesis, Mechanical Engineering (Nuclear Engineering)

Department, The University of Texas at Austin, 85 pp., December 1971.

30. M.B. Owen, " Fuel Management Using Dynamic Programming", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, 59 pp., May 1972.

31. C.E. Brauer, " Thermal Neutron Radiography with a Lithium-Lead Collimatcr-Filter", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, 64 pp., May 1972.

43

32. J.L. MacDonald, " Heuristic Learning Control for Nuclear Reactors", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, 131 pp., August 1972.

33 S.G. Barbee, "Neutronic Calculations in a Simulated Fusion Reactor Dianket", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, 259 pp., November 1972.

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

35. L.D. Hansborough, "Overall Tritium Considerations for Controlled Thermonucleur Deactors", Masters Thesis, The University of Texas at Austin, 154 pp., May 1973

36. M.E. Senglaub, " Cross Section Studies Based on the Statistical Model", Masters Thesis, The University of Texas at Austin,109 pp., August 1973

37. S.P. Nichols, " Experimental Determination of Neutron Fermi Age from Californium-252 Fission Spectrum to Cadmium Covered Indium Resonance in a Graphite Medium", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, 101 pp., January 1974.

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

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

40. J.W. Davidson, "A Cost-Benefit Analysis for Partitioning Strategies Involved in High-Level Nuclear Waste Management",

Masters Thesis, Mechanical Engineering (Nuclear Engineering)

Department, The University of Texas at Austin, May 1975

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

42. G.A. Taylor, "The Analysis of the Grid Spacer Pressure and Temperature Effects in SAGAP0", Masters Thesis, Mechanical 44

Engineering.(Nuclear Engineering) Department, The University of Texas at Austin, August 1979 43 D.D. Hsu, " Determination of the Relative Toxicities of the Fission Products Produced in the. Transmutation of Actinide Wastes", Masters Thesis, Mechanical Engineering (Nuclear lngineering) Department, The University of Texas at Austin, December 1979

44. If.A. Ross, " Electrical Power Generation and Process Heat Application for Coal Gasification and Liquefaction Using a Very-High Temperature and Gas-Cooled Reactor", Masters Thesis, 1:echanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, May 1980.

45. T.L. Sanders, "An Alternative Numerical Method for the Steady State and Transient Thermal-Hydraulic Analysis of Gas-Cooled Fast Breeder Reactor Arrays", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, May 1981.

46. J.E. Hamann, " Thermal Analysis of a Spent Fuel Railcar Shipping Cask in an Engulfing Fire", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, May 1983 47 M. Ally, "Preconcentration Method for the Determination of Uranium, Thorium and Transition Elements Using X-Ray Fluorescence and Activation Analysis", Masters Thesis, Mechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, May 1983

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

49. E. Ibrahim, " Determining the Minimum Plasma Minor Radius for a Power Balanced Reversed Field Pinched Device at Ignition",

leasters Thesis, Mechanical Engineering (Nuclear Engineering)

Department, The University of Texas at Austin, December 1984.

50. M.G. Krause, " Design and Fabrication of a Texas Assembly for the Evaluation of Heat Transfer in Flow Past Discrete Roughness Elements", Masters Thesis, Hechanical Engineering (Nuclear Engineering) Department, The University of Texas at Austin, December 1984.

51. R.D. Savage, " Error Analysis for a Hydrogen Filled Benjamin Counter", Masters Thesis, Mechanical Engineering Department, The University of Texas at Austin, December 1984.

45

S2. A. Sharif-Homayoun, " Comparison of Parametric Enpirical Bayes with Maximun Likelihood Estimators When Applied to Nuclear Reliability Data -- A Simulation Study", Masters Thesis, Mechanical Engineering Department, The University of Texas at Austin, December 1983 53 R.M. Laucius, " Calculation of the Differential Efficiencies of Organic Scintillators to Neutrons", Masters Thesis, Mechanical Engineering Department, The University of Texas at Austin, May 1983 Reports and Papers

1. D.G. Anderson, "A Technique for Recoil Fission Frag ment Range Measurements", Health Physics,.12:3, 558 (April 1966).

P. P.J. Rodriguez and D.H. Nguyen, " Time Decay Constants in Pulsed Multiplying Media", Trann. Amer. Nucl . Soc. 11:1, 289 (June 1968).

3 P.J. Rodriguez and D.H. Nguyen, "The Maximum Eigen-value in the Pulsed-Neutron Initial-Value Problem", Trans. Amer. Nucl. Soc.

.1.112, 578 (November 1968).

4. P.J. Rodriguez and D.H. Nguyen, " Contribution of the Continuum to the neutron Transient Behavior in a Pulsed Multiplying Cylinder",

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

5. G.D. Bouchey and S.J. Gage, " Neutron Radiography with a Small Suberitical Reactor", Trans. Amer. Nucl. Soc. 12, 462 (1969).

6. G.D. Atkinson, Jr. , W. Coltharp, R. Cramatges, E. Celkers, 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 Technolorv Conference, Dallas, Texas, 1969.

7. V. Chanto, S.J. Gage, and D.F. Barker, " Chlorine and Bromine Concentrations in Some Haliburton-Bancroft Rocks and Minerals by Neutron Activation Analysis", 1969.

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

9. F.A. Rodriguez, S.J. Gage, and K.M. Ralls, " Nondestructive Neutron Activation Analysis for Trace Impurities in Niobium",

presented at the Seventh Symposium on Nondestructive Evaluation of Components and Materials in Aerospace, Weapon Systems, and Nuclear Applications, San Antonio, Texas, 1969

10. S.J. Gage and M. Zuniga, " Uranium Trace Analysis by Pulsed Reactor Irradiation", Radiation and Isotope Technology in Latin American Development, American Nuclear Society Topical Meeting, San Juan, Puerto.Rico, May 1969 46

11. R.H. Richardson, " Migration and Enzyme Polymorphisms in Natural Populations of Drosophila", Jan. J. Gen., 1969.

12. R.H. Richardson, R.J. Wallace, Jr. , S.J. Gage, G.D. Bouchey, and Margaret Denell, " Neutron Activation Techniques for Drosphila in Natural Populations", Studies in Genetics, Marshall R. Wheeler Ed., The University of Texas Press, Austin, Texas, 1969.

