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UNCLASSIFIED
ORNL
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226

SCF,
ORNO-P-726 Dus
UNF- (54 -4
HOT CELL TEXHNIQUES FOR THE EVALUATION OF PUBLAD GRAPHITE SPHERES
D. R. Cuneo, E. L. Long, Jr., and H. E. Robertson
Reactor Chemistry Division
Oak Ridge National Laboratory
Oak Ridge, Tennessee
LEGAL NOTICE
D. R. Cuneo
Reactor Chemistry Division
Building 2024
.
.
.
..
.
..
Summary - 3 pages
Figures - 1
*Metals and Ceramics Division
-
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27.
HOT CELL TECHNIQUES FOR THE VALUATION OF PUKLAD GRAPHITE
SPHERES
D. R. Cunco, B. L. Long, Jr., and H. B. Robertson
Reactor Chemistry Division
Oak Ridge National laboratory
Oak Ridge, Tenness66
SUMMARY
Fueled graphite spheres wili be used to fuel the German AVR pebble
bed reactor. Development and testing of a fuel element of this type have
been underway at ORNL for the past 24 months. These spheres are sueled
with pyrolytic carbon coated particles, 2004 in diameter, of either UCZ
or (u,Th)C2 contained in a graphite matrix. For postirradiation exani.
nations we have utilized techniques and equipment common to bot-cell
work, but also equipment which was designed specifically for exani.
nation and testing of spheres.
The fuel spheres were 1-1/2 in. and
:
2.36 in. in diameter, and were of several types of manufacture.
.
.
.
The spheres are generally supported during irradiation by closely-
.
.
Pitting individual graphite holders with fluidized coke in the voids
-
-
-
-
between the spheres and holders to effect good heat transfer. The
entire graphite assembly is fitted into a stainless steel capsule which
18 either equipped to allow sweep gas entry and exit during irradiation
or 18 sealed to contain fission gas. Sphere temperatures are monitored
during irradiation. Figure 1 shows, schematically, a capsule ready for
irradiation and a photograph of 8 spheres and their bolders following
irradiation. Detailed design of the experiments and some of the early
results were previously reported. 1,2,3,4
*Research sponsored by the v.8. Atomic Energy Comedosion under contract
with the Union Carbide Corporation.
Hetals and Ceramica Division.
In the hot-cell, we obtain g88 samples by puncturing the sealed
capsule, make gamma scans and make measurements of sphere diameters
after opening the capsule by a remotcly controlled slitting device. We
weigh the spheres on a standard balance. Evaluation of weight and/or
diameter changes yielde information relative to effectiveness of
various manu.acturing methods, preirradiation treatment, etc.
For use in a reactor these elements must be resistant to impact
and compression forul:8.
Roth pre- und poet irradiation tests for these
propertiei ais carried out by equipacnt designed at ORNL. The com-
pression tester utilizes a loud cell and motor drive with the signal
fed to out-of-cell luxtrumentation. The impact tester le arranged
to allow dropping of a variable load from a fixed distance onto the
Epliere. Tae sphents are testei in plastic cupe with thick steel
bottoms and 0.005 in. thick copper tops. Such containment prevents
spread of highly active particles and dust in the hot-cell.
Meta llography specimens are cut from selected spheres and ex-
pmined in hot-cell and toxic laboratory facilities. These examina-
tions include standard hot-cell metallographic techniques, but several
new techniques have been developed for the coated particle fuels. By
condining autoradiography with optical examinations, we can distin-
guish between enriched UC2 pyrolytic carbon coated particles and per-
ticles containing normal uranium. In addition, etching techniques
allow distinction between UC2 and mixtures of (U, Th)C2.
Analyses of various portions of the assembly, including spheres,
holders, and flux monitors, are made to determine uranium burnup, flux
distribution, uranium migration, cracked particle coatings, and con- '
talement of fission products. Analytical techniques include gamma
spectrometry, activation analysis, and radiochemical analysis.
REFRENCHS
(1) Sanderson and Porter start, myruel Elizment Development Program for
the Pebble Bed Reactor, Phase II, Summary Report," NYO-9062,
November 1, 1959 - October 31, 1960.
(2) Oak Pidge National Laboratory staff, "Conceptual Design of the
Pebble Bed Reactor Experiment," USAB Report ORNL-TM-201, May,
1962.
