ML20115C598

Forwards Annual Rept for CY84

ML20115C598
Person / Time
Site:	05000192
Issue date:	03/29/1985
From:	Bauer T, Klein D TEXAS, UNIV. OF, AUSTIN, TX
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
NUDOCS 8504180474
Download: ML20115C598 (1)

Text

h'*f I

G THE UNIVERSITY OF TEX AS COLLEGE OF ENGINEERING AUSTIN, TEXA$ 78712 73@20WE  %

- Department of AlechanicalEngineering

. Nudear Engineering Program y3

. 312--4 71-5136 March 29, 1985

__ h Region IV USNRC Office of Inspection & Enforcement 611 Ryan Plaza Drive Suite 1000 Arlington, Texas 76012

Dear Sir:

Enclosed is a copy of the annual report for the calendar year

-1984'. Twelve (12)~ copies of the report have been sent to the Director of Inspection and Enforcement,-Washington, D.C.

Please contact me if you have any specific questions or comments.

Sincerely yours, N

T.L. Bauer Reactor Supervisor SOP #3664 Dale Klein, Director Nuclear Engineering Teaching Laboratory TLB:DK:bb Enclosure h

koj4180474850329: t h I R ADOCK 05000192 } l 1 )(,\ PDR .

Q

1 l  ;

h

>j .%

f4 -,. ,"

~

n

)-' ' -

r .

l l

1 1

l. , -

t NUCLEAR REACTOR l LABORATORY

! TECHNICAL REPORT  ;

THE UNIVERSITY OF TEXAS COLLEGE OF ENGINEERING DEPARTMENT OF MECHANICAL ENGINEERING F

_ , t . e~ r_ ! n

-w-,%.,,,-_-

$. ; e ) y ;: i n_

. _ , v. -

J - s

\ :; - 7.?

J! ,

d?

f '<

w r -

p i

.4V r ..

A i

x.

-i 1-.

- v.

~

1. + .%

)

m

'1984 ANNUAL REPORT'

.of-The University of Texas at Austin

. :4 Nuclear Engineering Teaching' Laboratary .-

3.<-._

u. i f

~

r ei January 1,- 1984 - December 31,: 1984

~

.1, _

'D.'E. Klein, Director T. L. Bauer, Supervisor

. Taylor Hall 104

' - c

'512/471-5136

- - January 1985 s 4

. 9 m 4

pg .

Qp idy? '

4-

. O R'ig:.:)' n. '

g]r3; *

-n L.ji TABLE'0F CONTENTS L+p: ,-

PjygtL

' List:of Figures _.. . .-. . . . . . .. .. . . . .... . . 11-

[ListofTables . .. ... . .:. . . ... . . . . . . . .. . . .-111-

1. Introduction'. ...................... . . . .

1 II. - ' Laboratory - Administration. . . . . . . - . . . .- . . . . . . . . . . -5

-A..' Organization B. Personnel C. Standing Committees .

f, _ _D. -Report to the College of Engineering

. III.' l Laboratory Development . . . . . . . . . . . . . . . . . .

10

. JA. Organizationf B. Nuclear Engineering Teaching Laboratory.

C. Neutron Activation Analysis Facilities -

D. Nuclear Radiation Laboratory IV. Facility Operations Summary. . . . . . . . . .. . ... . . 13 A. : Operating Experience

' B. . Reactor Shutdowns

. 'C. : Utilization D.. Maintenance E .- Facility Changes F.- Radiation Exposures G. Area Radiation Surveys

. ' H. -Radioactive Effluents V.. Laboratory Inspections.

'- .. . . . .. . . . . . . . . . . ' . 29 A. NRC Inupection February 27,1984 B. . TDH Inspection September 17-18, 1984

VI. Public Service Activities . . . . . . . . . . . '. .. . . . 30 A. - Summer High School Science Teacher Symposium B. Lectures and Presentations C. Reactor Facility Tours 31

'VII. Research Ascivities . ... .. . . . . . .. . . .. . . . .

VIII. Publicatior 4 from the Nuclear Engineering Teaching . abo rat o ry . . ' . . . . . . . . . . . . . . . . . . 44 e.

D W

+

b 9

List of Figures Firure No. Zggg 1 Floor Plan of Nuclear Reactor' Laboratory' , 3 _

2 Floor Plan of the Nuclear Engineering Teaching Laboratory. 4

.. 3 Organization chart of the Nuclear Engineering Teaching Laboratory 6 4 . Comparison Burnup vs Year 17 5 -Comparison of Number of Samples Irradiated vs Year 18 6 Taylor Hall Environmental Survey Locations 25 t ..

1 f

e 11

c"-

4 f

. List of Tables

- Table No. h

1. Facility Personnel 7

2. Standing Committees 8

3. Courses Utilizing NETL

' Facilities 11

, ~

4. Reactor Scrams 14

,- 5. Comparison of-Yearly-Inadvertent Scrams 14

6. NETL Performance Data 1984 15

7. Comparison of. Previous

-Utilization Data 16 8.- Summary of Radiation Exposure 20

9. Radiation. Exposure Analysis 21 10.

Laboratory Radiation Levels 22

11. Laboratory Contamination Levels 23

12. Environmental Surveys 24

13. Monthly Summary of Gaseous Waste Discharges 27

14. Annual Summary of Solid Waste Disposal 28

15. ~ Research Funding 32 iii e

m -

r.f y

..4- .

I.- INTRODUCTION

.This report'has been_ prepared by the staff of'the

_ Nuclear Engineering Teaching Laboratory (NETL),lThe-Uni-versity of' Texas at Austin, to satisfy the. reporting re-

quirements 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, 1984 -to December 31, 1984.

~.

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 Jmodes.. The reactor'laboratoryfand adjacent laboratory areas are shown in-Figures 1 and 2. Other equipment maintained by the NETL program includes two Cockcroft-Walton 14 MeV neutron generators, a Lockheed Aerojet suberitical assembly, and a 925. curie Co-60 irradiator.

Isotopic neutron sources available include three californium-252 sources and six plutonium-beryllium sources. A wide array of detectors and electronic equipment are available.to provide measurement and analysis capability.of laboratory produced or maintained radiation sources.

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

' facility location'from The University of Texas at Austin Main Campus to the Balcones'Research Center. The proposed.

move is in response to needs for expansion of other edu-cational programs and facilities on the Main Campus and the development of'the research center as a major research and engineering site. A submittal was made to the Nuclear Regulatory Commission in November for the approval of a combined Construction Permit and Operating License to be l applied to the proposed facility. Completion of final l ' plans.and issuance of the requested permits is expected in l

i.

1985 with construction scheduled for 1986. Facility completion and acceptance of the new facility is projected for the' spring of'1987.

I 1

o -

i i  : Decommission and dismantling of the current facility is being stu' died with plans to be submitted in early 1985.

Actual decommission and dismantling work is scheduled for

~

the first months of 1987. ~

The proposed _ facility will provide laboratories for the TRIGA reactor, neutron generator, radiation measure-ment.. preparation and-processing of radioactive samples, and office space.- Although the facility move consists primarily of moving the current TRIGA facility and other program activites into a single building at the Research Center, several improvements to the reactor' facility are planned to extend facility capability. These-include above

.. ground shield structure for. access to horizontal beam tubes, and increased power and pulse parameters. Plans are to-utilise the current 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 for the proposed facility. A few components such as the rod drives will be reconditioned.

t 4

e 2

. . . . .. _.. * .~u g

)

h PMEUMATic NUCLEAR ANALYTIC AL LABORATORY ;ji '

SYpEM7 , ,

d - . I I i; ..;

! I

.g .c Vraa s.af I-og ii ..

g, W , fl 8 e ,,1

? m#

m i. i, i; -

l My%

z e,...

.r l:

~

l i

I i

g g

.gI gi s'

l i .

l V^ YK if r l,l E

l' ~gl i

4Wl, . _ _ _ _ _..gj' g ,._,-__-_ __.u__

e

/N r- -

.t.  !

. 'l si o  :. _. _ _ _ r_ -% .

__ ____.ii.

=

=c

- - -j% ___.i-- -

r - - - - 5. ,W,. J- - - - - - ~P- -- - - - ;I 's i-i ML. E@tR 824 N 0  !!. . 8 ?f ~YN 'l

" h. . h*w-

71

.

4 _i a.-.,

J ' . . . . ).7, y[

. ..w.

. - l;1 i

u

? .c O lt IO,,STSE4 ,

o; , AT::.3.Z "i: $ 1i WELLS g 8

g, 8[j ig ' N, 1 .-

1i .

I cr eme wu m

@ 250 KW A'*'

, g} :y. i.} k. 18 ( I "N i s}l,

. ,I e :M .' . S,]

9 8 HEAT . l- ,7hh , . , l l l,.

M EXCHANGER % jg :i t , .--

---Y--rp. . .*' ~

_, gg ,l

.e e w

.. .,. ,.s . .- i.t .-

. in ge g  ;

-_ L_ .p_______ rht______.u.n . ______y8 t..- Z x  :. w .- tr+ *w wi . . - - _ _ _ _ -. 1 2 ;i e,' jl 'jli ll T -

i d.,

e c ore ,m e

i i m3. .

st.e7 l 8*""***

,i ll, i.

'~1 ,

" ~

el -#

l 0 f_

?

(&,8 - - ~ ~ ~ - - .y : : :_:::q1::

-- _ _: = _Qf :: ., sH09 U

• n==Ml .v _.;; - ; it li, . '  :.

.i e .

>> .. 'I__,, _ . .!

8 d 3 8

_ . _a 1, - _ 1 is e cs

.s l'

E Scale 1" = 8.533'

J 127 ..

e ~

Nuclear Activation ~~huclear

. Analysis Laboratory Teaching Laboratory 12 5

. 12 9 ..

i . .r ..

1318 Air Cond. .

Dist. Room "

R E ACTOR  :

LABORATORY -

c------- , l 31 . . a r

, s & .. . .

r Vestibule ::

Control i Room l . 131A ..

I .T Driveway office 133 -

104

F- r i

135 A I 135 B -

. h -

NORTH ylg, 2 TAYLOR !!ALL FLOOR PLAN

, ADJACENT ROO!!S TO 131 4

__ ~-

'(

' ..3 II. LABORATORY ADMINISTRATION A.' Ormanisation The'present organisational. chart'of the NETL program is presented in Figure 3. Budgeted NETL staff funding is pro-vided for a Supervisor / Assistant Director, technician /oper-stor, radiochemist, operator, and secretary. Budget sup-port is divided into full time positions for supervisor, technician and radiochemist; half time for an' operator; and quarter time for a secretary.

B. Personnel Personnel associated with the laborator) consist of NETL staff, faculty,. students, and certain other university personnel. The persornel involved in the NETL program during the past year are summarised in Table I.

C. Standina Committees

1. Reactor Committee The Reactor Committee convened and reviewed the activities occurring at the facility durina each calendar quarter of this reporting period. Committee meeting dates were April 30, July 2, October 26 and January 29. Committee composition is shown in Table 2.

