ORNL-TM-2743 by Jon Morrow

HOME HELP OAK RIDGE NATIONAL LABORATORY operated by

UNION CARBIDE CORPORATION NUCLEAR DIVISION

for the

U.S. ATOMIC ENERGY COMMISSION

ORNL- TM- 2743

THIS DOCUMENT CONFfRMEDAs UNCLASSIFIED DlV& OF CLASSiFICATlON

COPY NO.

DATE

- December

22, 1969

DESIGN AND CONSTRUCTION of CORE IRRADIATION-SPECDEN ARRAY FOR MSRE RUNS

19 and

C. H. Gabbard

Abstract

’

A new MSRE c o r e specimen a r r a y w a s designed and f a b r i c a t e d t o r e p l a c e t h e t y p e of m e t a l l u r g i c a l s u r v e i l l a n c e specimen a r r a y t h a t w a s used i n t h e MSRE through Run 18. The main purpose of t h e new a r r a y i s t o measure t h e capture-to-absorption r a t i o of 23% and t o determine t h e e f f e c t s of s a l t v e l o c i t y , turbulence, and s u r f a c e f i n i s h on t h e d e p o s i t i o n of f i s s i o n products on g r a p h i t e and on Hastelloy-N. Two a d d i t i o n a l t e s t specimens were included, one of p y r o l y t i c g r a p h i t e t o determine i f t h e r e i s permeation of f u e l s a l t o r i t s c o n s t i t u e n t s i n t o t h e g r a p h i t e and one of Hastelloy-N t o expose a s e r i e s of e l e c t r o n microscope s c r e e n s i n a t r a p p e d gas pocket.

The new specimen a r r a y was i n s t a l l e d on J u l y 31, 1969 and w a s exi n t h e r e a c t o r c o r e for 12,943 M w h r s of r e a c t o r o p e r a t i o n during Runs 19 and 20.

poses

Keywords:

MSRE, core-irradiation-specimens, design, f a b r i c a t i o n , uranium-233, capture-to-absorption r a t i o , cross s e c t i o n s , f i s s i o n products, adsorption, nickel-molybdenum-chromium alloy, graphite. HOTlCE This document contains information of a preliminory nature and was prepared prirnorily for internal use a t the Oak Ridge National Laboratory. It i s subject to revision or correction and therefore does not represent a final report.

p *$9 I’* ..-, uj-

,“J

DBTlUBUTION OF THIS DOCUhlEST IS UNLIMITED \

FECAL NOTICE T h i s report was prepared as an occount o f Government sponsored work.

Neither the United States,

nor the Commission, nar any persan acting an behalf of the Commission:

Makes ony warranty or representation, expressed or implied, w i t h respect t a the accuracy, completoness, or usefulness of the information contained in t h i s repart, or that the use of any information, apparatus, method, or process disclosed in ?his report moy not infringe privately owned rights; or

6. Assumes any l i a b i l i t i e s with respect ?a tho use of, or for damages resulting (ram the use of ony information, apparatus, method. or process disclosed in t h i s report. As used in the above, â&#x20AC;&#x2DC;â&#x20AC;&#x2DC;person acting on behalf of the Commissionâ&#x20AC;?

includes any employee ar

contractor of the Commission, or employee of such contractor, to the extent that such employee

or contractor of the Commission,

employeo of such contractor propares, disseminator,

provides access to, any information pursuant t o h i s employment or contract w i t h the Commission,

or h i s omployment w i t h such contractor.

CONTENTS

......... 5 ........ 6 Description and Design of Test Specimens . . . . . . . . . . . . . 8 F l o w T u b e . , . . . . . . . . . . . . . . . . ........ 8 Uranium Capsules. . . . . . . . . . . . . . . . . . . . . . . 10

Introduction..............,... Mechanical Design of t h e Cage and Basket Assembly.

Pyrolytic Graphite. Graphite Tube with

..................... Turbulence Wire... . . . . . . . . . . . .