13 G.D. Bouchey and S.J. Gage, " Development and Potential Utilization of a Neutron Radiography Facility at The University of Texas Nuclear Reactor Laboratory", presented at the Seventh Symposium on Nondestructive Evaluation of Components and Materials in Aerospace, Weapons Systems and Nuclear Applications, San Antonio, Texas, 1969.

14. G.D. Bouchey and S.J. Gage, " Utilization of The University of Texas TRIGA Reactor for Neutron Activation Analysis Service",

ANS/CNA Transactions 11, 287 (1968).

15. G.D. Bouchey and G. Gjerstad, " Chemical Studies of Aloe Vera Juice -- II. Inorganic Ingredients", Quarterly Journal of crude Drue Research, Sil, (1969).

16. S.J. Gage, R.H. Richardson, and G.D. Bouchey, " Neutron Activation Techniques for Labeling of Insects with Stable Elements", Trans.

Amer. Nucl. Soc., 12, 495 (1969).

17. G.D. Souchey, B.V. Koen, and C.S. Beightler, "The Optimal Allocation of Energy in Industrial and Agro-Industrial Complexes Using Dynamic Programming", Nucl. Sci. and Enre., 31, 70 (1970).

18. G.F. Malan and B.V. Koen, "A Nonlinear Programming Approach to Optimal Control of Nuclear Reactors", Trans. Amer. !!uel . Soc. ,

(1970).

19. Id.G. Stevenson and S.J. Gage, " Application of a Coupled Fission

!! ode Approach to Modular Reactor Kinetics", Journal of Nucl.

E ne rr_v , 21, 1 (1970).

20. G.D. Bouchey and S.J. Gage, " Neutron Radiography at The University of Texas Nuclear Reactor Laboratory", Isotooes and EM Dtion Technolocv, 1, 294 (1970).

21. G.D. Bouchey and S.J. Gage, " Detection and Location of Leaking TRIGA Reactor Fuel Elements", GA Publication T-117, Papers and Abstracts, TRIGA Reactors Cwners' Seminar, Denver, Colorado, February 1970.

22. G.D. Bouchey and S.J. Gage, " Neutron Radiography with a Small Subcritical Assembly", International Journal of Nondestructive Testinc, 1970.

47

i 23 G.D. Atkinson, Jr., J.B. Whitworth, and S.J. Gage, "NAACOL -- A Spectrum Analysis Routine for the Small Laboratory", presented at the 21st Mid-Acerica Symposium on Spectroscopy, Chicago, Illinois, 1970.

24 S.J. Gage, G.D. Atkinson, Jr. , J.B. Whitworth, and A.H. l Fradzynski, " Computer-Aided Multielement Gamma Ray Analysis with l a Compton Suppressed Ge(Li) Radiation Source", presented at the Ninth National Society of Applied Spectroscopy, New Orleans, Louisiana, October 1970.

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

322., 3312, 755 (1970).

26. S.J. Gage and D.G. Jopling, The Nuoler Concent: Potential for the SIMB Recion, Southern Interstate Nuclear Board, 250 pp., March 22, 1971.

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

Sci. and Enar., (1971).

28. G.D. Bouchey, B.V. Koen, and C.S. Beightler, " Optimization of Material Safeguards Sampling System", Trans. Amer. Nucl. Soc.,

Uinter Meeting, 1971.

29. A.H. Pradzynski and S.J. Gage, " Nondestructive Identification of Material by Nondispersive X-Ray Fluorescence Spectrosocpy Using Si(Li) Detectors and Radio-isotopic Sources", Proc. Pichth Symoosium on Nondestructive Evaluation in Aeroscace. Weacons Systamn. nnd Nuclear Aeolications, San Antonio, Texas, 1971.

30. G.D. Atkinson, Jr. and S.J. Gage, " Uranium Assay by Delayed Gacma Ray Analysis Following Cf-252 Neutron Interrogation", frQ2m Twelfth Annual Meetina institute of Nuclear Materials Manacement, Palm Springs, Florida, July 1971.

31. S.J. Gage, E. Linn Draper, Jr., G.D. Bouchey, and R.R. Day,

" Design and Construction of a Versatile Cf-252 Source Shield and Experimental Facility", Neutron Sources and Acolications, CONF-710402, 2, Proc. of ANS Topical Meeting, Augusta, Georgia, April 1971.

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

33 J.B. Whitworth, G.D. Atkinson, and S.J. Gage, "+_me 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.

48

34. G.D. Bouchey, E. Linn Draper,.?c. B.V. Koen, and C.S. Beightler, "Hultiple Foil Activation Spectrum Determination Using a Numerical Direct Search Technique", Trans. Amcr. Nucl. Soc.,

.14:2, 667 (October 1971).

35. G.D. Bouchey, B.V. Koen, and C.S. Beightler, "The Optimization of Nuclear Systems by Geometric Programming, Nucl. Sci. and Enrr.,

31, 267 (1971).

36. G.D. Bouchey, B.V. Koen, and C.S. Beightler, " Optimization of Nuclear Materials Safeguards Sampling by Dynamic Programming",

Nuclear Technolorv, J2, 18 (1971).

37. S.J. Gage, G.D. Atkinson, Jr. , and G.D. Bouchey, " Cyclic Neutron Activation Analysis with a Cf-252 Neutron Source", Trans. Amer.

Nucl. Soc., (October 1971).

38. E. Linn Draper, Jr., " Integral Reaction Rate Determination Part I: Tailcred Reactor Spectrum Preparation and Measurement", Nucl.

Sci. and Ence., lui, 22 (1971).

39. E. Linn Draper, Jr., " Integral Reaction Rate Determination Part II: Fission Rate Measurements", Nucl. Sci. and Ener., 34, 31 (1971).

40. G.D. Bouchey and S.J. Gage, " Detection and Location of Leaking TRIGA Reactor Fuel Elements", Nuclear Technolony, JD, 211 (1971).