(3) F. L. Carlsen, Jr., W. 0. farms, J. A. Condin, V. A. Decarlo,
J. G. Morgan, and D. F. Toner, "Irradiation Brperiments on
Graphite Matrix Puel Elements Containing Pyrolytic-Carbon- .
Coated Fuel Particles, " Trans. Am. Nucl. Soc. 6(1), 157 (1963).
R. C. Koch, G. L. Grandy, I. J. Gruverman, R. F. Weise, and
C. R. Wilson, "In-Pile Loop Test for the Pebble Bed Reactor
Ruel Element Development Program, " 18XC-47, April 28, 1961.
Coated Fuel Partio
Am. Nucl.


...
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IIIIIIII
UW.OUR TUR.
- IMEAMOCOUmes
TOP CAS-
.
..
.
.. .
T
.
.
13.SHOW
MODUCI OC OSITION
Tv .....-
ا..
TOP INSULAYOR
IMERMOCOUME WELL
CONTRAL IMERMOCOUPLE
MITE SOUCIA
CAPSULE MIMATY
CONTAINMENT
هلال
Couro-WTIQUE SAMEMS
CRAWUTC STACK
ennt WTA MERS
مه
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OTTOW MSULATOR
01
.
.
محرم
8B-4
Fig. 1. Schematic View of Capsule for Irradiation of Eight l-1/2 in. Diameter Spheres at Left,
and Eight Spheres and their Holders following Irradiation on the Right.
PO CEL. ECCO GUES P'O: HE
EVALUATION OM V Giving
SP:
ICS
១ .
R. C .CO
2. L. Lain, Jr.
1. E. Rowertica
OUR Roje liu: 10x.al laboratory
REQuic. Cedwiry Division
ذنب
رهنة
مانند
:
HON CHILE CHINA.
EVALUATICO Cř roku
Spikes*
Dit is
GiWiiTTE
LOUIE
D. R. Cillico, E. L. Win, Jr.,'
6 .
!!. E. Ruvelwci.
Ouv. iliane national Liburaiory
Reactor Ciclistry Division
Quis Rivist, Verviessee
ABSTRACT
ca specimens to determine irradiation
eii'ects on uranium migration, sta-
bility or particle coatints and to
separate thermal effects from combined
thermal and irradiation erfects.
Techniques and equipment developed ior
hot-cell hundlit o: fueled graphite spheres
are being u:1lized to evaluate this type o:
fel eiene.ii iollowinë irradiation at réalis-
tic teinperatures and flux. Spieres ou vury-
ini sizes and wethods o: ufacture have
been studied. All types of sprieres were
fueled with pyrolytic-carbon-coated UC2 or
(U, Th)C2. The techniques used include
INTRODUCTION
(a)
Gas sargpling to test caseous fission
product retention.
Gamma scanning to check relative bura.
ups of several spheres in a single
experient.
During tlie past 24 months & programu
development and testing of spherical graphite
maürix rüel elere:its nas jeen underway at
ORNI. Elements of this type will be used to
fuel the German AVR pebble bed reactor. The
spheres tested were either 1-1/2 in. or 2.36
in. in diameter, and contained pyrolytic
carbon coated fuel particles of either UC2 or
(U,Th) C2. The ratio of Th/U has varied iro:..
0.5 to 2.2. The fuel particles averaged 2004
in diameter, and were dispersed in a graphite
matrix. The spheres tested were of the
following types.
Deterruinations of weight and diameter
charges, allowing us to check sta-
bility of ceinerts and binder. And types
of graphite wr.der irradiation.
Compression and impact testing to
learn what effec is irradiation may
have on these wechanical properties,
and
Metallographic examinations of select-
1. Molded with no shell; fuel particles
dispersed throughout.
Moldeà i'uel cores contained in unfueled
molded shells of various thicknesses.
*Research sponsored by the U.S. Atomic Energy
Commission under contract with the Union
Carbide Corporation.
Moldeo t'uel cores coitained 11 uniweled
rachined shells of various thicknesses.
Metals and Ceramics Division.
h. Machined unfueled graphite spheres with
cylindrical fueled graphite inserts.
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51
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: : .::: ) نان به عندنا دن م
ار: ره تانجمنهن ..:::.