2. Radiation Safety Committee The Radiation Safety Committee convened and re-

• viewed radiological safety priorities at the univer-sity during this reporting period. Committee meeting dates were April 10 and November 26. Committee comp-osition is shown in Table 2.

4 l

5

i A

is

s. Dean of Encinwrina Chairman-M. E. Departngnt Director

' Nuclear Engineering s

' N

, ,- Teaching Laboratory s Radiation 5 Reactor Safety s '

/ Connittee

. Connittee ,

~ Reactor Supervisor '

Reactor

. Instructors Technicians Experimenters LINE OF RESPONSIBILITY

_ _ _ _ _ _ _ _ _ _ _ _ CONSULTATION AND VET 0 POWER Fig. 3 CRCMl!ZATIONAL C11 ART e

6 e

l'

. Table I Facility Personnel Staff and Faculty Director D.E. Klein Assistant Director / Supervisor T.L. Bauer

. Nuclear Technical Specialist M.G. Krause Nuclear Technical Specialist D.H. Eppes Radiochemist F.Y. Iskander

. Assistant Professor N.E. Hertel Administrative Secretary B.J. Babich

_Sunnart Parsonnel Safety Officer H.W. Bryant Graduate Annistanta M. Ally A. Gaines A. Fatterson-Hine T. Sanders B. Kolda R. Savage E. Ibrahim G. Polansky L. Grater N. Poor D. Smith R. Hartley Student Analatanta J. Evans T. Tran 1

f I

l

\

l

Table 2

' Standing Committees lanctor Committee Chairpersons. H. L. Marcus Member N. E. Hertel Member: D. E. Klein

. Member: J.O. Ledbetter Student Member R. D. Manteufel (Thru 8/31/84)

Student Member N.D. Foor (After 9/1/84)

. Ex officio member T. L. Bauer Ex officio member: H.W. Bryant i

Ex officio member E. F. Gloyna Radiation Safety Committee Chairperson: P. J. Riley (Thru 8/31/84)

Chairperson: E. L. Sutton (After 9/1/84) ,

Member F. H. Bronson (Thru 8/31/84)

Member L. O. Morgan .

Member: D. E. Klein Member R. L. Shipman Member K. J. Caskey Member: C. Hoffman (After 9/1/84)

Ex officio member: H.W. Bryant .

Ex officio member P.T. Flawn i

l 8

1

F-4 D. Renart to the Co11ere of Ennineerina Each year the Reactor Committee provides a report ~ to the Dean of the College of Engineering describing activi-ties of the committee and a review or assessment of the operation of specific, portions of the NETL program-con-cerning the. reactor and other radiation producing equip-ment. Dr. Harris Marcus,' Reactor Committee Chairman, sum-

. marised the activities during this period saying, "The program has again completed a busy, successful year. With

. the prospect of an upgraded facility at BRC, a great deal

. of enthusiasm exists within the Nuclear Engineering Teaching Laboratory."

a 4

9 s

e f

9

III. LABORATORY DEVELOPMENT A. Organization Dr. Dale E. Klein continued as the Director and Dr.

Thomas L. Bauer continued as Reactor. Supervisor during the past year. B. J. Babich filled the Administrative Secretary position vacated by M. G. Morrison and D..H.

Eppes filled the Nuclear Technical Specialist position vacated by N. Povio. The remaining technical personnel remained unchanged. Key faculty and university support personnel also remained unchanged.

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

The Nuclear Engineering Teaching Laboratory's central feature is a Mark I TRIGA thermal fission reactor. Origin-ally licensed by the Atomic Energy Commission to operate at 10 KW in 1963, t he nuclear reactor and the associated labor-atory equipment have been updated over the past years and the research capabilities of the Laboratory are now more diverse. In 1968, the facility license was amended to allow the TRIGA reactor to operate at a steady state power level of 250 kW which increased experimental capabilities.

Other radiation producing devices maintained by the Laboratory are a thousand curie Co-60 irradiator, vert-ical neutron beam tube, suberitical assembly, industrial x-ray source, 14 MeV neutron generator, and several isotopic neutron sources. Different types of radiation detection devices provide the capacity'to monitor or analyse 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 reactce operation. Several organiseu classes routiaely utilise the reactor facility. Numerous other classes, organisations and groups schedule tours or demonstrations of the reactor facility. Courses utilising the reactor and associated facilities are listed in Table

3. Approximately 700 persons were admitted into the reactor facility during the past year.

10

r-A sc

+

Table 3-Courses Utilizing the Reactor and Associated Facilities Mechanical Engineering-Department

Course Mumber Course I Descr'inting

HE 361F Introductory Nuclear' Laboratory -

studies in radioactive decay, acti-vation, detection and measurement.- _

=-*- ME 361G Reactor Operations - studi'es in nuclear reactor parameters..instru--

mentation characteristics and regu-Llation.

ME 389R Nuclear Engineering Laboratory -

studies for graduate students in nuclear methods in measurement and analysis.

ME 3389R Special projects course f'or nuclear-engineering laboratory-sutdies as a summer course for foreign students.

ME 377K Projects in Mechanical Engineering -

individual study and experiment projects for undergraduates.

. ME 397 Current Studies in Engineering -

special projects course.for grad-uste study'of selected topics.. ,

Additional Courses in Other Departments <

GE0.388L' Isotope Geology - graduate course CH 376K Advanced Analytica1' Chemistry -

senior level course in instrumental and analytical methods. .

CE 390L Environmental Analysis . graduate course -

PHR 370K' Nuclear Pharmacy - senior level course in measurement and analysis methods with nuclear pharmaceuticals.

11 i

s

,.s, b \

.The'use, operation, regulation, security,;and moni--

LtoringTof the> Nuclear Engineering Teaching Laboratory is contro11ed'by the United States Nuclear Regulatory _Commis-sion,-the Nuclear Reactor Committee of The University of

' Texas,lthe Director of the Nuclear Engineering Teaching Laboratory..the Radiation Safety Committee and the Texas Department of Health Radiation Control Board.

C. Neutron Activation Analvais Facilities .

~

Th's Nuclear Analytical Laboratory has provided support for sindividual projects ranging from student laboratory sup-port'for advanced classes in chemistry, zoology, physics, and engineering to investigative projects.in environmental monitoring. Scientific articles based upon the results of

. sponsored and unsponsored research by this laboratory have been published or accepted for publication in several jour-

'nals,and proceedings, and have been presented at confer-ences at.the state, national and international level.

Radiation detection systems available include gamma ray Espectroscopy HpGe detection' acquisition and' analysis. ,

system, multi sample -

proportional counter, Na1 detectors. Si(Li)-detector, neutron detectors and associated electronic modules to accomplish several types of standard nuclear measurements. An important function j . of the laboratory is to support various research projects with the neutron activation analysis method and other re-lated nuclear radiation research techniques.

D. Nuclear Radiation'Laboratorv ,

The' Nuclear ~ Radiation Laboratory is utilised by the students and staff of the Nuclear Engineerin's Program at The University of Texas at Austin. The laboratory is located in the Engineering Science Building. The main feature of the laboratory is a 14 MeV Texas'Muciaar

. neutron generator. 'Three californium-252 neutron sources are also available for'use. The facility, with installed neutron shielding, provides an area where students and staff can perform experimen'ts utilising not only'the .h'igh energy neutrons-from the agueron generator but fission spectrum neutrons from Cf 222 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.

12

T3

1. s 1

=

• 1 IV. Facility Operations Summary

A.:.

Operating Experience-

- During_the period no significant'deviat'ionsifrom-normal'

. operating conditions.were observed-aside from the apparent

- failure and subsequent replacement.of the Percent Power UCIC'(uncompensated ionization chamber) described in the

~

facility changes section. .The facility emergency plan was approved by the Nuclear, Regulatory Commission and imple-mented. Established operating procedures and other required' procedures remai'ned unchanged.

, Licensed activities were performed by three persons with Senior Operator Fermits, .T.L. Bauer, M.G.'Krause and

+ N.A.'Fovio. Most operating activities.were in support of nuclear engineeringtand reactor operations,- research and education or demonstrations. No new experiments were proposed or approved. Excluding operation for demon-stration,: instruction.or routine' surveillance, the major >

experiment performed was neutron activation to support various research activities. Some operation also occurred for radioisotope production. Maintenance during the period

-consisted primarily of routine equipment repair and adjust-ments.

B. Reactor Shutdowns '

Reactor shutdowns (scrams) occuring during the reporting period are1summarised in Table 4, categor-

. ised according to the type of initiating event. Table 5 compares the number of inadvertent' shutdowns during this_ reporting periodito previous reporting periods.

C. Utilisation Reactor utilization' data for this reporting. period is summarised in Table 6. A summary of reactor utilization since initia1 ' 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.

13

gr- _.x ;-

. . . : ,r ,. - ,

t-: .

c. _ , -

c ': ., -

~ w-a >

.3 rp - -

i

r. .y h

l's_i g -

t Q;

-TABLE 4 REACTOR SCRAMS

~

i:.

Q~..- .%

t ,

- Intentional- i-- 6

' Operator Error -- 2

-i .

Instrument Error- .-- 3 I

• - Power Outage .-- 0 Safety -- 0 Total -- 11 ,

A TABLE 5 -

COMPARISON OF YEARLY INADVERTANT SCRAMS *

., 1'63 '64 ' '65 '66 '67 '68 '69 '70 '71 '72 '73 ~

10 9 3 4 3 11' .15 11 13 6 10

^

'74 '75 '76 '77 '78 '79 '80 '81 '82 '83 '84 4 7 5 9 11 12 7 7 8 6 5

• Iriadvertant- scrams are defined as all scrams that were not . intentionally

' initiated.

l-h I

't >

i i

r.

T l 14

-_m.--J__.______-

4 'g  ; I

?

a,-

, TABLE 6 NUCLEAR ENGINEERING TEACHING. LABORATORY-PERFORMANCE DATA,1984 - .

j a -

Total Hours- Total Number of Reactor In Burn-up Samples i Operat1on* (kW-hrs) Irradiated j First-  ;

Quarter-1984 ~54.4 6576 157

\

Second Quarter

' 1984 46.4 5776- 141 )

- Third l

Quarter -

1 1984 43.5 6504 185 i I

Fourth Quarter 1984 35.3 5950 184 l

l TarAL 179.6 24806 667 J I

(1.03 MWD)

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

' : .. j I

l I 15

1 TABLE 7

+

COMPARISON OF. PREVIOUS UTILIZATION DATA' Number of i Hours Reactor Burn-up- Samples In Operatien* (kW-hrs) . Irradiated Year 1965-66** -

104.5 251 63

'1966-67 150.0 595 202 1967-68*** 342.6 28,168 2449 .

, 1968-69 260.8- 49,985 1452 1969 222.0 36,477 1640

, 1970-71 262.5' 53,912 2990 l 1971-72 222.8 48,389 1946 1973' 318.6 45,794 1347 1974 226.1 27,641 778 1975 207.0 20,450 363 1976 135.7 11,312 468 1977. 139.3 '7,509 164 1978 171.9 -

26,870 178 j 1979 311.6 72,616 1568 I 1980 184.1 11,760 150 1981 258.5 18,165- 330 1982 247.6 16,150 294 ,

1983 260.2 24,028 477 l 1984 179.6 24,806 667 i

-TOTAL 4,205.2 524,878 17,526 (21.9 MWD)

• Includes experimental setup time, maintenance, etc.

