LA-8735-PR

Progress Report

ClC-l 4 REPORT COLLECTION

REPRODUCTION

COPY

Space Nuclear Safety and Fuels Program

November 1980

.

L%?LOSALAMOS SCIENTIFIC LABORATORYPostOfficeBox 1663 LosAlamos,New Mexico87545

An Aff~mative Action/Equal opportunity Employer

The four most recent reports in this series, un-classified, are LA-8582-PR, LA-87 13-PR,LA-87 14-PR, and LA-87 15-PR.

.

This report was not edited by the TechnicalInformation staff.

This work was supported by the US Depart-

ment of Energy, Division of Space andTerrestrial Systems.

I)lSCLAIMI:R

This rqmt was prcpticd as m! account or work sponsored by m agency of the United S1’tcs Govern.mcnt. Ncilhcr the Umtcd St. tcs Covcr,~mcnt nor any agency thcrcc. f, nor any of thtk cn@oYccs.makes wry w’rranty, cxpres~ or mlplicd. or as$umcs any Icgai hbility or rcsponsibdit y for the accur.acy, complctcnes$, or useiulncss of any information, appar’t us, product, ot process disclosed, or tcP-

rcsenls that its use would not infringe priwtcly owned rghts. Reference herein to any spccill com-mercial product, process, or servtcc by trade name, trademark, manufacturer, or otherwise, dots notneceshty constitute or imply its cndorrement, recommendation, or favoring by the United Sta(csGovernment or any agency thcrcnf. The views and opinions of authors expressed herein do not nec-essarily state or reflect those of the Unilcd States Government or any agency thereof. u

UNITED STATESDEPARTMENT OF ENERGY !, .. . . .

‘ CONTRACT W-7405 -EfdG. 36!“ ,

:,

LA-8735-PRProgress Report

UC-23Issued: February 1981

Space Nuclear Safety and Fuels Program

November 1980

Compiledby

S.E.Bronisz

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

.,=,= ,

—

.

.

ABSTRACT

This formal monthly report covers the studies relatedto the use of 238Pu02 in radioisotopic power systemscarried out for the Space and Terrestrial SystemsDivision of the U. S. Department of Energy by the LosAlamos National Laboratory.

Most of the studies discussed here are of a continuingnature. Results and conclusions described may change asthe work continues. Published reference to the resultscited in this report should not be made without theexplicit permission of the person in charge of thework.

.

iv

,

v

SPACE NUCLEAR SAFETY AND FUELS PROGRAM

NOVEMBER 1980

Compiled byS. E. Bronisz

I. GENERAL-PURPOSE HEAT SOURCE

A. Impact Tests (F. W. Schonfeld)—The postrnc)rtem examinations of the four fueled clads imnacted in the

Design Verification Test (llVT)series were extended this month. Details of theDVT impacts were presented in the August, September, and October monthlyreports. Briefly, four General-Pll,rposeHeat Source (GPHS) modules of the LMRFdesign (CPJCFinsulation and end loading of the graphite impact shell (GIS))were impacted at 82f)°Cor 850°C at 58 mps at three orientations O°C (end-on),27°, and 9f1° (2 tests). The 0° and 27° tests resulted in deformation of thefueled iridium capsules , while both 90° tests resulted in severe, non-ductilecracking of the capsules. The observed cracking in the qOO orientation was dueto the design-specific stress state resulting from the effective void in theCBCF insulation volume.

1. Fuel analyses. The particle size distributions of the four fuelpelle= are given in Table I. The size range for IRG-88 is truncated becausethe fuel was not recovered quantitatively.

The spectrochemical analyses of three of the fuel pellets are listed inTable II. The small differences among the elemental contents have no obviousrelationship to the impact responses.

Typical mirostructures of the four fuel pellets are illustrated by thephotomicrographs shown in Fig. 1. Again, there are no extraordinaryvariations in the fuel that might explain the failure of IF?G-88 and the nearfailure of IRG-90. Analysis of the graphite components from IRG-88 revealedthat 3.5 mg of fuel had been released from the clad and trapped by thegraphite.