41. G.D. Bouchey and S.J. Gate, " Neutron Radiography with a Small Suboritical 9eactor", Int. J. of Nondestructive Testina, 2, 335 (1971).

42. G.D. Bouchey and S.J. Gage, "The Economics of Suberitical Radiography", Trans. Amer. Nucl. Soc., ja, 123 (1971).

43 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 Aoolications, CONF 210402, 3. Proc. ANS Toolc Meetine, Augusta, Georgia, April 1971.

44. G.D. Atkinson, Jr., J.B. Whitworth, and S.J. Gage,

" Computer-Assisted Analysis of Gamma-Ray Spectra", comouter l Physics communications, 2, 40 (1971).

45. S.J. Gage, E. Linn Draper, Jr., and G.D. Bouchey, "Recent l

Developmer.ts in Radioisotopic Source Neutron Radiography", Proc.

! Eichth Symoosium on Nondestructive Evaluation in AerosDace.

k'encon Systems, and Nuclear Acclications, San Antonio, Texas, 1971.

46. E. Linn Draper, Jr., Mary Elizabeth Foster, and G.D. Bouchey, i

"X-Ray Fluorescence Analysis and Neutron Activation Analysis in l

49

I an Analytical Chemistry Laboratory", presented at the Combined Meeting of the Texas Association for Radiation Research and South Central Photobiology Group, Houston, Texas, November 1971.

47. E. Linn Draper, Jr. and G.D. Eouchey, " Utilization of a Portable Californium-252 Source for Neutron Activation Analysis and Neutron Radiography", presented at the Combined Meeting of the Texas Association for Radiation Research and South Central Photobiology Group, Houston, Texas, November 1971.

h8. E. Linn Draper, Jr. and J.J. Chromik, " Production and Measurement of a Reference Spectrum in a Versatile Experimental Facility",

Trans. Amer. Nucl. Soc., J5:1, 157 (1972).

49. E. Linn Draper, Jr. and Andrzej J. Pradzynski, " Identification of Alloys by Energy Dispersive X-Ray Spectroscopy", presented at the Ninth Symposium on Hondestructive Evaluation, 1972.

50. G.D. Atkinson, Jr., E. Linn Draper, Jr., and G.D. Bouchey, "Suberitical TRIGA Reactivity Measurements Using the Source Jerk Technique", presented at the TRIGA Owners' Conference II, College Station, Texas, 1972.

51. G.D. Atkinson, Jr. and E. Linn Draper, Jr., " Transient Rod Failure in a Pulsing TRIGA Mark I Reactor", presented at the TRIGA Owners' Conference II, College Station, Texas, 1972.

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

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

Gage, " Radioisotopic Source Amplification Using a Heterogeneous Suberitical Assembly", Proc. 18th Annual Meetine of the American Nuclear Society, Las Vegas, Nevada (1972).

54. E. Linn Draper, Jr. and G.D. Atkinson, Jr., " Transient Rod Failure in a Pulsing TRIGA Mark I Reactor", published in Proc. of 2nd TRIGA Owners' Conference, February 1972.

l

55. E. Linn Draper, Jr., John W. Davidson, S.J. Gage, and G.D.

Bouchey, "A System for Reduction of 41A Release from a Research Reactor Facility", Trans. Amer. Nucl. Soc., 1511, 4 (1972).

56. E. Linn Draper, Jr., et al, " Standard for the Development of Technical Specifications for Research Reactors", Trann. Amer.

l Nucl. Soc., (1972).

l 57 E. Linn Draper, Jr., G.D. Atkinson, Jr., and B.B. Tomlin, "A Radiography and Capture Gamma Ray Facility for Californium-252",

Proc. of the American Nuclear Society "Anolications of Californium-262" National Tooical Meeting, September 1972.

50 L

f 58.- 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 Tonical Meetina, September 1972.

59. E. Linn Draper, Jr. and S. J. Gage, "The FusionFission Breeder:

Its Potential in a Fuel Starved Thermal Reacter Economy",

presented at the 93rd Annual !!eeting of ASME, New York,1972.

60. E. Linn Draper, Jr., " Technological Innovation and Assessment: A Novel Course for Nuclear Engineering", presented at the Winter Iteeting of the American Nuclear Society, November 1972.

61. D.T. Hall, E. Linn Draper, Jr., and P.S. Schmidt, " Management of the Transition to Nuclear Power Generation", Technical Report ESL-3, Energy Systems Laboratories, College of Engineering, The University of Texas at Austin, December 1972.

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

63 P.S. Schmidt and G.P. D' Arch, " Entry Region Effects on Flow and Pressure Drop of Lithium in Fusion Re- actor Blankets", Proc. of the Texas Symoosium of Technolorv of Controlled Thermonulear Fusion Evneriments and Fnaineerine Annects of Funion Reactors, Austin, Texas, November 1972.

64. E. Linn Draper, Jr. and Charles Brauer, " Lithium-Lead Collimater Fabrication for Radioisotopic Source Neutron Radiography", Trans.

Amer. Nucl. Soc., 1511, 142 (1972).

65. 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 Fusion Experiments and the Engineering Aspects of Fusion Reactors, November 1972.

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

67 E. Linn Draper, Jr., " Fusion Reactor Engineering in the Nuclear Engineering Curriculum at The University of Texas at Austin",

Trans. Amer. Nucl. Soc., (1972).

68. E. Linn Draper, Jr. and S.J. Gage, "The Fusion Fission Breeder:

Its Potential in a Fuel Starved Thermal Reactor Economy",

presented at the Texas Symposium on the Technology of Controlled Thermonuclear Fusion Experiments and the Engineering Aspects of Fusion Reactors, November 1972.

51 I i

69. James B. Freim and E. Linn Draper, Jr., " Experimental Determination of the Fusion Spectrum in Graphite", Trans. Amer.

Nucl. Soc., (1972).