14 14 18 18

............ Gas Trap and Electron Microscope Screen Holder. . . . . . . . Disposition of the Specimen Array . . . . . . . . . . . . . . 21 Acknowledgements . . . . . . . . . . . . . . . . . . . . . . . . . 22 Hastelloy-N Tube w i t h TurbuZence Wire

DIS~IFIUTIONOF THIS DOCUMENT IS UNLIMITED n

5 Introduction

During nuclear operation of the MSRE through May 1969, t h e graphite sampler assembly contained samples of graphite and Hastelloy-N which were used t o determine t h e e f f e c t s of the r e a c t o r environment on these materials, including corrosion and the e f f e c t s of i r r a d i a t i o n on the physical propert i e s and t o determine the deposition of f i s s i o n products on t h e materials.’ Assemblies of t h i s type were removed i n July 1966, May 1967, April 1968, and June 1969.

After the l a t t e r removal, the same type of a r r a y w a s not

r e i n s t a l l e d because the r e l a t i v e l y s h o r t exposure t h a t would occur before t h e planned f i n a l shutdown of the MSRE would add l i t t l e t o t h e information obtained during the previous long exposures. assembly was designed t o u t i l i z e

Instead, a d i f f e r e n t sample

he e x i s t i n g space i n the core.

This new

assembly i s described i n t h i s report. The new assembly contained several experiments f o r f i s s i o n product 9

deposition studies and four graphite capsules containing uranium isotopes f o r measuring nuclear properties of contained about 1-gr t o t a l of about 1-gr t o t a l of

23%

and

23%

238v.

233v. Two of t h e uranium and “38v and the other two

capsules contained

The other specimens of graphite and

Hastelloy-N were designed t o study t h e e f f e c t s of flow, surface f i n i s h , and turbulence on the f i s s i o n product deposition.

A specimen of pyrolytic

graphite was included f o r s a l t permeation s t u d i e s and the f i n a l specimen formed a gas t r a p where electron microscope screens were exposed t o d e t e c t the presence of c o l l o i d a l m a t e r i a l s . The design d e t a i l s of t h e individual specimens and of t h e assembly a r e shown on ORNL Drawings M-10551-RB-001, M-10551-RB-002, and M-10551(Footnote-2)

The new specimen a r r a y

i n s t a l l e d i n t o the MSRE core on July 31,

1969 and was exposed during Runs 19 and 20. posure h i s t o r y of t h e array.

Table I summarizes the ex-

he specimen a r r a y w a s scheduled f o r removal

about December 15, 1969. d

’MSR Program Semiannu

ogress Report, August 31, 1965, ORNL-3872,

P. 87.

?Chese drawings a r e available i n Reactor Division, Design Department o r Laboratory Records.

. .

Table I

Exposure History of t h e MSRE Core Irradiation-Specimen Array f o r Runs 19 and 20

Time above $WOOF

Time exposed t o f l u s h s a l t

Time exposed t o f u e l salt Integrated Power

2,815 hrs 120 hrs 2,262 hrs 12,943 Mwhrs

Mechanical DesiRn of the CaRe and Basket Assembly I n order t o keep the assembly as simple as possible, each capsule o r specimen was made c y l i n d r i c a l w i t h an outside diameter of 1-1/4 Inches.

This was the l a r g e s t diameter that could be held i n a removable cage inside the e x i s t i n g basket design. The individual experiments within t h e assembly a r e more completely described l a t e r i n t h e report. Figure 1 shows the completed cage and basket assemblies. The new basket assembly is generally the same s i z e and shape as the previous ones, but is made from 2-in. OD by 0.062-in. w a l l Hastelloy-N tubing ( c o n t r o l rod thimble material) because the perforated sheet used previously was not available,

The l a r g e s l o t s i n t h e lower p a r t of the basket assembly were

t o reduce the m e t a l volume and t h e neutron flu depression t o a minimum i n t h e v i c i n i t y of t h e uranium-containing capsules.