?. Iridium analyses. The spectrochemical analyses of samples of three ofthe i~dium clads are listed in Table III. Samples from each cup of the threecapsules in Table III were examined by Auger Electron spectroscopy. Thorium,carbon, and oxygen were detected in concentrations and distributions normal forthe IIOP-26 iridium alloy.

The analyses of the iridium provide no better reasons for the cracksobserved in IRG-88 and IRG-90 than do the fuel analyses. It seems quite likelythat the responses of IRG-88 and IRG-90 were related to the specific stressstate that exists in the 90° orientation and not to any mechanical or chemicaldifference among the components of the DVT modules. The main factor to beexplored is the importance of the following impact assembly to the deformationof the fueled clads in the leading impact assembly. The cracks in IRG-90occurred with very little prior strain, suggesting that the impact of theGPHS-LMRF module on its broad face might result in clad failures. This is

important, because the broad-face orientation is believed to be the most likelyand it puts all four fueled clads at risk.

R. Fine-l’leavePierced Fabric Shear Tests (R. Zocher, M. Stout)—The position of a GPt!S=lfithe heat-source stack is maintained bv

two lock members, which are placed in recesses in the broad face of th~aeroshell. The lock members are made of fine-weave pierced fabric (FNPF)graphite, as is the aeroshell, and are visible on the top of the module stackshown in Fig. 2. The FbJPFgraphite is known to have anisotropic properties,so we conducted a series of shear tests to obtain data on the effects of thatanisotropy in the shearing response of the

A precision fixture, shown in Fig.photograph in Fig. 4, was designed so thatsimultaneously.

The microstructure of the equator’tested are shown schematically in Fig. 5.were run at each of the orientations ~

ock member.3 as an exploded drawing and in thetwo lock members could be tested

al planes of the four orientationsFive tests of two lock members eacheuicted in the ficfure. In each

orientation the five tests replicated one another quite closely.-The stress-deflection curve for each of the orientations is shown in Fig.

6. The rotation of the X-Y plane about the Z-axis when the shearing directionis perpendicular to the Z-axis had a small effect. The samples with X and Ydirections at 45° ~~eresomewhat softer than when those directions were at ooand 90°, but the general shapes of the curves were similar.

The orientation of the Z-axis bundles when they were in the plane of shearhad quite a strong effect on the shape of the stress-deflection curves, as seenin Figs. 6C and 6d. Nhen the Z-bundles were parallel to the shearingdirection, the sample was stiffer and its deflection curve was monotonic to theultimate stress, whereas in the samples with the Z-bundles perpendicular to theshear direction the stress-deflection curve exhibited a pseudo-yield point, buthad a higher ultimate strength.

These shear tests are summarized in Table IV. The orientation of thelocking member about its axis will be random in use, because of the rotationalfreedom. If the FWPF is oriented so that its Z-bundles are parallel “to theaxis of the lock member, the rotational orientation will have much less of aneffect on the shearing properties than if the Z-bundles are perpendicular tothe lock member axis. Similarly, the parallel orientation displays stiffnessand early strength, whereas the perpendicular orientationbut later, strength.

results in higher,The selection of one orientation over the other would

depend on the amount of deflection that can be tolerated in the heat sourcestack and the actual strength requirements.

c. Fuel Development (R. Kent)——Los Alamos fuel pellet GP-19 was encapsulated in iridium’to form GPHS

fueled clad IRG-62, which will be used in the reentry simulation next month. Atotal of 37 Los Alamos-fabricated fuel pellets has been encapsulated.

The dimensions of seven Savannah River Laboratory (SRL) pellets receivedby Los Alamos for encapsulation and testing are given in Table V. Each of theSRL pellets had surface cracks like those visible in Fig. 7.

Los Alamos employees R. !lehrensand G. Melton visited the Savannah RiverPlant (SRP) to assist in the GPt{Sproduction startup.

2

II. SYSTEMS SUPPORT

.

‘4

A. Stirling Isotope Power System (D. Pavone)—The accumulated exposure time of the 800° test assembly was 25,678 h on

December 1, 1980.