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

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

72. T.L. Bauer and G.D. Atkinson, Jr., " Discrimination Between 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.

73 E. Linn Draper, Jr., Editor, Proc. of Teras Symnosium on the Technolocv of Controlled Thermo- nuclear Fusion Eroeriments and the Eneineerine Asnects of Fusion Reactors, published by USAEC.

74. E. Linn Draper, Jr., Editor, Proc. of the Tmolications of Nucleer Power in Teras, published by the Texas Atomic Energy Research Foundation.

75 E. Linn Draper, Jr., J.R. Deen, and J.J. Chromik, " Measurement of the Integral Fission Cross Section of Th-232 in a Cf-252 Fission Neutron Spectrum", Trans. Amer. Nucl. Soc., (1973).

76. D.C. Anderson and E. Linn Draper, Jr., " Fission Product Mass-Yield Measurements from Intermediate Energy Neutron Fission of Plutonium-239 and Plutonium-241", Trans. Amer. Nucl. Soc.,

(1973).

77 E. Linn Draper, Jr. and James B. Freim, " Experimental Determination of the Fusion Spectrum in Graphite", Trans. Amer.

Nucl. Soc., li, 9 (1973).

78. E. Linn Draper, Jr., " Fusion Reactor Engineering in the Nuclear Engineering Curriculum at The University of Texas at Austin",

Trans. Amer. Nucl. Soc., Ji, 16 (1973).

79. E. Linn Draper, Jr., Theodore A. Parish, and Brian J. McArdle, "A Neutronic-Photonic Comparison of Vanadium and Niobium Containing Fusion Reactor Blankets", Trans. Amer. Nucl. Soc., (November 1973).

80. John H. Vanston, Jr., "Use of Partitive Analytical Forecasting (PAF) Techniques for Fusion Development Analysis", Trans. Amer.

Nucl. Soc., (November 1973).

52

81. Theodore A Parish and E. Linn Draper, Jr., "Neutronic 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

62. C.E. Locke and D.R. Paul, " Graft Copolymer Modification of Polyethylene-Polystyrene Blends. I. Graft Preparation and Characterization", Journal of_ Anolied Polymer Science, II, 2597 (1973).

83 C.E. Locke and D.R. Paul, " Graft Copolymer Modification of Polyethylene-Polystryene Blends. II. Properties of Modified Blends", Journal of Aeolied Polymer Science, J2, 2791 (1973).

64. E. Linn Draper, Jr. , M.J. Voltin, Jr. , J.L. MacDonald, C.T.

Rombough, L.D. Hansborough, S.G. Barbee, and J.H. Vanston, Jr.,

"A University's Involvement in Municipal Decision-Making on Nuclear Power", Trans. Amer. Nucl. Sec., (1973).

85. E. Linn Draper, Jr., J.L. MacDonald, and M.J. Voltin, Jr.,

" Nuclear vs. Coal: An Economic Comparison of Power Plant Economics in Texas", Trans. Amer. Nucl. Soc., (1973).

86. R.E. Henry, " Forensic Applications of Neutron Activation Analysis", presented at the Combined Meeting of the Texas Association for Radiation Research and South Central Photobiology Group, San Marcos, Texas, November 1973 87 G.D. Atkinson, Jr., " Applications of Neutron Activation Analysis to the Life Sciences", presented at the Combined Meeting of the Texas Association for Radiation Research and South Central Photobiology Group, San Marcos, Texas, November 1973

86. E. Linn Draper, Jr. and J.R. Deen, " Measurement of Fission Product Yields from Thorium-232 in Californium-252 Fission Neutron Spectrum", Trans. Amer. Nucl. Soc., ll, 531 (1973).

89. E. Linn Draper, Jr., M. Etzion, S.P. Nichols, and W.G. Davey,

" Neutron Fermi Age in Graphite from Fission and Fusion Sources to Indium Resonance", CONF 740402, USAEC, April 1974.

90. E. Linn Draper, Jr. and T.A. Parish, "Neutronic and Photonic Analyses of Fusion Reactor Blankets Containing Natural Uranium",

CONF-740402, USAEC, April 1974.

91. G.D. Atkinson, Jr. , B.D. Adams, and S.J. Gage, "A Programmable and Automated System for Gamma and X-R&y Analysis", Proc. TFFF 1979 Nuclear Science Symoosium, San Francisco, California, 1973

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

Environmental and Biolgical Applications", presented at the Sixth Annual Meeting of the Texas Association for Radiation Research, San Marcos, Texas, 1973 I

53

k 93  !!. 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).

94. A.H. Pradzynski, " Determination of Selenium in Water on the ppb level" presented at the Texas Association of Radiation Research, Dallas, Texas, November 1974. (

95. J.R. Deen and E. Linn Draper, Jr., " Measurement of the Fission Product Yields and the Energy Integral Fission Cross Section of Thorium-232 in a Californium 252 Fission-Neutron Spectrum",

Nuclear Technology, 25, 416 (1975).

96. E. Linn Draper, Jr., T.A. Parish, and M. Etzion, " Utilization of a Small Accelerator for Fusion Reactor Blanket Design", Proc. of the Third 9mn11 Accelerator Conference, USAEC, CONF-741021, 1974.

97. R.G. Spangler, E. Linn Draper, Jr., and T.A. Parish, "14 MeV Cross Section Measurements of Threshold Reactions for Seven Metals", Trans. Amer. Nucl. Soc., 22, 818 (November 1975).

98. W.R. Smith, Jr. and E. Linn Draper, Jr., " Measured and Calculated Fast Neutron Spectra in a Graphite Medium", Trann. Amer. Nucl.

32n., 22, 800 (November 1975).

99 J.W. Davideon and E. Linn Draper, Jr., " Costs for Partitioning Strategies Involved in High-Level Nuclear Waste Hanagement",

Trans. Amer. Nucl. Soc., 22, 348 (November 1975).

100. M.J. Voltin, Jr. and E. Linn Draper, Jr., " Sensitivity of Total Fuel Cycle Cost to Variations in Enrichment Tails Assay Strategies", Trans. Amer. Nucl. Soc. , 22, 322 (November 1975).