The smaller s l o t s a t

the t o p of the basket are t o ensure an adequate salt flow through t h e

upper portion of t h e basket. The cage assembly c o n s i s t s of t h r e e v e r t i c a l 3/16-in.-diameter

rods

held by end f i t t i n g s and w i t h spacer rings welded a t i n t e r v a l s along t h e 1

length.

The lower end f i t t i n g was welded t o t h e v e r t i c a l rods and forms

a flow passage which d i r e c t s about half of the s a l t flow from the i n l e t tube of t h e basket i n t o the center of t h e f i r s t t e s t specimen.

The t o p

. c

rii

c d

rl ai

. rl

end f i t t i n g , which was removable t o f a c i l i t a t e loading and unloading t h e

t e s t specimens, s l i p s over the three rods and was held i n place by 1/16-in.-dia.

wire c l i p s .

The bottom t e s t specimen was pinned t o t h e lower end f i t t i n g t o res i s t any pressure drop e f f e c t s .

The other specimens were loose i n t h e

cage and were f r e e t o expand and contract as necessary.

The t o t a l length

of t e s t specimens was adjusted during assembly by machining the length of

the t o p metal f i l l e r plug t o provide end clearance w i t h the cage assembly. A t operating temperature the end clearance increased t o about 0.42 in.

due t o d i f f e r e n t i a l thermal expansion.

The graphite specimens, which

would normally f l o a t i n salt, were held down by the weight of t h e t o p

m e t a l specimens and t h e f i l l e r plug. The assembly procedure of t h e cage i n t o t h e basket and the i n s t a l l a t i o n of t h e basket i n t o t h e r e a c t o r v e s s e l were t h e same a s f o r t h e previous graphite sampler assemblies. "he assembly of the cage and basket was s i m p l i f i e d by the use of a l l new parts.

However, a previously used 9all-I;ock

assembly" was used t o complete the basket assembly, and t h e r a d i a t i o n l e v e l

of t h i s part required the final pinning operation t o be completed i n a hot cell

The r a d i a t i o n f r o m the ball-lock assembly was s u f f i c i e n t l y low that t h e completed assembly could be c a r r i e d from t h e Hot C e l l t o t h e MSRE i n a pipe carrier with r e l a t i v e l y l i g h t shielding on one end.

An argon at-

mosphere was maintained on t h e uranium capsules and on the completed assembly as much of the time as possible.

The t o t a l exposure of t h e

uranium capsules t o atmosphere was about one hour o r l e s s . Description and Design of Test Specimens

Flow Tube The first t e s t specimen a t t h e bottom of t h e assembly is t h e flow tube.

Figure 2 i s a photograph of the p a r t s and the completed assembly of L

t h i s specimen.

The metal core inside the graphite body formed a 1/16-in.

t h i c k flow annulus so a d i r e c t comparison between t h e deposition on Hastelloy-N and on graphite w i l l be possible.

The s a l t flow through the

Fig. 2.

Flow Tube Assembly

10 -

annulus was introduced through the lower end f i t t i n g of the cage assembly

id 5

and was driven by the pressure drop across the graphite l a t t i c e - b a r g r i d a t t h e bottom of the reactor vessel.

The salt velocity through the

1/16-in. annulus was estimated t o be 2.5 f t / s e c as compared t o 0.8 f t / s e c on the outside of the specimen.

The e f f e c t of s a l t velocity on deposition

can be obtained by c,omparing inside and outside surfaces of t h e graphite. Different surface f i n i s h e s were used on both the i n t e r n a l and t h e external surfaces so t h a t t h e e f f e c t of surface f i n i s h can be determined.

The

external surfaces w i l l a l s o be used as a reference f o r t h e graphite specimen with the turbulence wire.

The graphite parts were made of POCO grade

AXF-5Q. This grade of graphite was selected because of i t s uniform pore s i z e . Grade CGB graphite, such as c o n s t i t u t e s t h e MSRE core, was not used f o r t h i s specimen because t h e pieces of t h i s graphite s t i l l i n stock a l l had numerous cracks that would cause misleadingly high indications of apparent surface deposition.