B. Multi-hundred Watt (D. Pavone, C. Frantz)—The Multi-hundred Watt fuel sphere assembly (FSA] !IHFT-68was tested in a

simulation of the minimum-gamma reentry and impa;t”of the Galileo heat source.The sample was aged for 110 h at a surface temperature of 1210°C, subjected toa reentry heat pulse with a maximum iridium temperature of 1792°C and impactedat 81.7 mps and 1579°C. Radiographs taken after aging showed that the fuelsphere was broken and that the pieces were separated.

The impact of the sample occurred with the GIS cap oriented at 180° to theinitial impact point. The shell was delaminated, but the body was not split.

Photographs of the impacted sample with the graphite removed are shown inFig. 8. The iridium shell was oriented with its weld plane nearly parallel tothe target. No hoop fractures or tensile tears on the back side of the iridiumwere ohserved, nor were fingerprint cracks or fuel-fragment punch displacementsseen on the impact face. A gray, metallic deposit was observed adhering to theiridium exterior on the decontamination-cover weld bead. On exposure to airthis deposit oxidized to a yellowish-white material, which was identified byX-ray diffraction analysis as M003. The source of the molybdenum deposit isunknown.

The average diameter of the impacted sample was 43.66 mm, equivalent to adiametral strain of +7.4%, and the height of the impacted shell was 30.07 mm,indicating a height strain of -26.0%.

Analysis of the recovered graphite debris revealed a total plutoniumcontent of 47 ug and a phosphorous content equivalent to 82 ppm.

Metallographic examination of the microstructure of the iridium indicatedthat the weld microstructure was excellent, as shown in Fig. 9. The grainsize of one of the hemispheres of the iridium was nonuniform, varying from 5-12grains across the thickness, with the average being 8.8 grains/thickness. Themicrostructure shown in Fig. 10 illustrate the variation of grain sizeobserved for this hemisphere. The average grain size of the other hemispherewas 10.1 grains/thickness.

The appearance of flat grains of iridium on the interior surface of theiridium shell was noted, as was a slight amount of iridium transport. Thesefeatures are illustrated in Figs. 11 and 12.

Metallographic examination of samples of the plutonia sphere showed thatmaterial near the impact face was denser than that away from the surfaceregion, however, there was no evidence of deformation of individual grains thatwould suggest plastic deformation of the plutonia. Figure 13 showsmicrostructure of the plutonia sphere.

Chemical analysis of a sample of the plutonia sphere indicated aphosphorous content of 20 ppm. Spectrographic analysis indicated the followingelements to be present at levels exceeding the detection limits.

Si - 310 ppm Fe - 150 ppmZn - 25 ppm Cr - 25 ppmTa - 500 ppm Ni - 9 ppmCa - 7 ppm Ti - 15 ppmAl - 25 ppm Mo - 15 ppm

Mg - 300 ppm

3

III. LIGHT-WEIGHTRADIOISOTOPIC HEATER UNIT (R. Kent, R. Tate)

A. Specifications and Analyses—The .s~ecification Document. CMB-11-RDH-8f)-105. “The Sr)ecification for

Fabrication’ and Encapsulation of ~WfRHUPellets and Assembly of Heater Units,”has been written and submitted to llOE/STS for approval.

To date, we have hot pressed 7 lots of 16-each LMRHU pellets (112pellets). Each lot was fabricated, using constant fabrication parameters, fromthe same lot of SRP feed materialfabrication parameters

, nominally enriched at 83.5 at.% Pu-238. Theand sintered dimensions for these pellet lots are

summarized in Table VI. Two pellets from each lot were sampled for analyses.Spectrochemical data for the 7 pellet lots are summarized in Table VII.Isotopic chemical data for 5 of these lots are listed in Table VIII. Theisotopic data, combined with the weight data from Table VI, yielded acalculated thermal inventory of 1.11 watts per pellet on the delivery date,April 30, 1980. The specification is 1.1OA 0.03 watts.

No flight-quality hardware has been received. However, a number ofpellets have been encapsulated for testing at Los Alamos. The specificationfor decontamination of the welded capsules is 220 cpm (swipe). All capsuleswelded to date have been decontaminated to zero swipe.

The specified neutron emission rate for these pellets is 6000 n/s-g 238PU.