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

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

16

i r

9 er 4

70 -

60 .

50 . ,_

g 40 .

T H

30 .

3 20 .

E 5 10 .

~~~""

'69' 70'71 72 73' 74"75' 76'77 '78' 79 80'81 '82 '83 84 8

68 YEAR Fig. 4 TOTAL BURNUP PER YEAR 17

y .

J N '[

.g

=;. : >

i J

. 4. - ,

1 s

=. -

3 .

Q w- .

-!.E

. I 2 -

9

.g ,

o 8 j ,

!E  ;

~ ~

O

. 68 69 70 71 72 73 '74 '75. 76 '77 78 '79 80 .81 82 '83 84 '

YEAR Fig. 5 NUMBER OF SAMPLES. IRRADIATED e

I I 18 '

i .. . .. _ _ _ _ _ _ . - - - - _ - _ _ _ __ _.

e

- E. Facility Changes

-The uncompensated ionisation chamber in the percent power channel was replaced with a compensatediionisation chamber. The replacement chamber had previously operated-as the los power channel before installation of the wide range fission chamber. Replacement of the uncompensated ionisation chamber was indicated by several sporadic decreased readings of' power level ('5% low) and subsequent measurement of chamber impedance. Resistance; measurements supported the indication ~that an insulation, connector, or chamber condition may have caused the observed loss of

. sensitivity. No unreviewed safety questions are presented by replacement of the defective chamber.

.- Operation of the reactor.in the pulse mode'has been dis-continued until the operation characteristics'of the compen-sated 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 re-evaluated in relation to the new facility proposal.

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 summarised 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 mes-sured 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 per-formed outside the laboratory are summarised in Table 12.

H. Radioactive Effluents

1. Liquid Waste No liquid radioactive waste was discharged during the reporting period.  !

19

9 ,.

^*; . ..

,- - .o

~

, n. . .

[y f e .,'

~ -

TABLE 8'

SUMMARY

OF' RADIATION EXPOSURE'

s. t, Range'of Exposure' . Number of Individuals

~in REM Students

.g Staff -Visitors .

Non-measurable ' exposure 13 21- 720

~

I0.0 '

'O.1L 0 0 0

~. _ 0.1 -

'O.25 0 0 0 Ju- 'O.25 ' .

0.5 0- 'O O

'O.5

O.75 0 0- 0' O.75 ~ c 1.0 ' O 0. 0 1.0- -

2.0 0 0- =0' ,

'2.0 .-  :

3.0~ 0 0 0

, Greater than 3.0 ~ 0 .0 0

' *Staff and Students: Film measured exposures below 10 mrem'x or y, 40 mrem -

hard 8 ; 20 mrem fast n, .or 10 mrem themal n during each reporting period.

Visitors: Pocket dosimeter exposures at or below 10 mrem.

, 20 L1 6

' +

4

. TABLE 9-

. -RADIATION EXPOSURE ANALYSIS' Average Radiation Greatest Radiation Exposure;Per Individual Exposure Per-Individual - r-

' Group- (mrem)~ '(mrem) e 1

Staf'f < 10(I < 10( }

' Students . < 10(I) < 10( }

~ Visitors: . < 10 < 10 y -#

(1) Exposures less than minimum detectable level- (10 mrem 'x-y)

. during each film badge reporting period.

7 4

[

b 9<

21

77;:;

F . ,

?

~ ' TABLE 10

' ~

y_.

, ~

s I' ~i_ -

LABORATORY RADIATION LEVELS-

,.ke

-Location ,

' Average (mR/hr)( ) ' Maximum (mR/hr)( }

" Wall Near Control P.ane12 1 x 10 -3 1 x 10 ~I '. ,.

Wall Near: Water: Purification -

System -- 7 x 10- 6 x 10'

.,s ,

r

- Ceiling Directly Above -2 5 x 10 O Reactor Pool 6 x 10 (1) Determined using results of fixed film badge monitors' averaged' over one year.

(2) Annual film measured exposure divided by. effective annual reactor full power hours.

O i o

4 e

22 l --

. -n

• w ' ; ,

. =

,. .i .

s E  % ,4

.~ .

E W i .,

~

. TABLE 11

'4^

LABORATORY CONTAMINATION LEVELS-4

. ;'} '

Location' Average Maximum

. Floor 1 25 dpm < 50 dpm

~ ,. .

JWork Surfaces < 2'5 dpm . < 50 dpm f}~

Pool. Water (1) .

-< 112 pCi/t. '< 500 pCi/E-Z

% i 1 c r

(1) Measured when reactor not operating.-

~

~

w

? ,

i e 4

.9.

r s Y

s'-'

' / -

u i

7

~ N

^ '.

^

'-.9'..

8

?

.-; ; - s -

r

.i 23-

~ ~_k. - .

.y r- .

1"

.37, 2 !- _ . .

t'. 7 .

, . .e 7_

'~

< 'I ,

.c .,

e 4d -

,, , = ,. ,

l

~

- g

. > - ,. ,- ' TABLE'12 m; ~ +

~ENVIRONMENTALTSURVEYS 4

.?.

• w r

' ~

Location Average (tnrem/hr) Maximum (mrem /hr)

P

1~ 0.01 0.01-

• l '2' O.01 0.01

, 3- - 0'. 01 0.04 .

c.

0.01 0.01 4

.5 0.01 0.01 16- 0.01 0.01

?Waller Creek-(2)- 8 pCi/E 32 pCi/E J

2 y ~(1) Monitoring location's shown in Figure 6.- ~

..n-. .

s (2) Water sample from stream flowing through _ campus approximately 0.25

~

. miles from. reactor. facility.

+

I

-.-7 n

d

")

2.-..

i.

s9

[

24 D . .-

i 6

-1 127 ..

S p Nuclear Activation - h ucl~~a-Analysis Laboratory _ Teaching

---

Laboratory 2

li 12 5

.r 12 9 ..

l ..

131B Air Cond.

Dist. Room "

' R E ACTOR LABORATORY -

_,c------- ,

. l 31 .. .

4 r r ' Vestibule .' 4 Control H i

! . l l

Room l - 131 A ..

I I

summe - en-meme amm --t :T '- "

3

. Driveway office 133 -

104

---i s-i S5B 135 A y

NORTH l

I Fig. 6 -TAYLOR HALL ENVIRONMENTAL SURVEY LOCATIONS l

l 25

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

"The total estimated amount of radioactivity released was; calculated based on experimental equilibrium Ar4I >

-concentration measurements '(4' x 10-8 ci/m3) adjusted by.

the number of full power. hours operated.during the per-iod .: Although aircleakage from the laborator.y is

. restricted, an effective air change rate-of.two per hour'(0.37 m3/sec) is assumed with dilution at.the re-lease point-(0.'14 sec/m3). A summary of the calculated

.. radioactive gaseous discharges during the reporting period is presented ~in Table.13.

3. Solid Waste The activity andfamounts of solid wast'e. discharge'd during.the reporting period are summarized in Table

14. . All solid waste materials were packaged and' shipped, along with radioactive waste generated in

.other departments, by the University Safety Office.

4 4

6 26

A TABLE 13'

^

MONTHLY SIMfARY-0F GASEOUS WASTE DISCHARCES Date of Total Total Estimated Average Percent of the Total Estimated Average Estimated Average

. Discharge Estimated Estimated Atmospheric Applicable . Pehent of-tjuantity of. Concentration. Concentration of. SEPC (f the-Radioactivity lluantity of Diluted IWC for Diluted Radioactivity in of Itadioactive Other. $lgnificant IIeleased Argon-4) -Estimated.

Concentration of Concentration Particulate form Particulates Radlonuclides in Release was-(Curles) Released Argon-41 at of Argon-4I at with Half-Life Released Ifith Discharp if' ~ >201 of the (Curles) Point of Asiease Point of lielease >8 Days lis1f-Life >8 Days . <>20% or the- .Appilcable-(UCI) (Curles) (Curles) . Appilcable frC IIPC -

(UCi) (pCl/cc). (1) (pCl/cc)-

Jan. 258 258 1.4 x 10

-I1 3.4 x 10- flone flot Appilcable Not Applicable - Ilot Applicable 1 -1 Feb. 1176 1176 6.3 x 10 1.6 x 10 None not Applicable. Not A,.plicable. Ilot Applicable March 4 -I3 -4 Not Appilcable

~

4 2.5 x 10 6.2 x 10 None Not Applicaole plot Appli able April 345

~

-II -2 345 1.8 x 10 4.6 x 10 leone Not Applic'able . ' Not Applicable flot Applicable May -l1 213- 213 1.1 x 10 2.8 x 10- lione flot Appilcable Not Applicable Ilot Applicable June 706 706

-II -2 lione Not App 1tcable ~ Not Applicable 3.8 x 10 9.4 x 10 Not Applicable July -13 11 11 6.1 x 10 1.5 x 10 -3 None Not Applicable llot Applicable flot Applicable 761 -I1 -I' August 761 4.1 x 10 1.0 x 10 lione Not Appilcable Not Appilcable Ilot Applicable

-II -2 Sept. 651 651 '3.5 x 10 8.7 x 10 ggon, geog Appiicable . .Not Appilcable Not Appilcable Oct, g g g g lione flot Appilcable Not Appilcab b hr A;plicable Nov. 668' 668 3.6 x 10 -11 -

8.9 x 10

-2 lione Not Applicable- Not Applicable Not Appiicable Dec. 635 635 -11 -2 3.4 x 10 8.5 x 10 lione Not Applicable Not Applicable Ilot Applicable 5428 5428 -11 AfsluAL VALUE 2.9 x 10 6.0 x 10- None Not Applicable Not Appilcable Not Applicable 27

7 .-

r 1 .

-'.t

~ ~

N:

,...ht: , ,

+ .

x r a

P V .1 +c TABLE;14

,- c.

( -

~ ANNUAL-

SUMMARY

OF SOLID WASTE DISPOSAL

.i

- Activity Vo16me Shipment Date (1) t 3

.2 45 pCi~ March 5, 1985 2 ft J

- (1) All' shipments made to Iso'tex in Friendswoo'd, Texas.

y -

e, n.

e i

t b>

.6,

.e +

)

-< 28

.. e

r . . .

. V. Laboratory Inspections A. ,NRC. Inspection-Fe'ruary b 27, 1984-Th'e inspection examined the activities. conducted

. under. license SNM-180. The inspection consisted of.

selective examination of procedures and representative records, interviews with personnel and observations tor the inspector. During the sco'pe of'the inspection, one

-vi olat ion.was-identified. The violation originated from

. difference 2in the frequency and allowable. tolerance speci-

.. f i e d . cnt calibrations of survey instruments as stated in License-R-92 and License SNM 180. Until'this difference is eliminated, calibrations shall.be performed to meet the.

. - more' stringent requirement as stated in license SNM 180.

B. TDH Inspection September 17-18, 1984 The inspection consisted of a review of activities and radioactive materials used at The. University of Texas at Austin as authorized by TDH License.

e 4

6 5

29

\

r e

4 v d

i

• ~

V I ~. Public Service Activities

f 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.

B. . Lectures'and Presentations On numerous occasions during 1984 the NETL' staff' talked to.various organizations about' subjects including'but not.

limited:to: " Nuclear Reactor.~ Safety," " Nuclear Engineering and Society," "Research and Development of. Energy Resources," " Energy and the Environment," and "What hap-7 pened at Three Mile Island." '

i . C. Reactor Facility Tours i

During 1984, 720 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 fron'sevaral non-engineering related college courses visited tt 8.tcility.

4 Numerous college ' engineering related classes .n. several student engineering organizations also toured the facility..

Safety personnel with' Austin Fire Department, UT Police Department..UT Safety Office and the Texa's Department of

. Health also visited the. facility to remain familiar with the' laboratory and emergency respon'se' procedures unique to

the facility..

i i

! 30

--1-. .- . . . .--.--,-.__...i...-..._,-----.-----,---...,m,--.-._--._..J---

Y 1

.: VII.' Re' search Activities

'The Nuclear 1 Engineering Teaching 1 Laboratory pursues ,

research ofEboth sponsored.and unsponsored projects 1in several:different areas.' The following section lists research projects in which.the laboratory has participated.

Majorir.esearch: funding or grants are presented in Table 15.

.A. The U.S. Dena'rtment of Enerav has provided research support by providing reactor fuel cycle' assistance for the currently operating reactor core at The . Univ'ersity of Texas '

, at-Austin TRIGA reactor.-

B. -The Electric Utility Connanies of Texas have sponsored

. Summer High School Science Teachers Symposium, a program designed to'familiarise these teachers with the theory and technology of energy sources.