Uranium Capsules The next section of the specimen assembly contains f o u r graphite capsules t h a t contain mixtures of uranium isotopes i n a NaF-ZrF4 c a r r i e r salt.

The purpose of these capsules i s t o determine, f o r the energy spec-

trum a t the capsules, t h e capture-to-absorption r a t i o of

23%

and t o de-

termine t h e absorption cross sections of the other uranium isotopes r e l a t i v e to

23%.

primarily

Two s i z e s of capsules were provided, the long capsules containing 23%

and

and t h e s h o r t capsules containing

23%

and

2%.

After exposure the s a l t mixtures w i l l be analyzed f o r uranium 233, 234, 235, 236, and 238 and f o r 239pU.

The production o r depletion of these

isotopes w i l l be obtained by comparison with similar analyses of unirradiated samples of the salt mixtures.

The isotopic concentrations of

uranium i n the o r i g i n a l s a l t mixtures as calculated from t h e analyses of the source materials a r e shown i n Table 11. The total weights of salt f o r the long and s h o r t capsules were 49.4

and 25.0 grsms respectively giving a t o t a l uranium content of 1 gram per capsule.

Since t h e analyses w i l l be done on t h e basis of isotopic r a t i o s

the exact quantity of salt o r uranium i s not important.

The NaF-ZrF4

Table I11

Calculated Isotopic Concentrations of O r i f f i n a l S a l t Mixtures (grams)

b n g Capsule

Short Capsule

0.4 ppm of U

0.03 ppm of U

233

0.1000

0.0081

234

0.0042

0 -0263

235

0.0084

0.0566

236 238

0.0004

0.0033 0.9056

u-232

o 8870

c a r r i e r s a l t was selected so t h a t any leakage of MSRE f u e l o r f l u s h s a l t i n t o the capsules could be detected by an analysis f o r lithium.

The heat generation r a t e s within the s a l t mixtures were estimated t o be 170 and 100 watts respectively f o r the long and s h o r t capsules. The t o t a l temperature ris

n t h e capsule was estimated a t about 30O0F,

b u t most of t h i s i s i n the salt mixture and i n t h e outside convective film. The high thermal conductivity limits the temperature gradients within the graphite so t h a t thermal s t r e s s e s a r e not a problem. Each capsule contains a s e r i e s of f l u x and tempe cated on the v e r t i c a l ce s t a i n l e s s - s t e e l wire and an indication of both t h

r e monitors lo-

The f l u x monitors

er-copper alloy.

These monitors w i l l give

1 and f a s t fluxes.

The temperature moni-

t o r s are small rods of S i c 1/2-in. long which s u s t a i n a dimensional change under i r r a d i a t i o n .

The i r r a d i a t i o n temperature is the temperature a t

which t h i s dimensional change can be annealed out. The design d e t a i l s of

capsules a r e shown on Drawing M-10551-FU3-002

. bj

(Reference 1) and i n Figure 3.

The annular s a l t cavity 3/4-in.-OD

1/2-in. ID reduced the centerline temperature of t h e capsule and a l s o ?Phis drawing i s available o r Laboratory Records.

i n Reactor Division, Design Department,

provided a convenient

t i o n f o r the f l u x

the c e n t r a l graphite core.

temperature monitors i n

POCO graphite grade AXF-5QBG was selected t o

avoid t h e neutron depression t h a t would occur w i t h Hastelloy-N and t o pro-

â&#x201A;Ź

vide a s a t i s f a c t o r i l y low s a l t permeability.

The capsules were sealed by

welding t h e ends of two molybdenum rings t h a t were each vacuum brazed t o the graphite body o r cap w i t h a 85Cu-lONi-5Cr brazing a l l o y a t l25O"C and

loe5 t o r r .

A d i r e c t braze between t h e graphite body and cap was not used

because of the high temperatures t h a t would have been required on t h e completed and s a l t - f i l l e d assembly. The i n t e g r i t y of the brazed j o i n t between the molybdenum rings and

graphite was t h e most important mechanical problem.