Two of the test pellets have been c ted and the average neutron emission rate~ 9!J8PUmeasured was 5200 ~ 50 n/ -g Finally, the specified leak rate for

welded capsules is 1 x 10-6 cm/ he ium:3J

All capsules welded for testing havehad leak rates less than 1 x 10- cm /s helium.

~ =imulant pellets were encapsulated in Pt-30 Rh hardware fortesting.

All welding procedures have been written, tested, and approved. The 45pellets for Hughes Aircraft will be encapsulated into the Pt-30 Rhflight-quality hardware when it is received at Los Alamos.

c. Safety—A presentation on the development of the LWRHU was made to the Interagency

Nuclear Safety Review Panel at the meeting to review the Galileo andSolar/Polar Preliminary Safety Analysis Report held in Germantown, MD, onNovember 19, 1980.

A

.

TABLE I

FRACTIONAL DISTRIBUTION OF PARTICLE SIZES OF IMPACTED FUELS

Size(mm)

+6

-6, +2

-2, + 0.841

-0.841, + 0.420

-0.420, +0.177

-0.177, +0.125

-1.125, + 0.074

-0.074, +0.044

-0.044, +0.030

-0.030, +0.020

-0.020, +0.010

-0.010

IRG-87SRGPHS - 25

0.728

0.173

0.045

0.017

0.009

0.002

0.004

0.005

0.006

0.003

0.005

0.003

IRG-88SRGPHS - 27

0.490

0.281

0.134

0.050

0.045

N.D.

II

II

II

II

II

11

IRG-89SRGPHS - 28

0.240

0.478

0.183

0.051

0.025

0.004

0.005

0.003

0.002

0.001

0.003

0.004

IRG-90SRGPHS - 29

0.529

0.334

0.097

0.023

0.009

0.001

0.002

0.001

0.0009

0.0005

0.0012

0.0013

[

5

LI

Be

B

Na

Mg

Al

SIK

Ca

Ti

vCr

Mn

Fe

co

Ni

Cu

Zn

Rb

Sr

Y

Zr

Nb

Mo

Ag

Cd

Sn

Ba

La

Hf

Ta

w

Re

Pb

Bi

TABLE II

SPECTROGRAPHIC ANALYSES OF

SRGPHS-25

1

<1

<1

2

50

140

400

<5

>750

15

<3

9

3

310

<3

6

<1

15

<11)

10

<25

<100

<10

5

50

<10

<5

15

c25

<25

100

<10

<25

<5

<1

IMPACTED FUELS

~RGPHS - 27*

1

<1

5

2

300

35

350

<5

750

10

<3

25

5

340

10

45

<1

50

<10

<5

<25

<100

<10

10

40

<10

<5

<2

<25

<25

500

<lo

<25

<5

<1

~GPHS - 2%

1

<1

4

<2

50

40

550

<5

~750

10

<3

20

2

270 -

<3

30

<1

15

<10

<5

<25

<100

<10

4

7

<10

<5

2

<25

<25

400

<lo

<25

<5

<1

*Additional ly, P was determined by a wet method tobe 20 ppn.

Li

Be

B

Na

Mg

Al

Si

P

K

Ca

Ti

v

Cr

Mn

Fe

co

Ni

Cu

Zn

Ga

Ge

Sr

Zr

Nb

MO

Ru

Rh

Pd

Ag

Cd

In

Sn

Sb

Ba

Hf

Ta

Au

T1

Pb

Bi

TABLE III

COMPOSITIONSOF IMPACTEDIr-O.3% W CAPSULES(SpECTRO. suRvEY)

-LiUaiL

<30

<3

<30

<300

5

60

10

<300

<1000

<3

<30

<30

30

<10

40

<10

10

25

~50

<30

<30

<3

<300

<300

<300

<30

<30

<20

<10

c100

<30

<50

<300

<3

<500

<1000

0.1-1%

Najor

<30

<10

<30

<30

<30

.LRk8A

<30

<3

<30

<100

15

40

30

<300

<2000

3

<30

<30

20

<10

20

<10

<20

3

<50

<30

<30

<3

<300

<300

<300

<30

<30

<20

<10

<100

<30

<50

<300

<3

<500

<1000

().1-1%

Major

<30

<10

<30

<30

<30

J.EG4Q

c30

<3

<30

c100

15

40

30

<300

<2000

3

<30

<30

10

<10

20

<10

<20

3

<50

<30

<30

<3

<300

<300

<300

<30

<30

<20

<10

<1oo

<30

<50

<300

<3

<500

<1000

0.1-1%

Major

<30

c1o

<30

<30

<30

.