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, عادته: نن منه ، اتان د نده : نه ، ز ، ندمان نذا
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r t
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cCa
aater &
1 باغ به ز نا 1 ان 11باب .i3 cot به نامه روزه
1c
:
a هنه : نان به من Vry :: ...ما نية
spiere is con-
Tiruiiuiloin, while trit boito
ali.cü ii. is incon 10::.per::it to allow rission
tlou releuse race stucieu.
|
|
hilo liie irraciutton were carried out
1:: the ORRAĆ & flux o: 10-3 Co 1044 n/cm2.
Izruciation tlies sive varied froin 1 to
sec.
3 reactor wycles (7 to 21 weeks). Design
itt:&cümes or ine spieres were lu00 to
270CF. and burnups varied from 0.5 to 19%
(vased on arrivhed uraniw particles).
Surluä сorie intie 1/1,-
co; oir the river.
ucteu es üyestrvoir ji
1... cadiri P
نا .. :: : : .. ::::::: :.: ": ا ::نا''
من هذه .. معنا ندانی من ::ههههه
POSTIRRADIATION EXAMINATIONS
picade 20).ders, ni convi cliüs seen in this
ve veze iuürivaid irom. Liepnice excepi
ose nere due isci staiii-
ile ilux roj.
@ö uiialyzed ior39co content,
ca
less steel
post1.rudiüiica analysis for 60 co allowed
culculatio:i 0: the average ilux to which ilie
exper...ent was exposed durino irradiatior..
.
Arier removal i'rom the reactor, the ex-
periment is moved under water into the not-
cell which is over tiie ORR pool, and the
extraneous pizini, wiring, and secor.cary con-
tarnet vessels are removed. The capsule
containing the spheres is then transi'erred
to a suitable not-cell i'or the collowing ex-
Quinations.
(2)
Sunderson and Porter Staf:, "Fuei êle.
or the Pebble
.ert Development Projra
Bed Reactor, Phase II, Swary Report,".
VYO-9062, November 1, 1959 - October 31,
1960.
A.
(2)
Ou Ridge Vaiioral Laboratory Star'i,
"Conceptual Design ci' ühe Perwie Bed
pertueat," USAEC Report ORKL-
Reactor
TM-20i, May, 1962.
Gus Samplin - The static capsules are
puctured to recover the i'ission Eas.
Fl: Ure shows the ri: in wiiich the
The üctuai punc-
puicöuring is done.
turine of the stainless steel capsule
is erected by a drill with a 1/16 in.
diaeter tip. Only the shank on the
drill 16 visible in the figure, above
the 6&s-iigit seal arrangement which
contacts the surface of the capsule.
The compression i'ittinz, visible in the
figure, 16 coniected to a vacuum system.
This system 16 equipped to accommodate
318ll as sample containers and to allow
dilution li aciivity readines indicate
The yas
need for less active sa ples.
Samples are submitted for quantitative
analysis of composition and isotopic
distribution or xenon and krypton. A
F. L. Carlsen, Jr., W. 0. Haris, j. A.
Conlin, V. A. DeCarlo, J. G. Morgan,
und D. F. Toner, "Irradiacion Experi-
erts on GrupaitMatrix Fuel Elements
Containing Pyrolytic-Carbon-Coated Fuel
Part1cles," Taas. 0. Nucl. Soc. 6(1),
157 (193).
R. C. Kocia, G. L. Gray, I. J.
Gruvernan, R. F. Weise, and C. R.Wilson,
"In-Pile Loop rest for the Pebble Bed
Reactor Fuel Element. Developinent Pro-
STC-4'7, April 28, 1961.
ra,
HOT CELL TECHNICJES FOR DE
EVALUATION OF FÆLED GRAPHITE
SPHERES
D. R. Cur.co
E. L. Lom, Jr.
8. E. Robertson
das Riace tatlocal lavoratory
Rcavico Citutry Diviziun
Oui Ridre, Tennessee
typical analysis is shown to F17. 5.
The success o this suurpiilotetud 15
evident from the fact tiau toe uudyols
showed the contents o irie capüült to
te ciilclly the beri tus wit: ca. tile
capsule was ikilec verorė irrudlasici..