101. T.A. Parish, J.W. Davidson, and E. Linn Draper, Jr.,

" Transmutation of Fission Products in Fusion Reactor Blankets",

Trans. Amer. Nucl . Soc. , 22, (November 1975).

102. T.A. Parish, J.W. Davidson, and E. Linn Draper, Jr., "The Effects of the D-T Fusion Neutron Energy Spectrum on Hi hE Energy Reaction Rates", submitted to the Sixth Symposium on Engineering Problems of Fusion Research, San Diego, California, November 1975.

103 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, 21:5, 277 (1975).

104. B.E. Bulla, E. Linn Draper, Jr., R.E. Henry, M.J. Voltin, Jr., et al, Texas Nuclear Power Policies: A Study of Alternatives. Volume II Methodoloev. The University of Texas at Austin Center for Energy Studies, Policy Alternative Study No. 1 (1975).

, 54

T

-105. A.H. Pradzynski, R.E. Henry, and_J.L.S. Stewart " Determination of Transition Metals by Radioisotope-Excited Energy Dispersive X-Rny Spectrometry", Trans. Amer. Nucl. Soc., 2113, 34-(1975).

a I -

106. A.H. Pradzynski, R.E. Henry, and J.L.S. Stewart, " Hon-destructive Determination of Toxic Elements in Toys", Proc. of 10th Symoosium on Nondestructive Elements, San Antonio, Texas, April 1975.

107. R.E. IIenry,- " Determination of ppb Levels of Selected Elements in

. Natural Water Using Radioisotope-Excited Energy Dispersive X-Ray Fluorescence Analysis", presented at the EiEhth Annual Meeting of the Texas Association for Radiation Research, Austin, Texas, October 1975.

106. T.A. Parish, J.W.-Davidson, and E. Linn Draper, Jr., "The funimization of the Hazard Resulting from Transmutation of Fission Products", Trananntions of the Amanican Nuclear Society,

23, 59 (June 1976).

109 T.A. Parish, " Fusion-Fission Hybrid Studies at The University of Texas", presented at the U.S.-U.S.S.R. Symposium on Fusion-

[

Fission Reactors, Lawrence Livermore Laboratories, July 1976.

110. T.A. Parish, J.W. Davidson, and E. Linn Draper, Jr., "Neutronic Performance of Graphite Fusion Reactor Blankets Containing Sr90 and I129", presented at the Second ANS Topical Meeting on.the Technology of_ Controlled Thermonuclear Fusion, Richland,

Washington, September 1976.

111. T. A. Parish, J.W. Davidson, and J.B. Cornwell, "The Effectiveness of a Sr90 Fusion P.eactor Trancautation Waste Management Program",

Transactions of the American Nuclear Societv, 21,' November 1976.

< 112. A.H. Pradzynski and J.R. Rhodes, " Development of Synthetic '

Standard Samples for Trace Analysis of Air Particulates". ASTM Special Technical Publication, SSA, 320 (1976).

4 113 A.H. Pradznyski, R.E. Henry, and J.S._ Stewart, " Determination of ppb Concentrations of Transition Metals by Radioisotope-Excited Energy-Dispersive X-Ray Spectrometry, Journal of Radiannnivtical Chemistry, 32, 219 (1976).

l i 114. A.H.~Pradzynski, R.E. Henry, and E.L. Draper, Jr., " Determination of ppb Concentrations of Uranium, Thorium and Holybdenum in Water using APDC Preconcentration and Radioisotope Excited X-Ray Emission Spectrometry", Proceedinam of RRDA Svmnosium on Y- and Carma-Rav Sources and Aeolications, Ann Arbor, Michigan, !!ay 1976.

115. A.ll. Pradzynski, R.E. Henry, and E.L. Draper, Jr., " Determination of Trace Elements of Hydrogeochemical Prospecting by APDC-Coprecipitation and X-Ray Spectrometry", Invited Paper at The International Conference on World Nuclear Energy a Status Report. Transactions of Aner. Nuclear Society, 23, 119 (1976).

55

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

117. C.W. Savery and R.R. Gay, "Effect of Entrained Droplet Phase Upon Predicted Compartmental Pressures in Nuclear Containments",

Two-Phase Flow and Heat Transfer Symposium-Workshop, Miami Deach, Florida, 1976.

118. Rodney R. Gay, " Reactor Hydrodynamics During the Reflood Phase of Loss-of-Coolant Accident", Nuclear Technolorv, 3612, 229 (December 1977).

119 D.E. Klein, S.R. Bull, and J.B. Miles, " Flow Visualization Around GCFR Fuel Rod Roughness Elements", Trans. Amer. Nucl . Soc. , 23, (June 1978).

120. D.E. Klein, S.R. Bull, and J.B. Miles, " Pressure Drop for GCFR Fuel Rod Roughness Elements", Trann. Amer. Nucl. Soc., 3D, (November 1978).

121. E.!!.B. Sorensen, R.E. Henry, and R. Ramirez-Mitchell, " Time Dependent Localization of Arsenic in Subcellular Hepatocyte Fractions", J. of Patholorv and Toxicolorv, 211, 1161 (1979).

122. E.!!.B. Sorensen, R.E. Henry, and R. Ramirez-Mitchell, " Arsenic Accumulation, Tissue Distribution, Cytotoxity in Teleosts Following Indirect Aqueous Exposure", Bulletin of Environmental Contamination and Toxicolocv, 21, 162 (1979).

123 J.W. Davidson and T. A. Parish, " Fission Product Toxicity Reduction via Transmutation Using D-T Fusion Neutrons", presented at the Eighth Symposium on Engineering Problems of Fusion Research, San Francisco, California, November 1979 124. J.W. Davidson and T.A. Parish, "An Evaluation of the Requirements and Performance of a Transmutation Waste Management System, Trans. Amer. Nucl. Soc., 33, (November 1979).