6

TABLE IV

GPHS LOCK MEMBER COMBINEDa SHEAR TEST RESULTS

Ultimate Elastic Max. Elastic Eff. ElasticbTest Load Load, Load, Stress, Shear Mod.,*No. Direction N N MPa MPa/nm

1-5ZC XY 0° 5208 4270 14.46 65.4

6-1OZ XY 45° “ 5476 3999 13.53 55.1

11-15X z 0° 9008 3158 10.69 46.4d32.8e

16-20X z 90° 8202 5320 18.01 61.9

aFive tests averaged in each of four orientations.bThe effective modulus is the slope of the elastic portion of the stress-deflection curve.

CLetter denotes fiber direction 90° to shear direction.‘First elastic region.‘Second elastic region.

TABLE V

DIMENSIONS AND DISPOSITIONS FOR SRL GPHS PELLETS

SRL Pellets Ir-O.3 Capsules

Diam Length Weight Density WeightNo. (in.) (in.) (g) WQ_ No. J9J_

GPHS21 1.093 1.094 152.32 84.0 IRG-74 51.3

GPHS22 1.092 1.088 151.30 84.0 IRG-76 51.8

GPHS25

GPHS27

GPHS28

GPHS29

GPHS31

.087 1.085 149.29 83.9 IRG-87 52.0

.088 1.086 149.48 83.7 IRG-88 52.5

.089 1.087 149.43 82.7 IRG-89 52.4

.089 1.085 149.39 83.7 IRG-90 53.4

.083 1.082 149.28 84.7

7

TABLE V I

LASL RHU PELLET SUMMARY

<125-@ 2~BPu02 granules39) seasoned at 11OO”C(40 Wt%)

Feed Material (LAsL 10ts 38 and(60 wt%) and 1600”C

Hot Press Parameters

Post-Press Sintering

1530°C for 15 min at 19.5 MPa

6 h at 1000”C plus 6 h at 1527°C in Ar-H21G0

Comments 7 lots of 16 pellets each

Sintered Dimensions

Density(% TD)

87.9

88.2

87.8

86.7

86.2

87.5

87.3

87.4i 0.7

Diam(in)

0.246

Lenath(in)

0.365

Neiaht(Cl)

2.664

Lot

3

4

5

6

7

9

10

0.246 0.366 2.665

0.246 0.367 2.667

0.245 0.372 2.665

0.245 0.374 2.662

0.245 0.36’3 2.664

0.245

0.246~ooool”

0.369

0.369*0.003

2.661

2.664to,0(32

Specification 0.245*0.005

0.369f(3.oo7

2.664*().(3()5

SP!KEAl

B

Ca

Cr

Cu

Fe

Mq

Mn

Mo

Na

Ni

Pb

Si

Sn

Zn

TABLE VII

SPECTROCHEMICALDATAFOR RHU PELLETS(ppm by weight)

Limita

150

1

300

250

100

800

50

50

250

250

150

100

200

50

50

SensitivityLimit

5

1

3

5

1

5

1

1

20

2

5

5

5

5

5

Feed Powder

SR LASLAnalyses Analyses

60 78

1

60 130

97 100

7 15

262 270

15 10

8 10

< 50 8

8 2

45 60

< 10 10

78 165

< 10 5

< 20 18

LWRHUbPel1ets

147<c

44

138

<

274

196

7

3

3

22

<.

194

<

14

aThe s~ecification requires that iron and silicon shall not exceed theposted limits. Other cation impurities that exceed the limits shallbe reported in the summary data package.

bAverage for 7 pellet lots.

cBelow sensitivity limit, not detected in these samples.