C. Heat Transfer and Friction Factor-Analysis for Artificially Rounhened Surfaces i Personnel: Dale Klein, NETL' J. Parker Lamb, Mechanical Engineering Mike Krause,~-NETL Gary Polansky, Mechanical 3 Engineering Soonsored by: Center for. Energy' Studies National Science Foundation University.Research Institute Descrintion:

The proposed research is to determine the heat transfer'and friction characteristics for surfaces with discrete roughness geometry. Two major as'ects p are to be i examined in that this is both an experimental andHan anal-ytical 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 31

-- e, ,e,--m- , ,,,,,y - ,m -r-,-r,m- n., ,-,ane,,.e,,-.,n-,.,,..,vn,,__n--n_n...----.~-J

f~

, e r ,

R - '

t-fy > ,

TABLE.15

!s{

RESEARCH FUNDING l' ,

- Texas Atomic Energy Research Foundation-l1/83 - 8/84' 18,386 9/82 - 8/841 33,732

< Department of Energy -- Fuel Program ------

Center for Energy Studies 5/82 - 5/84 10,000

. . . 9/83 '8/84 6,600 6/84 - 8/84 1,400

-National Science Foundation 2/81 - 7/84. 76,376

. Texas Low Level Radioactive Waste Disposal Authority 9/84 - 8/85 9,736

. University of Texas-College of Engineering

.. Equipment Fund 9/83 - 8/84 , 21,400

' Center- for Fusion Eng'ineering 5/83 - 5/84 38,094 i:'

DOE Fellowship Program (Institutional Allowance) 4,000

' University Research Institute

, : ,- 9/84 - 8/85 6,000 TarAL $225,724 32 9

,l .

. without. making detailed. velocity and' temperature profile

1. 1 ' measurements.. Analytical predictions.will be made utilising fundamental parameters in boundary layer. theory.

- coupled with the latest'information on rough surfaces using

' integral techniques. Results from the' experimental and analytical methods will be compared in' order to gain

insight as to the dominant mechanism involved for the use

.'of discrete rough surfaces. . This research has fundamental application for-heat transfer augmentation.

. D. Measurement of Vanadium in Een White Dieta Personnel: T . L' . . B a u e r . NETL

, M. Ally, NETL

.Snonsored by: 'J.H. Freeland, Home Economics Department, UT at Austin Descrintion:

-Nutritional studies on takeup and retention of

.some trace elements in the human diet include the elements ,

of V and Mn.- Measurements were performed to determine the-

< vanadium content of a test diet prepared primarily from egg whites.

E. Interlaboratory Connarison of Element Analysis of Coal Personnel: T.L. Bauer, NETL F.Y. Iskander, NETL Snonsored hv': C. Ho, Bureau of Economic Geology Descrintigg:

Several core samples containing coal materials

' and other rock material from Texas sites were analysed by INAA. Thirty-eight (38) elements were determined in the-samples and compared to analysis performed by alternate analytical laboratory methods.

G 33

.- F. Analtais of Elements in Cinarette Tobacco. Filter.

Ash and Paner-Personnel: F.Y. Iskander, NETL

'T.L. Bauer, NETL Snonsored by: NETL Descrintion:

Cigarettes from several countries and various ,

domestic brands, including different brand _ types, were ,

' analysed by INAA methods. Results were examined and ,

compared to values reported in the literature. Approxi-mately thirty elements were identified. Measurement de-termined the element content in the unsmoked' tobacco, the residual ash after smoking, the residue in the filter and the paper from which the tobacco was removed. Presence of some elements indicative of additives at either the proces-sing or production stage were noted although evidence was

- not direct.

G. Calcium Content in Cereal Matter Personnel: F.Y.~Iskander, NETL M.M. Morad Texas A&M Soonsored by: Texas A&M University Descrintion:

Traditional method for tortilla and most corn snack-based food involve cooking of corn with calcium hydroxide for 12 - 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />. A new method, pre-soaking technique, was introduced in which a 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> steeping step was followed by 80 minutes of cooking. By this method, up to 40% of energy expended during alkali cooking of corn can be achieved and produce a similar quality product. INAA was employed to evaluate Ca content of starting material, during cooking and in the final product.

4 5

e

, 34 L

r- ,

2 , 27 ,,

O L

e H ,

E. 5 . .

f. '

I- ,H. ' Cadmium and Calcium Untake Studies 4 Personnels- E. Sorenson, Pharmacy, Dept..UT f'

D.~Acosta, Pharmacy Dept. UT

. -T.L. Bauer. NETL l., '

inonsored by: John Hopkins Center for Alterna-

~

tives' to Animal. Testing-

, Descrintions-Radioactive tracers of Cd 104, Ca45, and Cd 115

.. were employed in, studies of binding and tra'asport related.

to cell uptake mechanisms. Several experiments with cell

! cultures of rat. hepatocyte cells were performed to determine the effect of calcium presence on.the intake of the toxic element cadmium.

T. . Fission Product'Absorntion in Continuous 1v Processed Fission Sunnrassed Fusion Hybrid Reactor Blankats l

Personeel: Dale Klein, NETL J.W. Davidson, NETL l;

Ann Patterson-Hine. NETL soonsored by

Department of Energy Fellowship Center for Fusion Engineering I

Descrintion:

I r

-The effect ~ on blanket performance of fission

' product absorption in lithium / molten salt hybrid reactor a, i'

blankets is being'investis'ated. Neutron flux' spectra in blankets of varying fuel and fission product compositions are being determined using the discrete ordinates codes, ANISN, and D0T-IV with multigroup cross section data from j' ~ . VITAMIN-C. Flux levels and spectra 11y weighted cross i section libraries for the blanket materials, fuel, and l

fission products will be established for 'se u in the depletion analyses. Generation and depletion of the, various isotopes in the blanket will be calculated using l

ORIGEN. A lumped fission product model will be used in the j transport calculations; however, detailed information' con-

l. cerning the constituents of the lump will be included in L* the depletion analysis.

~ .

L 35

k -

{#

p

~* . ,

)

L h

[v In addition to full and partial reprocessing of the >

. molten salt, alternative processing concepts.will be investigated. A parametric' study of_the' effects of .

L processing performance.will be carried out.. This study, will result: in the characterisation of the~ fission product  ;

-concentration in the molten salt.with~ respect to isotopics, 'l

' neutron absorption, and the effects on. blanket ~ paraatters

^

such~asothe tritium and fissile breeding ratios.

J. P r e s s'u r e Dron and' Heat Transfer Measurements o f L ia: Lid =

Metal Flowinn in a' Packed Red-Under the Influence of a i . ~ Mannetic Field g Personnel

Dale Klein, NETL

.. Tom Sanders, NETL Larry Grater, Mechanical

! Engineering .

L Mike Crawford, Mechanical ,

L Engineering I l

,. Snonsored by: ' Center for Fusion Engineering  !

Texas Atomic. Energy Research [

L Foundation  :

i i

! Descrintion: f The flow'of electrically conducting fluids through porous media in the presence of a magnetic field has recently begun to' generate significant' interest due to L,

_ potential spplications for fusion reactors. . This study is L i designed to examine the pressure drop and heat transfer from a liquid metal (NaK) flowing through a packed bed l, of. stainless steel spheres under the influence of a trans-l Verse magnetic field. Results of this investigation should ,

L :have direct applications on the design of fusion-breeder -

L blankets using liquid metal flowing around' spheres of fertile material.

• i f

, i I

l

, 1 l 36  :

I  !

L

. K. g22 Production for Enhance'd Oil Recovery Usine Texas Linnite and Nuclear Process Heat Personnel: B. Kolda. NETL Dale Klein, NETL Soonsored by: Center for Energy Studies Descriotion:

Carbon dioxide miscible displacement is one method of enhanced oil recovery which can increase ultimate

, production beyond that obtained from primary and secondary methods. Current sources of CO2 for this application are obtained from natural CO2 wells, by-product CO 2 and on-site

. . generation of CO2 This project is to examine the feasibility of obtaining CO 2 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.

L. Exam'ination of Reversed-Field Pinch Reactor usine a Homonolar Generator as a Power Sunoly Personnel: Herbert Woodson, Electrical Engineering Dale Klein, NETL Erfan Ibrahim, NETL Soonsored by: Center for Fusion Engineering Texas Atomic Energy Research Foundation Descriotion:

The Reversed-Field Pinch (RFP) reactor is one of the conceptual designa under study for the production of electrical energy from fusion. Several reactor design evaluations have been undertaken at the Los Alamos National Laboratory. The RFP is a toroidal shaped device that holds a plasma by the simultaneous presence of a toroidal field and a poloidal field. A homopolar generator power supply has been developed by the Center for Electromechanics (CEH) at The University of Texas at Austin. The goal of this study is to examine the RFP and the homopolar power supply developed by CEM as a conceptual design. Parameters to be 37

i '

- -investigated' include the physical size,of the RFP, the power supply required and the fundamental ~ plasma requirements for ignition.

M. Construction of a Larne Beniamin= Counter

' Personnel: Nolan E. Hertel, NETL Richard Savage, NETL Soonsored by: Texas Atomic Energy Research Foundation Descriotion:

. A large spherical proton-recoil proportional

-counter is being constructed for use in measuring neutron

. energy spectra below 2MeV. By differentiating proton-recoil spectra obtained with the detector filling gas (methane or hydrogen)Dat various pressures, an unknown neutron energy spectrum can be reconstructed. This de .

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

N. Trsusient-Analysis of Fissile and Fusile Fuel Traiec- ,

tories for Hybrid and Convertor Reactor Symbioses Personnel: Nolan E. Hertel, NETL J. Wiley Davidson, NETL Yukitaka Kunimoto, NETL Soonsored by: Texas Atomic Energy Research Foundation Descriotion:

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

fusile inventories for stockpiles, as well as for both 38 i

r- .

+

. hybrid and convertor reactor' cores and blankets. This transient analysis is being performed for a variety of fission convertor and anticipated fusion hybrid reactor concepts and fuel cycles.- Such an analysis will allow the prediction of initial stockpile requirements in addition to providing a more accurate assessment of short term symbiotic system doubling times.

O. Neutron Transoort Studies: Neutron Multiolication by Beryllium

. Personnel: Nolan E. Hertel, NETL Center for Fusion' Engineering

. Soonsored by: Pending, National Science Foundation Descriotion:

The use of beryllium as a neutron multiplier is central to the current fusion breeder design. Recent measurements of beryllium neutron multiplication-and re-evalutions of beryllium nuclear data indicate that the mul-tiplying performance of beryllium previously has been over-estimated, possibly by as much as 25%. If beryllium's per-formance as a neutron multiplier has indeed been overesti-mated even by as much as 10%, the direction of the fusion breeder program in the United States might well change. It is tantamount to the current fusion breeder concepts that the issue of beryllium neutron multiplication be resolved.

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

The beryllium experiment has been designed'to measure multiplication 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 multi-plication will be obtained'directly from summing weighted Bonner ball measurements of the neutron leakage. The neutron multiplication obtained in this manner will provide a number which tests the capability of the current beryllium nuclear data to calculate total neutron multi-plication.

39

~ ~

P. Thermal Analysis'of Nuclear'Shippinn Containers Personnel: Randy Manteufel, NETL Dale E. Klein, NETL

'Soonsored by: Sandia National L'aboratories Descriotion:

.The thermal. analysis o f 1sh'ipping containers to-be used in the transport of1cpent nuclear fuel is.an impor--

. ' tant safety. issue. Sandia National Laboratories has been involved in safety issues for the transport of nuclear ma-terial for many years. The University of Texas at Austin 3

. (NETL) has been involved in the specific issues of thermal-analysis of these containers-for several years. The cur-rent project is intended to benchmark a therma'l analysis code (Q/TRAN) and pre _and post processing software PATRAN-G using four standard model-problems. Comparisons will be made with other applicable codes. currently available at UT-(including HEATING 5). Sensitivity studies will be per-formed to-further' evaluate'Q/TRAN's suitability for thermal analysis. ' Enhancements, if any, that will increase the-current. capabilities of the software will be suggested and developed if-feasible.

Q.. Determination of Trace Element Imourities in Aspirin Tablets Personnel: Felib Y. Iskander, NETL Dale E. Klein, NETL

, Thomas L. Bauer, NETL Soonsored by: Nuclear Engineering Teaching

. Laboratory Descriotion:

Twenty-five trace and minor elements-in five

- differene aspirin brands were determined. The results were compared :to literature values.

0 40

A

[

1 4 4

w

'R.  : Determination of 25 Elements in Texas Har'd-Red' Winter Wheat and Its Millina Fractions. '

, [ Personnel: Felib Y..Iskander,-NETL

-i 'Snonsored by: ' Nuclear l Engineering Teaihing

Laboratory

' Texas'A&M University Descrintion:

Five varieties of he-d: red winter wheat-(Scout

- 66,.Coker:767,.Vona.. TAM 101 and TAM 105) grown in Texas, 1982 were: milled and separated into sixifractions using U.S. standard sieves. Twenty-five' elements were determined in'ench fractica as well as in the whole wheat. . Protein,

-in vitro protein digestibility and ash content of~each frac-tion were'also determined. Correlation between.the results was: studied.

s - .

-S. Vanadium Sorotion by Crude-Oil L

Personnel: Felib.Y. Iskander, NETL-

.F.S. Jacobs, ODU

'Soonsored by: Nuclear Engineering Teaching Laboratory University of Old Dominion (Virginia)

Descriotion:

~

Crude oil and ashphaltenes samples were equilibrated with vanadium salt-solutions then' separated ~

i :into. petroleum ~a'nd aqueous phases. Each: phase was ana-

~

.lyzed for.vanadiumLby.INAA. Sorption of!V02+ occurs to a-

- greatersextent than the sorption o'f V0+. .The effect offpH, presence of other ions.and oil-to-aqueous voluse ratio ~was studied. Three< crude oil samples were used (Jobo, Tis ,

'Juana and Bachaquero) and one asphaltene (Jobo).

l-T h-I t

[

l' l.

1 41 I

h L:

x 7

A 1

F

. - T .: Determination of Lanthanum in Soil Samoles Personnel: Felib Y.7Iskander, NETL Thomas L. Bauer, NETL J. Rhodes, (CSI)'

Soonsored by: Nuclear' Engineering Teaching Laboratory Columbia Scientific Industries Descrintion:

. .The use-of rare earth elements (e.g...La) as an

- indicator.in oil exploration was_the prime' target in this

~

- study.. Several samples. were activated and the activity of

. 141La was measured.

U. Determination of Toxic and Other Elements in Rain Sedi-ment Collected in Nineria Personnel: Felib Y. Iskander, NETL Bode Asubiojo, U of Ife Soonsored by: Nuclear Engineering Teaching

-Laboratory

-University of IFE'(Nigeria)-

Descrintion:

Rainfall, after drought season, washes'out the suspended dust and air particulates. Twenty-seven (27) ele-ments were determined in six samples collected at different locations.

\

.: 6 42

1c= ,

t 6 ,

. x s

. 00% ,

~ '

4

.i ;

-- ' V. Analysis of Soil Samoles from South America ,

Personnel: Thomas L. Bauer, NETL Felib.Y. Iskander,'NETL~

I~ ,

Soonsored by: , Center for-Maximum Potential Building Systems

.Descriotion:

~ Clay samp1'es in1different locations were.

analysed.for A1, Mg, K,CNa_and.Ca to determine suitable

~

. 'componen'ts of.certain' minerals. -Study supported-appli-cations.of two types of mineral deposits.for building construction in areas of low economic income.

.W . Measurement of Gold Personn31: 'Felib Y. Iskander, NETL Soonsored by: Nuclear Engineering Teaching Laboratory H.S.~ Jackson ~_ Sand & Gravel, Inc.

Irving,. Texas 75061

Description:

Different methods were used to extract gold and other precious metals. Several samples that represents-the

, fextraction steps were analyzeduto identify the_ efficiency.

of these methods. The concentration of gold ranged from 15 ng g-l to ;800 ,pg1 g-1 t

D G

43

VIII. Publications From the Nuclear Engineering Teaching Laboratory

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

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

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

June , 1962.

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

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

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

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

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

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

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

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

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

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

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

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

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

44

t

14. D. A. ' Pullen, " A~ Rod Oscillator. Design' and Zero Power Transfer Function Measurement for a TRIGA Mark I Reactor," Masters Thesis.. Mechanical Engineering

• • - (Nuclear Engineering), The University of Texas, January,1967.

15. G.F. Malan, " Transfer Function Analysis of Temperature and Xenon Feedback

~

in Couple:1-Core Nuclear Reactor Systems", Masters Thesis, Mechanical Engineering Department The University of Texas, 69 pp., August 1967.

-16. 'M.G.LStevenson " Investigations on the Macroscopic Nodal Approach to Space-dependent Nuclear Reactor Kinetics", Ph.D. Dissertation, The University

.of Texas, 203 pp., August 1968.

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

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

18. R. Valient'e.. " Neutron Radiography with the University of Texas TRIGA >

Nuclear Reactor", Masters Thesis, Physics (Nuclear Engineering), The University of Texas August 1968.

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

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

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

Nucl. Soc., 11:2,_582 (November 1968).

22. G.D. Bouchey and S.J. Gage, " Neutron Radiography with a Small Subcritical Reactor", Trans. Am. Nucl. Soc., ,21_2_, 462-463, 1969.

- 23. G.D. Atkinson, Jr., W. Coltharp, R. Cramatges, E.'0elkers, 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 Cit , Proceedings of the Offshore Technology Conference, Dallas, Texas (1969)y" .

24. J.A. Villalobos, "A Study of Gamma Radiation Dosimetry Techniques and Application to Radiation Field Mapping", Masters Thesis, Physics Department (NuclearEngineering),TheUniversityofTexas, January 1969.

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

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

- Texas, January 1969.

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

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

1969. .

45 1

p,

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

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

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

30. F.A. Rodriguez, S.J. Gage, and K.M. Ralls, " Nondestructive Neutron Activation Analysis for Trace Impurities in Niobium", Seventh Symposium on Nondestructive Evaluation of Components and Materials in~ Aerospace, Weapon

. Systems, and Nuclear Applications, San Antonio, Texas (1969). ,

1

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

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

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

Studies in Genetics, Marshall R. Wheeler Ed., The University of Texas Press, Austin, Texas 1969.

34. G.D. Bouchey and S.J. Gage, " Development and Potential Utilization of a Neutron Radiography Facility at The University of Texas NuclearReactor Laboratory", 1 Seventh Symposium on Nondestructive Evaluation of Components and Materials in (

Aerospace. Weapons Systems, and Nuclear Applications, San Antonio, Texas (1969).

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

p. 287, 1968.

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

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

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

12.,495-496,(1969).

38. F.G. Pasos, "Nondispersive X-Ray Fluorescence Analysis Using a Lithium-

, Drifted Germanium Detector" Masters Thesis, Physics Department, The University of Texas, 54 pp., January 1969.

46 .

3

t 4

' A x  %.

I g 139. P.J. Rodriguez, " Time and Energy. Dependent Neutron D'istribution in.a-Pulsed Multiplying: Medium", Ph.D. Dissertation; The: University.of Texas, 2.05 pp.,. January.1969.-

l40'.' . G.D. Bouchey,' B.V.' Koen', C.S. B'eightler,: "The Optimal Allocat!1on of :

Energy in Industrial and Agro-Industrial Complexes Using Dynamic Programing",

Nucl . - Sci . and Ener. c Vol .. 4.1,-70-78 (1970).

"41. G.F.' .Malan and B.V. Koen, "A Nonlinear Prog'raming' Approach to Optimal Control of Nuclear Reactors", Tran's.1 Am. - Nucl . Soc. , November 1970.

- 42.' ' M.G.' Stevenson and S.J'. Gage, " Application of 'a Coupled Fission Mode -

Approach to Modular Reactor Kinetics",' Journal' of Nucl . Energy, Vol. '24, pp.1-10. . Pergamon Press 1970. Printed in Northern Ireland.

43. . G.D. Bouchey and S.'J. Gage, " Neutron Radiography at The University of

.. , "TexasNuclearReactorLaboratory",Isotopesand.RadiationTechnology1, 294-296-(Spring,1970).

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