125. S.A. Hodge, J.P. Sanders, and D.E. Klein, " Determination of Friction Factors and Heat Transfer Coefficients for Flow Past Artificially Roughened Surfaces", Oak Ridge National Laboratory Report, ORNL-5599, November 1979 126. D.E. Klein, " Nuclear Problems and Prospects", National Energy Policy Issues, Council on Energy Resources, The University of Texas at Austin, May 1979 t 127. D.E. Klein,11.11. Woodson, and J.W. Davidson, " Commercial Nuclear Power Generation", Council on Energy Resources, The University of Texas at Austin, June 1979.

l 56 l

128. E.M.B. Sorensen, R.R. !Etchell, A. Pradzynski, T. Bauer, and L.

Graham, "!!orphocetric Analyses of Arsenic-Induced Histopathological Changes in Parenchymal Hepatocytes", Tennessee Academy of Science Annual Meeting, Nashville, TN, November 16-17, 1979 129 A.H. Pradzynski, " Determination of V and Ba in Marine Sediments and Biota", Internal Report, Nuclear Engineering Teaching Laboratory, Mechanical Engineering (Nuclear Engineering)

Department, The University of Texas at Austin, 1979.

130. H.E. Hertel, B.W. Wehring, and J.J. Dorning, " Integral Test of ENDF/D-IV High-Energy Neutron Cross Section Data for Tungsten",

Trans. Amer. Nucl. Soc., 32, 632 (1979).

131. R.H. Johnson, K.R. Koch, D.W. Wehring, and N.E. Hertel, "TDL Measurements in an Iron Sphere Containing a DT Source", Trans.

Amer. Nucl. Soc., 32, 632 (1979).

132. B.W. Wehring, J.J. Dorning, N.E. Hertel, D.T. Ingersoll, and R.H.

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

133 N.E. Hertel, R.H. Johnson, J.J. Dorning, and B.W. Wehring, "Mearsurements and Analyses of Neutron Transport Through Iron",

Proc. Conf. Nuclear Cross Sections and Technolorv, Knoxville, TN, October 22-26, 1979, NBS Special Publication #594, pp. 568-571.

134. N.E. Hcetel and B.W. Wehring, " Absolute Monitoring of DD and DT Neutron Fluences Using the AssociatedParticle Technique", Engl.

Instr. fieth., J22, 501 (1980).

135. S. A. Hodge, J.P. Sanders, and D.E. Klein, " Slope and Intercept of the Dimensionless Velocity Profiles for Artificially Roughened Surfaces", Int. J. Heat Mass Transfer, 23, 135 (February 1980).

136. N.E. Hertel, J.B. Smathers, and R.G. Graves, " Gamma-Ray Spectra Measured in a Tissue-Equivalent Medium Irradiated with Neutron Radiotherapy Sources", Trans. Amer. Nucl. Soc., 35, 457 (1980).

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

138. D.E. Klein, S.R. Bull, and J.D. Miles, " Pressure Drop Measurements and Flow Visualization Surrounding Roughness Elements", Journal of Enerry, 313, 112 (1900).

139 D.E. Klein, "ANS Student Involvement in Public Information - The University of Texas at Austin", Invited Paper, Trans. Amer. Nucl.

Sng., 31 (1980).

57

9 140. 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", AS!!E 80-HT-38, April 1980.

141. J.E. Hamann, D.E. Klein, R.B. Pope,.and H.R. Yoshimura,

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

142. M. A. Ross and D.E. Klein, " Synthetic Fuel Production Utilizing Texas Lignite and a VHTR for Process Heat", Trans. Amer. Nucl.

Sag., 35, (1980).

143 J.H. Davidson and D.E. Klein (co-editors), Proc. of the International Conference on Nuclear Waste Transmutation, The University of Texas at Austin Press, March 1981.

144. M.A. Ross and D.E. Klein, " Synthetic Fuel Production Using Texas Lignite and a VHTR for Process Heat", Nuclear Technoinav, 5613, (March 1982).

, 145. T.L. Sanders and D.E. Klein, "A tiodified Numerical Scheme for GCFR Flow Transient Analysis", Trann. Amer. Nucl. Soc., 3o, (November 1981).

146.  !!. A. Ross and D.E. Klein, " Synthetic Fuel Production Using Texas Lignite and a Very High Temperature Gas Cooled Reactor for Process Heat and Electrical Pcwer Generation", The University of Texas at Austin Center for Energy Studies Research Report, J3, May 1981.

147 ti.M. Razzaque, J.R. Howell, and D.E. Klein, " Finite Element

. Solution of Heat Transfer for Gas Flow Through a Tube", IAA Journal 2ful, July 1982.

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

149 J. Andersen and D.E. Klein, et al., " Peer Review of the Preliminary Design and Program Interfaces for the Iransgranic Uaste fagkage Iransporter (TRUPACT)", Sandia Report, SA!!D 81-2405, June 1982.

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

, 58 i

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

L 152. T.L. Sanders and D.E. Klein, " Comparison Analysis of Severe Flow Blockages for Computational Efficiency Using COBRA", Proc. from Cas-Cooled Reactors Today Conference, British Nuclear Energy Society, London, England, September 1982.

153 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 Meeting, Phoenix, Arizona, November 1982.

154. J.B. Smathers, N.E. Hertel, and R.G. Graves, "In Phantom Photon Spectra Measurements for High-Energy Neutron Therapy Sources",

Proc. frem the Fourth Svmoosium on Neutron DosimetrvrBeam Dosimetry, Neuherberg/ Munich, Germany, June 1981.

155. N.E. Hertel, B.W. Wehring, and J.J. Dorning, " Measurements and Analyses of High-Energy Neutron Transport Throuch Tungsten",

accepted for publication (subject to revision) in Nucl. Sol. and Engn. , November 1981.

156. Y. Kunimoto, J.W. Davidson, and N.E. Hertel, "A Core Inventory Model for Fuel Trajectory Analysis in Fusion-Fission Symbiotic Systems", Trans. Amer. Nucl. Soc., 31, 1978 (June 1982).

157. N.E. Hertel and W.E. Murphie, "The Use of Neutron and Gamma-Ray NE-213 Spectral Measurements and Calculations to obtain Dosimetric Information for DT Neutrons", Medical Physics, 10:66, (1983).