This sho's nul: Eicle air cortaduation
durisid samplinis.
wilcter, with a motor driven wordt gear
to ove the saw tabie and various hand
operated positioning devices. Tie
cutlich wiecl is in position to begin
to do..citudinal cut oi' the capsule.
dec 20 Blows the relative positions
vite spl.cres and holders in a cwany
cupsüle, following slitting, and Fie 11
siłow'the rocail chuck holdins & cap-
sule 1: posli10:: ior erici cap removal.
Gaio Sca:1:1.. - Guna Suans are made
Deiore tre capsule is opel.cd arü o:
the lindividual spheres arter removal or
the capsule.
D.
A drawing or the scawler 13 show'li
in Fic. 6. The cocor and pulley
arrane.Clot travel che capsule pusi tie
3lit at a fixed speed. The scintille-
tior. crystal is locuteu out o: che cell
This clin.1:&tes the liee for shicluins
iron ühe higii activity level of the
cei aid acilitates calibration with
& 137C6 source. The crystal output is
recorded by a recorder whose wiart
speed ratches the travel on the capsule
in the scanner.
Wel..C:.. Decemb.. !cas - The
hes.Cö oi che perts ür'c Chre:'ully
der erined beiore ai uiter irradiation.
Weicü changes treator lizen 0.2% pay
indicate & loss in street. This will
be discussed wider Compression and In-
pact Testing. The sphercü are Elven a
ratne: severe vakeout before irradiation
to remove volatile components o? bind-
ers and cements used to clue the cores
to the writ'ueled shells. However,
duri: Irradiation t'e spieres
occasionally are subjected to more
severe terperature excursions than
those for which they were designed. In
some cases, welcht 2068es have been as
high as 2%.
Any Erious displacerent couel can
be detected before opening of the cap-
sule, Scans of the irradiated spheres
are suficiently derinitive to allow
quick recognition of variations in the
thickness of the unfueled shell and
abnormality in fuel loading. Figure 7,
for example, shows a sharp dip in
activity indicative of a low density
region in the fuel matrix in spbere No.
1. Tie varying widto or the curves
reflect unfueled shell thickness of
0.33 in., no shell, and 0.25 in. res-
pectively for spheres 1, 2, and 3.
There is, of course, a direct relation
between uranium burnup and the area
under the curve of the gamms scan.
Figure 8 shows the relative areas under
the gamma scan curve witn burnups for a
3-6pbere experiment located such that
sphere No. I was adjacent to the reactor
face with spheres 2 and 3 positioned in-
creasingly farther away. The nor-
raa lized values of areas and burnup Fre
seen to show very good agreen:ent. The
actual gamma scans are also shown in
this figure.
Dianeter Vacsurements - The spheres in
a pebble bed reactor are moved either
by Eravity or preunatically, and 11 16
desirable that they underco a win imiva
or change in diameter. We seldom ?ind
a significant diameter variation, par-
ticularly in the most recent experi-
ments, with spberes irom newer vanu-
facturing methods. Changes less than
0.1% are considerable inconsequential.
Figure 12 shows the currently-used
sphere measuring device with a 1-1/2 in.
sphere in place. It !6 possibie to
position the sphere very accurately
between the dial-indicator type cea-
suring gauges. Several trials and 00-
servations are made to be certain the
indicator tips are located at the maxi.
mum diameter of that region of the
sphere. Four readings are made of each
sphere at the pole, tenperate, and
equator regions. The average of four
readings should be accurate to +0.0005
ini.
C.
F.
Opening the Capsule - The next three
figures show the apparatus used for
slitting open the capsule and removal
of the spheres, Figure 9 shows the
Compression and Impact Testing - For
reactor use, the fuel spheres must be
resistant to compression and impact
forces. Tests were run on unirradiated
.
TI
Ch 20:51.
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SPiz
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CAP:!!!
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z... kies jis
b. E. Ruitatea
Oticipat livinliburacody
Recuto: Chemistry Division
Oui. Riüsey Sonntavle
. را
. رفت: نه، : م. ن...ت
upliereb üwline tiie vi-uell equierei
te:ort it was place .. hic cell.
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ر
ا ن، ن : ن
-: ا د
مر). ، ، ته ننان: ذرا ننع نن 433 ای!Core
ربانزل وعامت
::ة
او د نندنا: زهره
ننه نان
.:
hic, wij bec: 0. Cinc !ciü. Ouric'6 iu:1
by & uadui erodi:ë or chipping away
OA : نان تد، زن y the .: د.نز نند
د. با
ici.L"This opi.c!ć Dejana w.1pping at
ü: 1.avtos jy 1000 , w licacied
ühe staut who'mir Ilicic Ivire at
Lipuess; Gilil with.dui iructurin6.