The metallographic

examination of t h e t e s t braze indicated t h a t t h e braze was s a t i s f a c t o r y , -

b u t t h e i n i t i a l production brazes leaked helium when subjected t o 10-psig pressure.

The brazing procedure w a s revised t o include coating the gra-

p h i t e surfaces w i t h C r $ 2 brazing a l l o y .

t o f a c i l i t a t e wetting of the graphite by t h e

Subsequent brazes were s a t i s f a c t o r y , b u t one cap was re-

j e c t e d because of a l a r g e pore i n t h e graphite.

Following t h e brazing operation, t h e capsules were leak-tested i n an alcohol bath with 10-psig helium.

Since the graphite i s porous t o helium,

t h e l e a k t e s t was used only t o screen out any p a r t s m i t h abnormally l a r g e pores o r any p a r t s with a poor braze.

The capsules were then cleaned i n

an untrasonic alcohol bath and vacuum-dried-at 300Â°C.

The f l u x and

temperature monitors, which had been previously cleaned, dried and assembled i n t o g l a s s tubes, were i n s t a l l e d and t h e capsules were delivered f o r s a l t filling

The s a l t mixtures were prepared and loaded i n t o t h e capsules by the

Chemical Technology Divisio

he s a l t was prepared i n one melt f o r each

of t h e two compositions. T f o r the indivi

It i n each melt w a s crushed and weighed

capsules.

The crushed s a l t was loaded

d then melted down

e r an argon atmos-

phere. wn of t h e s a l t was completed, t h e capsules

posed ends of t h e molybdenum rings. f

4d I

The

welding was done i n an argon atmosphere without t h e use of f i l l e r w i r e .

14 .-

The welds were inspected v i s u a l l y and by l i q u i d penetrant.

The completed

U 5

capsules and the excess s a l t mixtures contained i n small g l a s s jars were sealed i n p l a s t i c with an argon atmosphere u n t i l ready f o r use.

The o r i g i n a l plans were t o load the salt mixtures i n t o f o u r capsules

of each type, b u t one capsule of each type was r e j e c t e d during fabrication.

Two of each type were assembled i n t o the core specimen array and the t h i r d , along with t h e excess salt, is being held t o develop the s a l t recovery and a n a l y t i c a l procedures and t o provide the isotopic concentrations of the uni r r a d i a t e d salt.

Table I11 shows the monitor data and core location f o r each capsule. Pyrolytic Graphite A rectangular specimen of pyrolytic graphite as shown i n Figure 4

i s immediately above the uranium capsules.

0,687-in. x 6.0-in.

The t e s t specimen is 0.5-in.

long and is held i n t h e cage assembly by c i r c u l a r

pieces of POCO AXF-5Q graphite pinned t o each end. t h e graphite are p a r a l l e l t o t h e 0.687-in.

The l a y e r planes of

x 6-in. surfaces.

The depth of

any penetration of s a l t o r i t s constituents i n t o the graphite both p a r a l l e l and perpendicular t o the l a y e r planes, w i l l be determined by proton a c t i vation technique.

The specimen w i l l also be analyzed f o r the penetration

of f i s s i o n products both parallel and perpendicular t o t h e graphite l a y e r planes. The weight of t h e t e s t specimens above t h e pyrolytic graphite i s t r a n s f e r r e d from the outer diameter of the t o p end r i n g t o t h e c e n t r a l region by a 1/8-in, t h i c k Hastelloy-N disk. Graphite Tube with Turbulence Wire The next specimen i s a graphite tube machined from POCO AXF-5Q.

t e s t section is a l-in.-diameter

cylinder w i t h t h r e e 2-in.-long

with d i f f e r e n t surface f i n i s h e s (5, 25, and I25 RMS). i s 1/2-in. with surface f i n i s h bands of 5 and 125 RMS.

s e c t i o n has a c o i l of 1/16-in.

The

sections

The bore diameter The OD of t h e ' t e s t

Hastelloy-N wire wound on a 1/2-in, p i t c h

and w i t h a 20-mil radial clearance between the graphite surface and the wire.