158. R. Laucius, J.W. Davidson, and N.E. Hertel, " Calculation of the Differential Efficiencies of Organic Scintillators to Neutrons Above 10 11eV", Trans. Amer. Nucl. Soc., 33, 625 (November 1982).

159. J.W. Davidson and N.E. Hertel, "Bonner Ball Detection Responses for Neutrons from Thermal Energies to 17 3 MeV", Health Physics Society Annual Meeting, Baltimore, Maryland, 1983 160. N.E. Hertel, J.W. Davidson, and R.M. Laucius, "NE-213 Response Matrix for Neutron Spectrometry Up to 50 MeV", Health Physics Society Annual Meeting, Baltimore, Maryland, 1983 161. N.E. Hertel, J.W. Davidson, and R.M. Laucius, "An NE-213 Response Matrix to 50 MeV", Trans. Amer. Nucl. Soc., 15, 607 (1983).

59 t

162. J.W. Davidson and N.E. Hertel, "An Equal Probability Neutron Detection System Using Bonner Spheres", Trans. Amer. Nucl. Soc.,

A5, 609 (1983).

163 U.M. Razzaque, J.R. Howell, and D.E. Klein, " Coupled Radiative and Conductive Heat Transfer in a Two Dimensional Rectangular Enclosure with Gray Participatir.g Media Using Finite Elements",

ASME/JSME Thermal Engineering Joint Conference, ASPE-H-35, Honolulu, Hawaii, March 1983 164. S. Yang, J.R. Howell, and D.E. Klein, " Radiative Heat Transfer Through a Randomly Packed Ded of Spheres by the Monte Carlo Method", Journal of Heat Transfer, 105:2, 325 (May 1983).

165. M.M. Razzaque, J.R. Howell, and D.E. Klein, " Finite Element Solution of Radiative Heat Transfer in a Two Dimensional Rectangular Enclosure with Gray Participating Media", (accepted by the Journal of Heat Transfer).

166. M.M. Razzaque, J.R. Howell, and D.E. Klein, " Coupled Radiative and Conductive Heat Transfer in a Two Dimensional Rectangular Enclosure with Cray Participating Media Using Finite Elements",

Journal of Heat Transfer, lad, 613 (1984).

167 E.M.B. Sorensen, C.W. Harlan, M.D., T.L. Bauer, and A.

Pradzynski, " Hepatocyte Changes Following Selenium Accumulation in a Freshwater Teleost", The Amer. Journal of Forensic Medicine and Patholorv, 313, 8 (1982).

166. E.M.B. Sorensen and T.L. Bauer, "A Correlation Petween Selenium Accumulation in Sunfish and Changes in Condition Factor and Organ Weight", Evironmental Pollution Series A. DIA3, 357 (1984).

169. E.M.B. Serensen, 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).

170. E.M.B. Sorensen and T.L. Bauer, " Selenium Induced Hematological Dyscrasia in Teleosts", Archives Environ. Contam. and Toxicolorv, 12, 135 (1983).

171. E.M.B. Sorensen, P.M. Cumbie, 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.

and Toxicolory, 13, 153 (1984).

172. E.M.B. Sorensen, R.R. Mitchell, 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 Patholocv. Toxicoloev and Oncoloev).

60

173 N.E. Hertel and J.W. Davidson, "The Effect of Cadmiun Covers on Bonner Sphere Responses", to appear in the Proc. of the Personnel Radiation tosimetry Symoosium, Knoxville, Tennessee, October 1984.

174. N.E. Hertel and J.W. Davidson, "The Response of Donner Spheres j from Thermal Energies to 17 3 MeV", (accepted for publication Nuclear Instruments and Methods, (February 1985).

175. A. Patterson-Hine, J.W. Davidson, and D.E. Klein,

" Characterization of Product Buildup in Continuously Processed Holten Salt Fusion Breeder Blankets", Trans. Amer. Nucl. Soc.,

35, (1983).

176. A. Patterson-Hine, J.W. Davidson, and D.E. Klein, " Contributions to the Thermal Power of Continuously Processed TMHR Molten Salt Blankets", 10th Symposium on Fusion Engineering, Philadelphia, Pennsylvanie, December 5-9, 1983 177 G.P. Polansky, J.P. Lamb, and D.E. Klein, "A Finite Element Analysis of Incompressible Laminar and Turbulent Flow with Heat Transfer", presented to the 5th International Symposium on Finite Elements and Flow. Problems, The University of Texas at Austin, Austin, Texas, January 23-26, 1984.

178. M. Ally, D.E. Klein, and T.L. Bauer, "Preconcentration Methods cf 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.

179. D.E. Klein and W.H. Miller, " Student ANS Branch Involvement in Public Information", Invited Paper, Trans. Amer. Nucl. Soc., June 1984.

180. F.Y. Iskander, D.E. Klein, and T.L. Bauer, " Toxic and Cther Elements in American Cigarette Tobacco Compared with International Brands", 17th Annual Meeting of Texas Association for Radiation Research, Denton, Texas, November 1984.

181. F.Y. Iskander and R.H. Filby, " Formation of Anatase from Ti(IV)-pre-asphaltene Complexes under Coal Liquefaction Conditions", Engl. 63, 280 (1984).

182. F.Y. Iskander and R.H. Filby, "Speciation of Titanium in Solvent Refined Coal Using SESC-INAA", Proc. of American Nuclear Society Meetinc, Fifth International Conference, Mayaguez, Puerto Rico, April 2-6, 1984.

183 T.L. Sanders, D.E. Klein, and M.E. Crawford, "A Liquid Metal Facility for the Analysis of Phenomena Related to the Magnetohydrodynamics of Fusion Related Systems", Sixth Topical Meeting on the Technology of Fusion Energy, San Francisco, California, March 1985.

61 L

i ,.

4 184. T.L. Sanders, D.E. Klein and M.E. Crawford, "A Liquid Metal Facility for the Analysis of MHD Effects in Fusion-Helated Systems", Fusion Technolorv, 311, (1985).