The juppiy o: il.t'' uptocosies uvull-
wile i'or both wirrudisitu Gioci !rruuiui-
:: 4 باند به مان
:
:
1 : : ::
،
t :::
11
:
4
stilar sphicrowy cor. :: citiru
laboza ücry eqüiu.erot yieiücü curicu porsik
in data. Fire I3 is uplotour'üpis oi'
the coagrossici Cester with a 3-1/2 in.
diaeter sphest in peace. The couprès-
üion tejier wakes use o: & load cell
and Oor ürive with the resultiin
wiinas being ici to 1.süru.cn,&' 1011
cuisice the cell. In acüiul practice
the sphere in contained, durine test-
int, in the plastic cup ceea to tie
left of the sphere. This cup in a
ühick steel base, Sütis wide ülit :piere,
and the top is a 0.005 ái.-iis cx pui
copper slut. Tuis cum arru: 6641
ullo'üll the corrowi ivci :'ordt û be
experices on the sphere while oii'erino
compiute coutaimeri io: the fruipients
öz the where we rupturi Occurs. It
is 1:.teresting to rote chat the loan to
ailure isis rakti orci avout 600 to
5000 pounds. Figure 1.. shows priocio-
graphs oispheres aiter copression
testing. The sphere at the left t'ailea
au 1450 pounds. liote the lack oibord-
1:18 02:'uei core to the uniucleu sien.
The weicht lcs6 1.n this sphere whes 0.21%
(od 50 my), probably due to vaporization
of cerenting material betwee:) the core
and shell. On the right is a sphere
which ialled at 2500 pounds. The good
shell-to-core bond is evident.
resistance lies beer. quilte 117.1ied.
Therefore, we do not pulve good static-
ticul values to show eii'e:cis, 17 any,
oi irradiation on theje properties.
Froin the testine which has bec: poisible,
However, ii sces 11ely that irracia-
üloi. fus littie si uny ericci ori coiü-
pression or dr.puct resistance. Panu-
ructurini Chod is obviously a much
treuter l'actor.
G.
jciallovenite din4ü 10:19 - The
slliiing macnire already described to
also used to cut specimens from the
spieren zor metallograpnis studies,
These specimens are counted in an epoxy
resin, then lanped by a coldkercial
lapping machine which has been modiiled
for remote not-cell cperation. The
specinens are then polished and transa
i'erred to the remote metallograph for
examination.
We carry out impact testing by use
of the apparatue shown in Fle. 15. A
movable begin is ifted by a sprocket
drive to a height oi 24 in. At this
point, the begin is released and falls
onto the sphere in the plastic cup des-
cribed above. The force of the tupact
Tiiay be changed by adding weijnts to a
spindle in the center of the bean.
Based on limited data correlation be-
tween the weight used and the nurver
of impacts necessary to fracture
spheres of similar manufacturing gethods
is apparentiy a function of juomeatwa.
The weight of the bear has been varied
fro: 325 grams to 1000 grams i'cr test-
ing a variety of fuel spheres. Fail-
wres have occurred in the range of 2
to 85 impacts. A few solid graphite
spheres (unfueled, unirradiatec) were
found to require as many as 250 un-
pacts by 1300 g to produce failure.
Two modes of failure are shown in Fig.
In contrast to the unirradiated
thorium-ura:iiwn carbides, the ir-
radiated reactor fuels can be examined
at leisure in the as-polished condition.
Figure 17 is an example of the decreased
chemical reactivity o: (U,T) C2 with air
after irradiation as corpored to un-
irradiated materiul. The wiirradiated
carbide su::ers & rapid deterioratica
in air, whereas, there is o evidence
or a reaction on the surt'aces of the
as-polished irradiated particles after
veinti exposed to the atmosphere for over
an hour,
odai sin siis
Aiter examining the polished sur-
Puces ine specizens are ttched wiin an
equal parts solution o? INOZ-CH3COO-
H20, rinsed with a solute etiny. ulcohol,
dried, and re-examined. The etching
time i'or UC2 is short -Usually 10 to
20 sec is all that is required; the
etching tine for (u, Th) C2 is sovewhat
longer - usually 1 to 3 min.
r
P
9 CE2.II ES POTE
Linn.:C: ropa OFWPEITE
SERS
5. R. C EO
E. L. Lorë, jr.
3. E. Robertsoa
Oak Ricce lat. 8: laboratory
icacior Ciemotory Division.