145. - A.H. Updaneta, "A Programmed Associative Analyzer", Masters Thesis. .

' Mechanical . Engineering (Nuclear Engineer.ing), The University of Texas. December 1960. ,

46. G.D. Bouchey and S.J. Gage, " Detection-a'nd Location of Leaking TRIGA-Reactor Fuel Elements", GA Publication T-117, Papers and Abstracts. TRIGA Reactor Owners' Seminar February 19-20,1970 (Denver, Colorado) p.- 43.

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

~

48. G.D. Atkinson, Jr., J.B. Whitwerth, and S.J. Gage, "NAAC0L--A. Spectrum Analysis Routine for the Small Laboratory",' 21st Mid-America Symposium on

' Spectroscopy,-Chicago, Illinois (1970).

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

" Computer-Aided Multielement Gama Ray Analysis with a Compton Suppressed .

Ge(Li) Radiation Source", Ninth National of the Society of Applied Spectros-copy. New Orleans, Louisiana, October 5-9, 1970.

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

51. V.H. Chanto, " Neutron Activation Analysis of Chlorine and Bromine in Some

. Haliburton-Bancroft Rocks and Minerals", Masters Thesis Physics (Nuclear ,

Engineering),TheUniversityofTexas, January 1970. ,

47 c ,

x

>q -

3 2

52. 'J.J. Chromik and E.L. Draper, 'Jr.,;" Energy Integral Tests of Differential ~

Fission Cross $ection Data", Trans.-Am. Nucl. Soc., Vol. 13,-No. 2,.p. 755

~

'(1970) . .

,53. R.5 Gramatges-Figueras, " Neutron Waves in Cylindrical Geometries for a Subcritical: Reactor", Masters Thesis', Mechanical. Engineering Department, The University of-Texas. 98 pp., Ma'y 1970 1 54. E.10elkers, Jr.. "ALLearning Method for .Identi*ication of Nuclear Reactor -

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

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

~~

.to the Study of Interstitial Solid Solution'of Oxygen in Niobium and in

~ Niobium-Titanium Alloys",- Ph.D. Dissertation, The University of Texas.131 pp.

- August 1970.

-56. .J.R. Deen, " Calculation of Resonance Integrals Using the Intermediate

, Resonance Approximation", Masters Thesis, Mechanical Engineering Department, The University of Texas, 140 pp., January 1970.

57. C.T. Rombough, " Application of Queueing Theory to Closed-Loop Computer--

Reactor Control Systems", Masters Thesis, Mechanical Engineering. Department, The University. of Texas, .78 pp. , December 1970.

A.H.U. Bohorquez, "A Programed Associative Anal'yzer", Masters Thesis,

~

58.

Mechanical Engineering Department, The Universi,ty of Texas, 98 pp. December -

1970.

59.- S.J.' Gage.and D.G. Jopling, The Nuplex Concept: Potential for the.

SINB' Region, Southern Interstate Nuclear Board,-250 pp., March 22, 1971. .

• =

l 60. G.F 'Malan and B.V. Koen.. " Application of Nonlinear Programming to the

. Optimal Control of a Point Model Nuclear Reactor", Nucl. Sci.' and Engr. ,

(1971).

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

62. A.H. Pradzynski and S.J. Gage, " Nondestructive Identification of Material by Nondispersive X-Ray Fluorescence Spectroscopy Using Si(L'i) Detectors and Radioisotopic Sources", Proc. Eighth Symposium.on Nondestructive Evaluation in Aerospace, Weapons Systems,'and Nuclear Applications, . San Antonio, Texas (1971).

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

48 c  ;

m g -

-. x-s .

y,. .

+ -. .

h^ ,-.

f

~ 64. S.J. GageLE.5Linn' Draper, Jr., G.D.:Bouchey, and.R.R. Day, " Design and Construction' of aLVersatile:Cf-252 Source-Shield and_ Experimental Facility", '

c- Neutron Sources and ' Application _s, CONF-710402, Vol . 2, Proc.. of ANS Topical .

. Meeting,; Augusta., Georgia,; April 19-21, 1971'.

65.' D.G.iJopling and S.J.. Gage,. "Public. Resistance 1 to Nuc1' ear Reactor Siting",,

~

.Nucl ear News,74:3,32-351(March 1971).

~

66. ~J.8. .Whitworth,:G.D. Atkinson, and S.J. Gage, Some Recent- Applications

. of Nuclear Analysis Techniques;to Typical Forensic. Evidence." 23rd Annual-Pro-gram American Academy for Forensic Sciences, Phoenix,1 Arizona (February 25,.

.: 1971)

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

" Multiple Foi1LActivation Spectrum Determination Using a Numerical Direct-

~. Search Technique", Trans. Am. Nucl. Soc. , Vol.14_:2, pp. 667-668, (October 1971). .

1

63. G.D. Bouchey, B' V. Koen, and C.S. Beightler, '"The Optimization of Nuclear 23ystems by~ Geometric Programing, Nucl.' Sci. and Engr. 44.. 4 267-272 (1971).

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

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

Anal sis with a Cf-252 Neutron Source", Trans'. - Am. Nucl . Soc. , (October

.1971 .

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

D Tailored Reactor Spectrum Preparation and-Measurement", Nuclear Science.

and Engineering, 4_6, 22, - (1971 ) .-

72. . E. Linn Draper,- Jr., " Integral Reaction Rate Deterininations Part 'li:

Fission Rate' Measurements", Nuclear' Science and Engineering, 4_6, 31 -(1971).

s ,.

73. . G.D.. Bouchey and- S.J. Gage,'"Det~ection and Location of Leaking .TRIGA l Reactor Fue1 ~ Elements", Nuclear Technology, 10,-211-214' (1971-).

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

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

g ,

Trans. Am. ' Nucl . Soc. , ,14,123 - (1971 ) . .

76. G.D. Bouche'y,.E. Linn Draper, Jr. , and .S'.'J. Gage, " Neutron Radiography

+ with'Cf-252: The Effect_of Tailoring Neutron Energy-Spectra on Photogrpahic Images", Neutron Sources- and Appifcations, CONF-210402,' Vol . 3,' Proc. ANS Topical Meeting, Augusta, Georgia, April 21, 1971.

oy ,

' 49 E ^

I 77. G.D. Atkinson, Jr. .

J.B. Whitworth, and S.J. Gage, " Computer-Assisted Analysis of Gama-Ray. Spectra", Computer Physics Communications, L 40-46 (1971).

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

~

tions, San Antonio, Texas (1971).

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

8D. '.G.D. Bouchey, "The Optimization of Nuclear Systems", Ph.D. Dissertation,

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

81. J.B. Whitworth', "The Development and Application of a Systematic Approach

. to Elemental Analysis in Forensic Investigations", Ph.D. Dissertation, The University of Texas, 223 pp. , December 1971.

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

83. E. Linn Draper, Jr., Mary Elizabeth Foster and G.D. Bouchey, "X-Ray Fluroescence Analysis and Neutron Activation Analysis in.an Analytical Chemistry.

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

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

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

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

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

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

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

88. C.E. Brauer, " Thermal Neutron Radiography with a Lithium-Lead Collimator- ~

Filter", Masters Thesis, Mechanical Engineering Department, The University of Texas, 64 pp., May 1972.

50

k 1

-,i* .

" I

' ^'g

. t i

d

. . 189.c~J.L.!Macdonald, " Heuristic. Learning' Control for Nuclear Reactors", Masters

~

. Thesis. MechanicalLEngineering Department, The University of Texas' 131 pp.

= August 1972.

r L90. J. Freim,T" Theoretical'and Experimental Evaluation of Nuclear Data and Calculation *echniques for Fusion Reactor Blanket Design",'Ph.D. Dissertation,

The-University 1of Texas, 210'pp., December 1972. .

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

92.. D.G. Anderson, " Fission Product Mass-Yi. eld . Measurements from Intemediate

-Energy Neutron Fission'of Plutonium-239 and Plutonium-241", Ph.D.' Dissertation.

The University of- Texas.125~ pp. , December 1972.

. 93. D.M. Williams, " Identification of Thermal Feedback Parameters for a -

TRIGA Mark I Reactor'.', Masters Thesis, Electrical Engineering Department.

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

a > .94. -G.D. "Atkinson, Jr. E. Linn Draper, Jr. , and G.D. Bouchey, "Subcrititcal' TRIGA Reactivity Measurements-Using.the Source Jerk Technique", TRIGA Owner's Conference.II,-College Station Texas (1972).

~

95. G.D. Atkinson, Jr., and E. Linn Draper,.Jr., " Transient Rod Failure in a 3 Pulsing JRIGA Mark I Reactor", TRIGA Owner's. Conference II, College Station,.

' Texas.(1972).'

96.. G.D. Atkinson, Jr., "A Safegu'ards Minicour'se", 18th Annual Meeting of

!? the American Nuclear Society, Las Vegas, Nevada (1972).

S7.. G.D. Atkinson, Jr., E. Linn Draper, Jr., G.D. Bouchey, and S.J. Gag ~e, .

F " Radioisotopic Source Amplification Using a Heterogeneous Suberitical Assembly",

)L Proc.18th Annual Meeting of the American Nuclear Society, Las= Vegas, Nevada-c' (1972),

f 98. E.. Linn Draper,' Jr., and G.D. Atkinson, Jr. , " Transient Rod Failure in a F'

Fulsing TRIGA Mark I Reactor", published in proceedings of 2nd TRIGA:0wner's

. Conference, February 1972. ,

~

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

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

lho. E. .Linn Draper, Jr., et.al., " Standard for the Development of Technical

. Specifications for Research Reactors",.Trans. Am. Nucl. Soc.i'(1972).

, 101;. E. Linn Draper, Jr., G.D. Atki_nson, Jr. , and B.B. Tomlin, "A Radiography _-

L* -and Capture Gamma: Ray Facility for Californium-252" Proceedings of the American

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

" September 11-13 1972. ,

p '

51 3

s.

=

s ,

b u;,

?

-102. E.L Linn~ Draper, Jr. .- G.D. Bouchey, G.D.T Atkirison, 'Jr. , .and S.J. ~ Gage, "A Versatile Subcritical Assembly for Undergraduate Nuclear Engineering

Instruction",= Proceedings'of the American Nuclear Society " Applications of

- Californium-252": National Topical, Meeting, September 11-13, 1972.

, .103. E. Linn1 Draper, Jr., and S.J. Gage, "The Fusion-Fission Breeder: -Its

, Potential,in a Fuel Starved Thermal-Reactor. Economy", 93rd Annual. Meeting of ithe' ASME, New: York, New York-(1972).

& , .104. E. Linn Draper, Jr., " Technological Innovation and Assessn.ent: A Novel

' Course for Nuclear Engineering", Winter Meeting of the American. Nuclear-Society, November 12-16 -1972.

105. D.T. Hall, E. Linn Draper, Jr. , and' P.S. ISchmidt, " Management of.the Transition to Nuclear Power Generation", Technical Report ESL-3, Energy Systems

"~  : Laboratories, College of Engineering, The University of-Texas at Austin,

.z..

,f December.1972.-

106. . P.S. Schmidt and G.G. Park " Heat Dissipation in a Power y1 ant Cooling Bay",LASME, Paper No. 72-WA/HT-61, November 1972.

1. ^

107. P.S. Schmidt and G.P. D' Arch, " Entry R'egion Effects on Flow and Pressure i

. Dropof-Lithium in Fusion Reactor Blankets", Proceedings of the Texas Symposium on-Technology of Controlled Thermonuclear Fusion Experiments and Engineering l Aspects!of Fusion. Reactors, Austin, Texas (November 20-22, 1972).

108. E. .Linn Draper, Jr., Charles Brauer, " Lithium-Lead Collimator Fabrication