The o r i g i n a l design c a l l e d f o r spacers between t h e wire and the

graphite, b u t these were eliminated because of welding problems with the t h i n spacers.

The wire c o i l i s t o promote turbulence on t h e outside sur-

face of t h e graphite.

Figure 5 is a photograph os t h i s t e s t specimen.

Table I11 Uranium Capsule Location and Monitor Data -~

Capsule U-Mixture

Location Weight (Top t o of S a l t Bottom)

Monitor Array (Top t o Bottom)

SS-302-1/4I'

(11/16" Ag-Cu

234-238 24.

Sic

. .

Holder)

sic

9.700 mg 9.382 mg

*50046"

2" .49992" 9.387 mg

.50050"

5/32" 5/32"

.4436 gm .4448 gm

s-1 s-2

s-3

Spacer

.50024"

SS-302-1/4" ( 11/161t Holder)

L-2

233-238 49.4

MSRE-4 9.505 mg

Spacer

SS-302-3/8" ( 11/16ii Sic

Spacer

Ag-Cu

Holder)

sic

1-1/1611.49998" 1-1/16t1 .4438 gm 16.046 mg .50025"

(Bottom)

L-3 L-4

233-238 49.4 233-238 49.4

9.581 mg MSRE-2 9.461 mg

Storage

1-1/1611.49992"1-1/16t1 .4435gm 15.604 mg .50046" 1-1./16~~ .49999" 1-1/16ii .4422 gm 15.321 mg .5001911

0.0804

u t

0 d

-P

18 The s a l t flow r a t e s on both the i n t e r n a l and e x t e r n a l surfaces a r e

LJ f

somewhat more uncertain than on t h e bottom flow-tube specimen because t h e pressure drop i s not well defined.

However, both the i n t e r n a l and ex-

t e r n a l v e l o c i t i e s should be about t h e same as outside the sample basket o r about 1 t o 2 f t / s e c . The quantity of fission-product deposition as a function of surface f i n i s h w i l l be determined f o r both t h e inside and outside surfaces.

The

e f f e c t of the turbulence wire w i l l be determined by comparison with the graphite flow tube a t the bottom of t h e assembly. Hastelloy-N Tube with Turbulence Wire T h i s t e s t specimen, shown i n Figure

6, i s a duplicate of the graphite

specimen j u s t described except t h a t it is constructed of Hastelloy-N. Both of these specimens w i l l be subjected t o about the same conditions and w i l l provide the same type of information. The e f f e c t of t h e turbulence wire w i l l be determined by comparison with t h e surface of the electron microscope screen holder. The double w a l l design of t h i s specimen, and t h e next one above, prevents contamination of t h e surface under study from t h e exposure of t h e opposite surface. The t e s t specimen w i l l be sawed i n t o individual rings f o r each surface f i n i s h and then each r i n g w i l l be dissolved f o r analysis. T h i s procedure eliminates t h e necessity f o r machining o f f t h e surface f o r

analysis. I

Gas Trap and Electron Microscope Screen Holder The l a s t t e s t specimen w i l l t r a p a sample of gas t h a t may be circul a t i n g i n the core and expose s e v e r a l e l e c t r o n microscope screens t o t h i s gas so t h a t any c o l l o i d a l o r p a r t i c u l a t e m a t e r i a l can be c o l l e c t e d and examined.

Figure 7 is a photograph of t h i s specimen with the c e n t r a l rod,

which holds t h e microscope screens, removed.

The d r i l l e d holes i n the

rod slope downward and w i l l t r a p s a l t so t h a t the maximum s a l t l e v e l during operation can be determined. The sealed cavity formed by the double w a l l was f i l l e d with helium t o improve the heat t r a n s f e r and t o reduce the temperature of t h e c e n t r a l rod t o about 100OF above the s a l t temperature.

k Q,

c Q, k 0

a rn

0 V

2 k a,

4J V

rl w

a r:

a a3 k

t 3

Disposition of t h e Specimen Array The specimen a r r a y was removed from the MSRE core on December 18,

1969 and delivered t o the hot c e l l on

the

19th. The assembly w a s f r e e

of s a l t and was i n good mechanical condition.