Ô Ridge, tennessee
:: مهند مسنه .:نتاج
atory : 1
5
4
3،
ccorcisidor victional scanities with Outl.),
4
:
45 من dee
.ه! څه : ماه :
ete
:
:
e8
,
SU
Compressio.. ario de aticuit. &iidi welación
Uploi endinebra idol. öi wodocitu speccosi,
Ceci uz vc se posirracin::05 lectu colitri.
buitü ise au cuc.ovali:00 O: various
...
coriacewerende rosüdüs ö: ul.
steinkbe dowicca :0 separa:c thermometria
c!?6.Puli.t cmner.cccrita 61.0
o'
lida:0:. t::ccio are wi04;. X L
con Áirali ispi.crc ita etica .
de vie r0n watch.ca or proviny: 12.
cardioidentitá (0,*..) C2 pericits with a
"..Zvij j: 0.0. mind 0..ve..:-
ca :::: .00 :8. jico inó ita: 05.0:0:
jár:..co 2.5 conti come viilud ý %
ti..... (,..) 2 Stoc Luc oli.e."
(U,..) Ca particicavitiónes batura:
w
rodo muere Win 0..c creier.!
6.no spiccs ::radidit:1. 6. eight-
.نن. مه مه.تي. . من.نکت
ت
م:
der.نا rrصرنه
speciibo cuadri:558 ji' iamrat wc, bildsip,
and roacto: flux.
cit .ونده نزاع مهم
تا...Te P e
cperutta &: le cekira: icmperature or
io Scuºr, acuti.c e::richieder-
jocacio caned a bite or approxi-
ملت
نه
.
4 .
.ذهن ته زه
Compar: 606 0 1:16 : wisted catiba
ci yariácico b13b. .0 wliorulait: con-
10 ..wato ha ao ošvicubicro-
ci nemasë civile si ocurred in inc par-
.4
ن أهمية
..لنا 1 اهنة أهلنا :a: دته م
Distillo.. o: tnc cricicrued par-
cenatoca eles, reveal orosw Citroen
iscr: appcaruöce. Wedee-öhayes cruc-
into aici cea o ila: Oricates st the
wei-cuito dicerita internet betri tú
propochie troete che pyro Vic-carbon
coat.inc haso, a coniiduous, letti -
وما تتمتع
:tea:و 6قه پایین تر ننه :
::. iáe peripheral regions oi the (U,ni.)
Ca dei mamicie, sked the nei particies
s..comes dies 0: piastic flowAfter
escá n ere &6 20 evidence ou crys-
28.1:..e cialis in the rise. wdier. Examin-
منهم من دع
فون نمبر :) :e.: :.عن
ott
As an auditioiind cbeca on ihe
ice: : o: the carbide perilcles,
& cardicorapoy w&b periored on the
eta2.20crapbic specime... The specimen
speciz06copic :: La darkened hot-
cel :07 ricrious itines rangine from
50 sec. Sinie he film is in-
sensitive io y, shortly sensitive to
ū, una gran sensitive 10 ) radiation,
de erriched particies were readily
cisceraidie trom the particies or normal
caricheut. on positive priut from the
aütoraniliograpa is show in iz...
To owarice, I have a templed io deö-
cribe or you some of the bot ceud techniques
used com evaluation om iueles graphite
bpbere. miese techniques Lecluie gas
*Type 629-0 Eastman Kodas Company, Kuchester,
New York.
some new in
UM-Out Tue
TOP CA
RSSON
MOOI OCNOS.TRO
TUDES

So I SU. ATON
IMACCali Mu:
CENTRAL TMELOCOUA
GRAD.IE POWO
-
.-
CAPSULE PRIMS.MY
CONTAINMENT
COANTO-M
IKAE stone ATS -
GRANITE STACK
GRAPHITE CONTAINS ÁS.
IMOMES
8017.
Svi d'on
BOTTOM C
Fig. 1. Capsule for Irradiation of Eight if in. Diameter
Graphite Spheres.