185. A. Patterson-Hine, J.W. Davidson, D.E. Klein, and J.D. Lee,

" Characterization of the Effe, cts of Continuous Salt Processing on the Perforcance of Molten Salt Fusion Breeder Blankets", accepted I

to J. of Fusion Enerav.

186. F.Y. Iskander, " Neutron Activation Analysis of an Egyptian Cigarette and its Ash", J. Radicanal. Nucl. Chem., IS, 511 (1985).

187 F.Y. Iskander, " Egyptian and Foreign Cigarettes. 1. Determination of Trace Elements in Cigarette (Filter Before and After Smoking",

J. Radionnal. Nucl. Chem., 31,j191 (1985).

188. F.Y.Iskander,"CigaretteAshbsaPossibleSourceof Environmental Contamination", Environ. Pollut. (Series B), 11, (1986).

189. F.Y. Iskander, " Egyptian and Foreign Cigarettes. 2. Determination of Trace Elements in Tobacco, Ash, and Wrapping Paper", J.

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

190. F.Y. Iskander, T.L. Bauer, and D.E. Klein, " Determination of 28 Elements in American Cigarette Tobacco by Neutron Activation Analysis", Analyst, jll, 107)(1986).

191. F.Y. Iskander, D.E. Klein and T.L. Bauer, " Determination of Trace Inpurities in Aspirin Tablets by Neutron Activation Analysis", J.

Radioanal. Nucl. Chem., 31, 353 (1986).

192. H.M. liorad. F.Y. Iskander, L.W. Rooney, and C.F. Earp, "Physico-chemical Properties of Alkali-cooked Corn Using Traditional and Presoaking Procedures", Cereal Chem., f3(3)

(1986) 255.

193 F.Y. Iskander and M.M. Morad, " Neutron Activation Analysis of Texas Hard Red Winter Wheat and its Hilling Fractions", American Association of Cereal Chemistry, 70th Meeting, Orlando, Florida, paper 151, 1985 194. F.Y. Iskander, " Neutron Activation Analysis for Assessing the Concentration of Trace Elements in Laboratory Detergents", iLu Anol. Radiat. Isotones,_It (5) (1986) 435.

195. F.Y. Iskander, T.L. Bauer, and D.E. Klein, "Some Considerations of Elements Content of Cigarette Wrapping Paper", TAPPI, fra (5)

(1986) 134.

62

m i

196. F.Y. Iskander, !!.M. Morad, D2E. Klein, and T.L. Bauer, " Protein, In-Vitro Protein Digestibility and Minerals Content of Hard and Soft' Red Wheat Varieties", submitted to Cereal Chem.

197 F.Y. Iskander, (1986). Determination of lipid unsaturation by neutron activation analysis. Submitted to J. Radicanni Muel.

Chem.

198. F.Y. Iskander and M.M. Mored, " Minerals and Protein Contents in Texas Hard Ecd Winter Wheat and Ito Milling Fractions", Ennd Science, 51 (1986) 1522.

199. F.Y. Iskander, D.E. Klein, T.L. Bauer, and M.!!. Morad, " Protein and Nutritional Elements Content in Texas k' heat", 18th Annual i lleeting of Texas Association for Radiation Research, San Antor.io, Texas, November 1985.

200. F.Y. Iskander and M.M. Morad, "Multielement Determination in Wheat and Bran", Radiaochem. Radionnal. Letters, 125 (3) (1986) 151.

201. 0.I. Asubiojo, J.A. Adepetu, and F.Y. Iskander, " Determination of-the Chemical Composition of Nigerian Harmattan Dust by Instrumental Neutron Activation Analysis", The 7th International Conference, !!odern Trends in Activation Analysis, Copenhagan, Denmark, 1986. Q

+

t 202. F.Y. Iskander, (1987). Maturation stage and mineral content in scybeans. J. Food Chem. (in press).

203 (T.R. Ajayi, F.Y. Iskander, 0.I. Asubiojo, D.E. Klein, Geochemistry of upper cretaceous classic sediments of Ifon area, S. U. Higeria. Submitted to Gtochemica Cosmochimica Acta.

204. K.R. Davis, F.Y. Iskander, H. Ashour, H.F. Hassan, Aluminum content in Egyptian breads. Submitted to Egrgp1 Chem.

205 F.Y. Iskander, H.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.

206. F.Y. Iskander (1986). Use of NAA to determine nutritive elements

~

in immature and mature soybeans. Trans. Am. Nucl. Soc., 53: 170 207 F.Y. Iskander (1987). Determination of lipid unsaturation by neutron activation analysis. Submitted to J. Radiennal Nucl.

Chem.  %

208. J.A. Adeptu, O.I. Asubiojo, F.Y. Iskander, and T.L. Bauer,

. Elemental cocposition of Nigerian harmattan dust for ecological edndtoring using instrumental neutron activation analysis.

Submitted to J. Radionnal. Nucl. Chem.

t I

i j 63

209 R.D. Manteufel:. D.E. Klein, and H.R. Yoshimura, " Benchmarking cf Q/TRAN Thermal Analysis Computer Code", accepted by PATRAN, 198'.

210. 'd.D. Manteufel, D.E. Klein, and H.R. Yoshimura, " Comparison Study of PATRAN and 0/TRAN for Thermal Analysis of Shipping Containers", accepted by PATRAN USER'S Conference.

211. G.P. Polansky, J.P. Lamb and D.E. Klein, " Finite Element Simulation of Recirculating Flows with Heat Transfer",

Comennication in Aeolied Nummerical Methods, Vol 3, No. 1 P.

17-22, Jan-Feb, 1987 64

gs% #

COLLEGE OF ENGINEERING ca . W -THE UNIVERSITY OF TEXAS AT AUSTIN

%(# &' *l.

\., ~).:!

%mgy _s/ DepartmentofMechanicalEngineering NaclearEngineeringProgram Austin, Texas 78712-()12)471-5136 March 27, 1987 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 1986 Annual Report. These are being submitted according to 10CFR Section 50.59.

Sincerely,

[~ b#

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

-cc: Dr. Dale Klein L

y J