The individual specimens

were removed from t h e assembly on December 22, 1969. The detailed examination and analysis of t h e fission-product deposition specimens w i l l be directed and reported by S. S . Kirslis and the analysis and r e s u l t s of the uranium capsule experiments w i l l be directed and reported by G. L. Ragan.

ACKNOWLEDGMENTS The author i s indebted t o a l a r g e number of individuals whose cooperation and assistance was required t o complete t h e design, fabrication, and i n s t a l l a t i o n of the specimen array on t h e time schedule t h a t was available.

The following individuals i n p a r t i c u l a r contributed d i r e c t l y

t o the design and f a b r i c a t i o n of the assembly.

S. S. Kirslis: Conceptual design of fission-product deposition experiment and specimens. G. L. Ragan:

Formulation of the r a t i o experiment.

23%

capture-to-absorption \

Graphite t o molybdenum brazing and f i n a l s e a l welding of the uranium capsules.

W. J. Werner and coworkers:

J. C. Mailen and F. J. Smith: Preparation of t h e s a l t mixtures and f i l l i n g t h e uranium capsules. W. H. Cook:

Design and f a b r i c a t i o n of t h e pyrolytic graphite specimen and general assistance on the design and f a b r i c a t i o n of t h e o v e r a l l assembly.

H. G. Kern:

Scheduled and supervised the f a b r i c a t i o n of the p a r t s and assemblies through the various shops.

ORNL-TM-2743 I n t e r n a l Distribution 1. G. M. Adamson

J. L. Anderson 3. C. F. Baes 4. S. E. Beall 5. E. S. B e t t i s 6 . F. F. Blankenship 7. E. G. bhlmann 8. G. E. Boyd 9. R. B. Briggs 10 E. L. Compere 11 W. H. Cook 12-13 D. F. Cope (AEC) 14. W. B. C o t t r e l l 15 J. L. Crowley 16 F. L. Culler 17 S. J. D i t t o 18. W. P. Eatherly 19 J. R. Engel D. E. Ferguson 20 21. L. M. F e r r i s A. P. Fraas 22 23-27 C. H. Gabbard 28. G. Goldberg 29 W. R. Grimes 30 A. G. G r i n d e l l R. H. Guymon 32 R. W. Harvey 33. P. N. Haubenreich 34. P. R. Kennedy 35. R. J. Ked1 36. C. R. Kennedy 37. S. S. Kirslis 38. M. I. Lundin 2.

... .

'*.

.. 0

31.

39. 40.* 41. 42. 43. 44-45 46. 47 48 49 50 51 52. 53 54 55-56. 57 58 59 60. 61. 62. 63 64. 65 66. 67. 68. 69. 70. 71 72. 73.

. .

R. R. J. H. H. T. L.

N. U o n MacPherson Mailen McCoy McCurdy W. McIntosh (AEC) E. McNeese J. R. McWherter A. J. Miller R. L. Moore E. L. Nicholson A. M. Perry B. E. Prince G. L. Ragan M. Richardson M. W. Rosenthal A. W. Savolainen Dunlap S c o t t M. Shaw (AX) M. J. Skinner L. A. Smith, ORGDP F. J. Smith I. Spiewak D. A. Sundberg R. C. Steffy R. E. Thoma D. B. Trauger J. W. M. J. G.

E. C. E. C.

R. Weir J. Werner E. Whatley C. White

D. Whitman

Gale Young

Central Rese h Library (CRL) Y-12 Document Reference Section (DRS) Laboratory Records Department (LRD) 81. Laboratory Records Department - Record Copy (LRD-RC) 82. ORNL Patent Office External D i s t r i b u t i o n

74-75 76-27. 78-80

83-97. 98

Division of Technical Information Extens ion (IYTIE) Laboratory and University Division, OR0