9

C-3

o0~o+

1

m*.

ma

moG+1

o0o“+1

.0

!-4HH>

..

..

.3C

O*FO

0tY

cnl-

,

mo-l.

N-.

0

u)

*G

10

.

./

(a) (b)

(c) (d)

Fig. 1.The microstructure of the impacted DVT fuel pellets were quite similar. a) IRG-87(GpHS-25); b) lRG-88 (GpHS-27); C) IRG-89 (GPHS-23); and d) lRG-90 (GPHS-29). 250x.

11

c

*

Fig. 2.The module’s position in the heat sourcestack is maintained by the lock rrrembersvisible on top of the stack.

n-7--SHE

LOC

Ficr.3.The lock-member shear t&ts were carried Out using

a

.

a shear fixture that simultaneously loaded two lo~kmembers.

12

-i~ ..= . . ...+..,.- i—.. ——.@= ‘- a,...,.

Fig. 4.The parts of the shear-test fixture areall visible in this photograph.

.

Z BUNDLE ORIENTATIONRELA~ TO SHEAR TEST DIRECTION I

XY 0°Fig. 5.

Four characteristic orientations for theFMPF structure were tested in shear(arrows).

z 0°XY 90”

z 90”

XY 0°

73

SEeu

4W%3

3ee4

U-1L

~2nm

(nwa1-U-i

mm

I

FWPF LOCK MEMBER

SHEAR TEST

It

PZ DIRECTION PERPENDICULAR

XY AT 0 OEGREES

/ 2.41x10TS PSI/INCH Ia.- n.81 L&? #.m CM Lm

DEFLECTION (INCHES)

(a)

FWPF LOCK MEMBER

SHEAR TEST

““~

4WS

We4

Z DIRECTION 0 OEGREES IN PLANE

XY AT90 OEGREES

lZl$x10t5 PSI/INCHa9.W 8.11 #.m3 S.S3 I. 84 9. as

OEFLECT ION (INCHES)

(c)

Sblea

4eL7B

3W3a

mO-

~ 2k3aaInwa1-In

1LW6

a

FWPF LOCK MEMBER

SHEAR TEST

r

<

‘

0/ Z OIRECTION PERPENOICULAR

XY AT 45 OEGREES

2.03x10T5 PSI/INCH

3. m 0. M 0.02 am a. #4 e.us

DEFLECTION (INCHES)

(b)

FWPF LOCK MEMBER

SHEAR TEST

““~4U243,

38(s4

mn

~am,

HLx)-UI

lam ,

Z DIRECTION 90 OEGREES IN PLANE

//’ XY AT 0 OEGREES

1/ 2.28x10t5 PSI/INCH

am a al LE2 3.03 R B4

OEFLECT 10N (INCHES)

(d)Fig. 6.

The shapes shear stress vs deflection curves for FUPF varied with the orientatof the microstructure of the composite. a) Z perpendicular, XY at OO; b) Zperpendicular, XY at 45°; c) Z parallel and OO; and d) Z parallel and 90°.

14

8.8s

\

.

on

?

.“

(b)

Fig. 7.The GPHS fuel pellets received fromSavannah River Laboratory all containedsurface cracks. a) GPHS-28; b) GPHS-29;and c) GPHS-31.

(c)

15

(a)

,,,’ylla. 21 , 31 ,4:-, .51

(c)

(b)

Fig. 8.Photographs of the impacted sample fromrlHFT-68. a) Impact face, b) profileview, and c) back side. ~lx.

.

I

16

L

7“

. .r .,-

. .

(’”

,.,

‘\ “,-. \.!

,.,/ .)

.-

(a)

..

Fig. 9.Microstructure of the equatorial weldof the iridium shell of MHFT-68. 40X

-.. ““-n./’..+

.[.

,4, .:.—-. \,.

,-w

L--’

.- .,\\ ‘<

.4’.1 ‘....

. .

(b)Fig. 10.

Microstructure of one hemishell from the iridium shell of MHFT-68. 50X.

Fig. 11.Photomicrograph illustrating the occur-rence of flat grains of iridium on theinside surface of the iridium shell ofMHFT-68. 250X.