. for1 Radioisotopic Source Neutron Radiography," Trans. Am. Nucl . Soc. . .Vol.15:1, p.142-143,(1972).

( -109. E. Linn' Draper, Jr. , James B. Freim, " Theoretical and Experimental Eval-uation of Nuclear Data and Calculation Techniques for . Fusion . Reactor Blanket *

"o . Design",' Texas Symposium on the Technology of Controlled Thermonuclear Fusion Experiments and the Engineering Aspects'of Fusion Reactors, November 20-22,

~1972.

110. . E.: Linn Draper, Jr., " Status of CTR Related Integral Experiments" pre-sented at the conference on." Nuclear Data.and Neutronics of CTR Blankets" held

-in ~ Seattle, Washington, September 19-21, 1972.

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

(1972) . .

- 112. . E. Linn Draper, Jr., S.J. Gage. "The. Fusion-Fission Breeder: Its Potential in'a Fuel Starved Thermal Reactor Economy", presented at the Texas Symposium on the Technology of Controlled Thermonuclear Fusion' Experiments and the-Engineering Aspects of' Fusion Reactors', November 20.-22, 1972.

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

52 L

p

[ L 4

y' fg y~ !114. - G.D. Atkinson,. Jr., S.J. Gage, 'G.D. Bouchey, " Cyclic Activation with

" , a Californium-252 Source", Nuclear Technology (1972).-

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

211'6. _T.L.-Bauer, G.D.cAtkinson, J'r., " Discrimination Between Plutonium and- ~

' Uranium by Gannia Ray Analysis Following Cf-252 Interrogation", National Topical Meeting on the Applications of Californium-252, Austin, Texas (1972).

Il7.; EElinn Draper, Jr., Editor, Proceedings' of Texas Sym)osium on the Tech-nology of Controlled Thermonuclear Fusion Ex)eriments and tie Engineering

. Aspects of Fusion Reactors, published by USA EC. 1118.. E.:Linn-Draper, Jr., Editor, Proceedings ~of the Implications of Nuclear

, Power in Texas, published.by the. Texas Atomic Energy Research Foundation.

119. E.=Linn Draper, Jr., J.R. Deen, J.J. Chromik, " Measurement of the Integral

' Fission Cross Section of Th-232 in a Cf-252 Fission Neutron. Spectrum,"

'Trans'. Am. Nucl. Soc. (1973)..

t

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

121; .E.'Linn Draper, Jr., and James B.-Freim, " Experimental Determination of the Fusion Spectrum in Graphite", Trans. Am. Nucl . Soc. , ~ 16,' 9, (1973).

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

. .16,6 16:(1973).

~ .

[ -l'23.= E. Linn Draper, Jr. , Theodore A. Parish, and Brian J. McArdle. "A Neu-tronic-Photonic Comparison of. Vanadium and Niobium Containing Fusion Reactor

' Blankets", Trans. Am. Nucl . Soc. , (November 1973).

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

~

.-Techniques for Fusion Development Analysis", Trans. ' Am. Nucl . Soc., (November 4

1973).

?l25. Theodore A. Parish and E. Linn Draper, Jr.. "Neutronic and Photonic Analyses of. Fusion Reactor Blankets-Containing Thorium," Fifth Symposium 'on Engineering

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

N~ ~

126. .C.E. Locke and D.R. Paul, " Graft' Copolymer Modification of Poly-

h. ethylene-Polystyrene Blends. 'I. Graft -Preparation and Characterization".

Journal of Applied Polymer Science, Vol. 17,, pp. 2597-2617 (1973.)

L I' 53 i4 .

[ 127. C.E. Locke and D.R. Paul, " Graft Copolymer Modification of Poly-ethylene-Polystyrene Blends. II. Properties of Modified Blends", Journal of

,b; Applied Polymer Science, Vol . l_7,,

7 pp. 2791-3800 (1973).

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

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

130. "M.E. Senglaub, " Cross Section Studies Based on the Statistical Model",

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

131. E. Linn Draper, Jr. , M.J. Voltin, Jr. , J.L. Macdonald, C.T. Rombough, L.D..Hansborough, S.G. Barbee, and J.H. Vanston, Jr., "A University's In-

.. volvement in Municipal Decision-Making on Nuclear Power", Trans. Am. Nucl.

Soc.,(1973).

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

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

Nucl. Soc., (1973).

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

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

134. G.D. Atkinson, Jr., " Applications of Neutron Activation Analysis to the Life Sciences", presented at the Combined Meeting of the. Texas Association for Radiation Research and South Central Photobiology Group, San Marcos, Texas, November 9-10, 1973.

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

January 1974.

136. T.A. Parish, "Neutornic and Photonic Analyses of Simulated Fusion Reactor Blankets Containing Thorium and Natural Uranium", Ph.D. Dissertation The University of Texas at Austin, 329 pp. January 1974, 137. J.H. Vanston, Jr., "Use of the Partitive Analytical Forecasting (PAF)

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

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

54

p g

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

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

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

CONF-740402, USAEC, (April 1974).

.141. E. Linn Draper, Jr., and T.A. Parish, "Neutronic and Photonic Analyses of ,

Fusion ~ Reactor Blankets Containing Natural Uranium", CONF-740402,:USAEC, (April ~1974).

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

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

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

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

Soc.,(October 1974);

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

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

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

148. J.R. Deen, E. Linn Draper, Jr., " Measurement of the Fission Product

. Yields and the Energy Integral Fission Cross Section of Thorium-232 in a Cali-fornium-252 Fission-Neutron Spectrum",. Nuclear Technology, 25, 416 (1975).

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

' Accelerator for Fusion Reactor Blanket Design", Proceedings of the Third Small Accelerator Conference, USAEC, CONF-741021 -(1974).

150. R.G. Spangler, E. Linn Draper, Jr.. T.A. Parish, "14 MeV Cross Section Measurements of Threshold Reactions for Seven Metals", Trans. Am. Nucl. Soc.,

. 22,,818(November 1975).

4 55

( - -

l 151.- 'W.R.. Smith,'Jr., E. Linn Draper, Jr., " Measured and Calculated Fast.

Neutron Spectra in a Graphite Medium". Trans. Am. Nucl . Soc. , ~22, 800 4 . (November 1975). ~

e ~

• 152. .J.W. Da'vidson, E. Linn Draper, Jr., " Costs for Partitioning Strategies

- Involved in.High-Level Nuclear Waste Management", Trans. Am. Nucl . Soc., g, 348 (November 1975)..

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

. E,322(November 1975). , .

f 154. T.A.' Parish, J.W. Davidson, E. Linn Draper, Jr., " Transmutation of

- Fission Products in Fusion Reactor Blankets", Trans. Am. Nucl. Soc., 22

-.- ~ (November,1975).

155. T.A. Parish', J.'W. Davidson, E. Linn Draper, Jr., "The Effects of the D-T Fusion Neutron Energy Spectrum on High Energy Reaction Rates", submitted to the Sixth. Symposium on Engineering Problems of Fusion Research, San Diego, California (November 18-21,1975).

156. A'.H. Pradzynski, R.E. Henry, J.L.S. Stewart, " Determination of Selenium

.in Water on the ppb Level.by Coprecipitation and Energy Dispersive X-Ray Spectrometry", Radiochem. Radioanal. Letters, 21(5) 277-285 (1975).

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

et.al . ,

Texas Nuclear. Power Policies: A Study of Alternatives, Volume II:

The Universit Study No.1 (y of Texas at Austin Center for Energy Studies, Policy A 1975).

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

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

159. A.H. Pradzynski, R.E. Henry, J.L.S.-Stewart, " Nondestructive Determination of Toxic Elements in Toys", Proc. of 10th Symposium on Nondestructive Elements, San Antonio, Texas, 257-265 (April 23-25, 1975).  ;

160.. R.E. Henry, " Determination of ppb Levels of Selected Elements in Natural '

Water using Radiosiotope-Excited Energy Dispersive X-Ray Fluorescence Analysis", '

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

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

Technique to the United States Controlled Thermonuclear Research Effort,"

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

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

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

56

r

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

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

165. T. A. Parish, J. W. Davidson, and E. Linn Draper, Jr., "The Minimization of the Hazard Resulting from Transmutation of Fission Products," Transactions of the American Nuclear Society, 23,3 59, June 1976.

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

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

onic Perfor-167.

.manceT. ofA. Parish,Fusion Graphite J. W. Davidson and E. Linn Reactor Blankets Draper,Sr90 Containing Jr., "NeypW."

and Is Second

- ANS Topical Meeting on the Technology of Controlled Thermonuclear Fusion.

Richland, Washington, September 1976.

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

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

169. A. H. Pradzynski and J. R. Rhodes, " Development of Synthetic Standard Samples for Trace Analysis of Air Particulates," ASTM Sper.ial Technical Publication No'. 598, 1976, pp. 320-336, 170. A. H. Pradzynski, R. E. Henry and J. S. Stewart, " Determination of PPB Concentrations of Transition Metals by Radioisotope-Excited Energy-Dispersive X-Ray Spectrometry, Journal of Radioanalytical Chemistry, 3_2, 2 1976, p. 219-28.

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

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

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

1976, p. 119.

173. R. R. Gay, G. F. Brockett and R. T. Johnson, "Two-Phase Flow Measurement Techniques for Nuclear Safety Research," Two-Phase Flow and Heat Transfer

. Symposium-Workshop, Miami Beach, Florida (1976).

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

57

t

'.. 175. . Rodney R. Gay, " Reactor Hydrodynamics During the Reflood Phase of a Loss-  !

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

176. :D. E. Klein, S. R. Bull, and J. B. Miles, " Flow Visualization Around GCFR Fuel Rod Roughness Elements," Trans. Am. Nuclear Soc., 28, 8 June, 1978.

177. ' D. E. Klein, S. 'R. Bull, and J. B. Miles, " Pressure Drop for GCFR Fuel Rod Roughness Elements," Trans. Am. Nuclear Soc., 3_0, _0 November 1978.

- 178. E. M. B. Sorensen, R. E. Henry and R. Ramirez-Mitchell, " Time Dependent Localization of Arsenic in Subcellular Hepatocyte Fractions," J. of Pathology  ;

and Toxicology, Vol. 2, No. 4,.1979, pp. 1161-1171. l-

179. E. M. B. Sorensen, R. E. Henry, and R. Ramirez-Mitchell, " Arsenic Accumula-

, tion, Tissue Distribution,.Cytotoxity in Teleosts following Indirect Aqueous