Fig. 12.Photomicrographillustrating a smallamount of iridium transport in theinterior of the iridium shell of MHFT-68.250X.

(a) (b)Fig. 13.

Microstructure of the plutonia sphere from MHFT-68. a) Area near the impactface surface, and b) area removed from the impact face surface. 250X.

18

,AIIDITIONAL DISTRIBUTION

Pi.G.J.P.0c.R.J.J.R.n.H.MOD.H.M.R.w.T.R.G.R.

J.L.J.!3.o.

Rock, Dept. of Energy/ANSP, Washington, DCBennett, Dept. of Energy/ANSP, Washington, DCLombardo, Dept. of Energy/ANSP, Washington, DCMorrow, Dept. of Energy/ANSP, !dashington, llCTarr, Dept. of Energy/ANSP, Washington, DC

Rrouns, Dept. of Energy/ANSP, Washington, DCGriffo, Dept. of Energy/ANSP, Washington, DCL. Liverman, Dept. of Energy/ANSP, Washington, DCFerguson, Dept. of Energy/ET, !~ashington, DCK. Stevens, Dept. of Energy/BES, Washington, DCE. Roser, Dept. of Energy/ALO, Albuquerque, NMYcMullins, Dept. of Energy/ALO, Albuquerque, NML. Plymale, Dept. of Energy/ALO, Albuquerque, NMN Hill, Dept. of Energy/DOA, Miamisburg, OHJ. Sires, Dept. of Energy/SRO, Aiken, SCJ. Hart, Dept. of Energy/ORO, Oak Ridge, TNL. Von Flue, Dept. of Energy, SFOO, Oakland, CAB. Kerr, NASA, Washington, DCA. Ivanoff, NASA/JPL, Pasadena, CAStapfer, NASA/JPL, Pasadena, CACam~bell. NASA/JPL. Pasadena. CA

AFISC/SNS, Attn: CO1.-J. A. Richardson, KAFll,Albuquerque, NMAFWL/NTYVS, Attn: Capt. J. D. Martens, KAF13,Albuquerque, NMHQR.R.J.G.R.J.w.w.E.H.R.H.E.I.c.E.J.R.

kc.R.v.E.F.J.P,.

Sbace lliv./YLVS: Attn: Lt. Col. Needham. -Los Anqeles,-CAL;H.R.w.A.R.T.

Folger,” SRL, Aiken, SCTait, SRL, Aiken, SCMellen, SRP, Aiken, SCWilds, SRP, Aiken, SCBrownback, SRP, Aiken, SCMcClain, MRC, Miamisburg, OHCave, MRC, Miamisburq, OH

Amos, MRC, Miamishurg, OHW. Johnson, MRC, Miamisburg, OHPostma, ORNL, Oak Ridge, TNCooper, (_lRNL,Oak Ridge, TNInouye, ORNL, flakRidge, TNFoster, BCL, Columbus, OHGrinberg, BCL, Columbus, OHAlexander, BCL, Columbus, 01{E. Rice, BCL, Columbus, OHHagan, APL, Raltimore, MDW. Englehart, NUS Corp., Rockville, MDH. Van Tuyl, PNL, Richland, WASchock, Fairchild-Hiller Ind., Germantown, MDW. Whitmore, GE, Philadelphia, PAHemler, GE, Philadelphia, PAHaley, GE, Philadelphia, PAC. Krueger, Sundstrand, I?ockford, ILSchumann, TES, Timonium, MDBoretz, TRW, Redondo Beach, CAHartman, GE, Philadelphia, PA

N. Mecham, ANL, Argonne, ILG. A. Cowan, Los Alamos, NMR. D. Baker, Los Alamos, NMR. N. R. Mulford, Los Alamos, NMW. F. Miller, Los Alamos, NMR. J. Pryor, Los Alamos, NMG. R. Waterbury, Los Alamos, NMR. Behrens, Los Alamos, NMS. E. Bronisz, Los Alamos, NMR. A. Kent, Los Alamos, NMW. Stark, Los Alamos, NMl?.W. Zocher, Los Alamos, NMJ. A. Pattillo, Los Alamos, NM

20

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