. ' Exposure," Bulletin of Environmental Contamination and Toxicology, Vol. 21, 1979, pp. 162-169.

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

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

- 33, November 1979.

l 182. S. A. Hodge, J. P. Sanders, and D. E. Klein, " Determination of Friction

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

183. D. E. Klein, " Nuclear Problems and Prospects," National Energy Policy.

- Issues, Council on Energy Resources, The University of Texas at Austin, May 1979.

184. D. E. Klein, H. H. Woodson, and J. W. Davidson, " Commercial Nuclear Power .

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

June 1979.

185. E. H. B. Sorensen, R. R. Mitchell, A. Pradzynski, T. Bauer and L. Graham, j "Morphometric Analyses of Arsenic-Induced Histopathological Changes in Parenchymal >1 Hepatocytes," Tennessee Academy of Science Annual Meeting, Nashville, TN, j i November 16-17, 1979.

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

Biota," Internal Report, Nuclear Engineering Teaching Laboratory, The University )

ofTexasatAustin,DepartmentofMechanicalEngineering(1979).

187. N. E. Hertel, B. W. Wehring, and J. J. Dorning, " Integral Test of i ENDF/B-IV High-Energy Neutron Cross Section Data for Tungsten," Trans. Am. l Nucl. Soc. 32, 631 (1979).

i 58 .

i i

L

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

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

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

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

Publication #594, pp. 568-571.

{

i 191. N. E. Hertel, B. W. Wehring, " Absolute Monitoring of DD and DT Nuetron Fluences Using the Associated-Particle Technique," Nucl. Instr. Meth.172, 501(1980).

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

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

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

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

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

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

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

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

198. J. E. Hamann, D. E. Klein, R. B. Pope, and H. R. Yoshimura, "Modelling of Pool Fire Environments Using Experimental Results of a Two-Hour Test of a Railcar/ Cask System, " Paper #147, PATRAM-80, West Berlin, FRG., Nov.1980.

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

200. J.W. Davidson and D. E. Klein (co-editors), Proceedings of the International Conference on Nuclear Waste Transmutation, University of Texas Press, March 1981.

59

201. M. A. Ross and D. E. Klein, " Synthetic Fuel Production Using Texas

, Lignite and a VHTR for Process Heat," Number 3, March 1982, Nuclear Technology, Vol. 56.

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

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

204. M. M. Razzaque, J. R. Howell and D. E. Klein, " Finite Element Solution of Heat Transfer for Gas Flow Through a Tube," AIAA Journal, Vol. 20, No. 7 July 1902.

. 205. S. Yang, J. R. Howell and D.E. Klein, " Radiative Heat Transfer Through a Random 1v Packed Bed of Spheres by the Monte Carlo Method," AIAA/ASMI 3rd Joint Thermophysics, Fluids, Plasma & Heat Transfer Conference, ASME 82-HT-5,

. St. Louis, Missouri, June 1982.

206. D.E. Klein and J. Andersen et al., " Peer Review of the Preliminary Design and Program Interfaces for the Transuranic Waste Package Transporter (TRUPACT)," Sandia Report, SAND 81-240 E Juiie 1982.

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

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

209. T. L. Sanders and D. E. Klein, " Comparison Analysis 'of Severe Flow Blockages for Computational Efficiency Using COBRA " Proceedines from Gas-Cooled Reactors Today Conference, British Nuclear Energy Society, London, England, September 1982.

210. M. M. Razzaque, J. R. Howell and D. E. Klein, " Finite Element Solution 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, 211. J. B. Smathers, N. E. Hertel, R. G. Graves, "In Phantom Photon Spectra Measurements for High-Energy lieutron Therapy Sources," Proceedings: Fourth Symposium on fleutron Dosimetry: Beam Dosimetry,1-5 June 1981, Neuberberg/Munchen, Federal Republic of Gemany, EUR 7448en (1981).

, 212. N.E. Hertel, B. W. Wehring and J. J. Dorning, " Measurements and Analyses of High-Energy Neutron Transport Through Tungsten," (accepted for publication subject to revision in Nuclear Science and Engineering, November 1981).

60

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

Nucl. Soc., H , 1976, June 1982.

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

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

Trans. Am. Nucl. Soc., M , 625. November 1982.

216. J. W. Davidson and N. E. Hertei, "Bonner Ball Detection Responses for Neutrons from Thennal Energies to 17.3 MeV," Health Physics Society Annual Meeting, Baltimore, Maryland.

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

218. N. E. Hertel, J. W. Davidson, and R. M. Laucius, "An NE-213 Response Matrix to~ 50 MeV," Trans. Am. Nucl. Soc. , .4_5, 607 (1983).

219 J. W. Davidson and N. E. Hertel, "An Equal Probability Neutron Detection l System Using Bonner Spheres," Trans. Am. Nucl. Soc. , g, 609 (1983).

220. D. E. Klein, " Coupled Radiative and Conductive Heat Transfer in a Two Dimensional Rectangular Enclosure with Gray Participating Media Using Finite Elements," ASME/JSME Thermal Engineering Joint Conference, ASME-H-35 Honolulu, Hawaii, March 1983, i 221. S. Yang, J. R. Howell, D. E. Klein, " Radiative Heat Transfer Through a Randomly Packed Bed of S heres by the Monte Carlo Method," (submitted to the Journal of Heat Transfer .

. 222. M. M. Razzaque, J. R. Howell, D. E. Klein, " Finite Element Solution of Radiative Heat Transfer in a Two Dimensional Rectangular Enclosure with Gray Participating Media," (submitted to Journal of Heat Transfer).

~

223. M. M. Razzaque, J. R. Howell, D. E. Klein, " Coupled Radiative and Con-ductive Heat Transfer in a Two Dimensional Rectangular Enclosure with Gray Participating Media Using Finite Elements," (submitted to Journal of Heat Transfer).

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

Hepatocyte changes following selenium accumulation in a freshwater teleost.

The American Journal of Forensic Medicine and Pathology 3(3) 8p., 1982.

l 225. Sorensen, E. M. B., and T. L. Bauer. Selenium-induced Condition Factor )

, and Organ Weight Changes in Naturally-exposed Redcar Sunfish. (Submittedto Toxicology).

61

• 226. Sorensen, E.M.B., T.L. Bauer, J.S. Bell, and C.W. Harlan, " Selenium Accumulation and Cytotoxicity in Teleosts Following Chronic, Environmental Exposure," (accepted by Bulletin of Environmental Contamination and Toxicology).

227. Sorensen, E.M.B. and T.L. Bauer, " Selenium Induced Hematological Dyscrasia in Teleosts," (accepted by Archives Environmental Contamination and Toxicology).

228. Sorensen, E.M.B. , P.M. Cumbie, T.L. Bauer, J.S. Bell, and C.W. Harlan,

" Histopathological, Hematological, and Other Changes Associated with Selenium Accumulation in Fish from Belews Lake, North Carolina," (ready for submission to Archives Environmental Contamination and Toxicology).

229. Sorensen, E.M.B., R.R. Mitchell, A. Pradzynski, T.L. Bauer, and L. Graham, "Sterological Analyses of Hepatocyte Changes Parallel Arsenic Accumulation in the Livers of Green Sunfish," (accepted by The Journal of Environmental Pathology,

. Toxicology, and Oncology).

230. Hertel, N.E. and J.W. Davidson, "The Effect of Cadmium Covers on Bonner

- Sphere Responses," to appear in the Proceeding of the Personnel Radiation Dosimetry Symposium, Knoxville, Tennessee October,1984, 231. Hertel, N.E. and J.W. Davidson, "The Response of Bonner Spheres from Thermal i Energies to 17.3 MeV "(accepted for publication Nuclear Instruments and Methods A, Februa ry, 1985) .

232. Patterson-Hine, A. , J.W. Davidson, and D.E. Klein, " Characterization of Product Buildup in Continuously Processed Molten Salt Fusion Breeder Blankets," Trans.

American Nuclear Soc. , 45, San Francisco, California, Oct. 30-Nov. 3,1983.

233. Patterson-Hine, A. , 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, Pennsylvania December 5-9, 1983.

234. Polansky, G.F. , J.P. Lamb, and D.E. Klein, "A Finite Element Analysis of Incompressible Laminar and Turbulent Flow with Heat Transfer," 5th International Symposium on Finite Elements and Flow Problems, The University of Texas at Austin, Austin, Texas, Jan. 23-26, 1984.

235. Ally, M., D.E. Klein, and T.L. Bauer, "Preconcentration Methods of Trace Elements in Water for EDXRF and INAA." Sth International Conference on Nuclear Methods in Environmental and Energy Research, Mayaguez, Puerto Rico, April 2-6, 1984, 236. Klein, D.E. and W.H. Miller, " Student ANS Branch Involvement in Public Information," Trans. Am. Nuclear Society, June 1984 - invited paper.

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

62

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

'- 239. Iskander, F.Y. and R.H. Filby, "Speciation of Titanium in Solvent Refined Coal using SESC-INAA " Proceeding of American Nuclear Society Meeting,

! Fifth International Conference, Mayaguez, Puerto Rico April 2-6, 1984.

240. Iskander. F.Y., " Neutron Activation Analysis of an Egyptian Cigarette and its Ash," J. Radioanal. Nucl. Chem. 89,511(1985).

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

Nuc. Chem. 91, 1 (1985).

242. Iskander, F.Y., " Cigarette Ash as Source of Environmental Pollution,"

• Environ. Pollut. (accepted).

243. Iskander, F.Y., T.L. Bauer, and D.E. Klein, " Determination of Trace Elements in American Cigarette Paper by Neutron Activation Analysis," (submitted to Beitr. Tobakforsch. Int.).

244. Iskander, F.Y., " Egyptian and Foreign Cigarettes. 2. Determination of Trace Elements in Tobacco, Ash and Wrapping Paper," (submitted to J. Radioanal.

Nucl. Chem.).

245. Iskander, F.Y., T.L. Bauer and D.E. Klein, "Detennination of 28 Elements in American Cigarette Tobacco by Neutron Activation Analysis," (submitted to Analyst).

246. Iskander, F.Y., D.E. Klein and T.L. Bauer, " Determination of Trace Impurities in Aspirin Tablets by Neutron Activation Analysis," (submitted to J. Radioanal. Nucl. Chem.). .

, 247. Jacobs, F.S. and F.Y. Iskander, " Vanadium Sorption by Crude Oils," (sub-mittedtoFuel).

, 248. Iskander, F.Y. and M.M. Morad, "Multielement Analysis of Hard Red Winter Wheat and Its Bran," (submitted to J. Food Science).

249. Morad, M,M;, F.Y. Iskander and. L.W. Rooney, "Physico-chemical Properties of Alkali-cooked Corn using Traditional and Pre-soaking Procedures," (submitted ,

toCerealChem.).

i4 63

. . _ _ _ - - - - _ _ _ _ _ _ _ _ - - - _ - _ _ _ _ _ _ _ - _ _ _ - _ - - _ _ _ _ _ _ _ _ .___ _ - _ . _ - _ _ _ _ _ .