-
RAPHIC STACK
උපයන>
වරදාට
4.
TV
|+
|
A
TOP END CAP
FUEL arus
IONIOM ENO CA
•
Plg. 2. Bight Graphite Spheres and Fuel Containers with End Caps and
Graphite Sleeve Before Assaably.
sr
\
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:
….
jd
.
.
WAS TO
On On

SUAIACE 'ONPLAATURE
IMERMOXOUPES
Ouit
TUBE
!
iNhat A IUBE
COATKA. IMPERATURE
IMLAMO: OUlt
STATIC SECTION
i.GMAWILE CONIAME AS
-
-c
co
Goose
T***
..MORNIS CANAON
I NO IASILATUS
......
:
(NO CAPS

SWCEP GAS OUT
CRAPHITE POWER
!
---...---
SWEEP SECTION
..
--
-
SWEEP GAS IN
Fig. 3. Capsule for Iriadiation of 3-2.36 in. Diameter Graphite Spheres.
Top two spheres in static compartment, bottom sphere in sweep compartment.

7
Si
boles
:
:::*tis,?arri .
-**..**2;!;. !.360.co.ted on
H
e
t best
he
...:•:-:
je to do antisociazi "...?
.
Fig. 4. Apparatus for Puncturing Capsules to Allow Recovery of
Fiskion Gas.
residio,
f
L
.

'
-
1
.
.
1
.
1
.
WAWILI
Analysis of Gas from Experiment 8B-4
Gas
Vol. %
0.029
Не
98.97
CH,
0.014
H2O
0.006
HC
0.005
N2 + CO
0.033
0.002
0.94
0.007
0.001
0.003
Fig. 5. Typical Mass Spectrometer Analysis of Gas Recovered from
Irradiated Capsule Containing Bight Fuel Spheres.
UNCLASSIFICO
ONN-W-OW $90

.
.
.
RODINE MOTOR
REX
... Mol (THUIUM ACTIVATED) .
SCINTILLATION DETECTOR
(mme AIDOTOUUNIT
CAPSULE
Turun!
:323011111:11 millions
---
-
MEMOVADU QOLIMATOR -
-
-
-
.
-
-
.
he was. Web.
.
'
AIR TIGHT SEAL
....
lo-
Gomma Roy Sconner.
Fig. 6. Draving of Gamma Scanner Showing Apparatus to Moye Irradiated
Capsule at Constant Speed Past Scanning elit.
X
.
m
os
80
06
20
.
60
.
sc
50
*
0
to
0
a.
3
203C
E
20
01
10
0
TODO
TOP
01-7 SPHERES ONLY
BOTTOM
Fig. 7. Camma scans of 3-2.36 in. Diameter Spheres. Relative unfueled
shell thicknesses (0.33, 0, and 0.25 in., respectively, for spheres 1, 2,
and 3) are shown by widths of curve bases.. Low density fueled region in
sphere I shown.
.
2

LOOP 2-2
Sphere
Burnup
No.
Aroa. Under
Scan Curves
Normalized
-
100
200
57
Societimme sind national
Fig. 8. Gamma Scans of Spheres in Loop 2-2 with Correlation of Burnup
with Kelative Areas under Curves.
E

. .
.
+
.
..
ay:..
----------
Who?
.
-
-
.
*
-.--.--
.
..oviding en erkennen thu hwuser usamleguistinults •
..::. mor....saya
menganggang
•
VU
XL
hihihihihihihihihleilbliniininhnhuinnnnnlin birin
:: db.
:
... of tot
Fig. 9. Slitting Apparatus with Cutting Wheel in Position for Longitudinal Slitting of Capsule.
Fig. 10. Slitting Apparatus Showing Relative Positions of Spheres and Holders in Dumny Capsules.
We
f
so we como o
dominate
entistico chander within rendelet felis
minden side and one would like to h
a
contention Center Phones and thens
WAL
und meinasiasmantana de
l
mio ramonitaimmin ****
me
dedicat
o
alimentos corte
2
w asinsrian
S
d'imme
..
.
the
+
.. Timmersas old
...
'love.
.
I
..






EI
.
--
-
.
si..
***
. Wi
tware ancheon ,
t
MW: Nie
min**** ipo
babgu
yorim o
"";' wion:
Aldosijoti toidini
"
matrica
Fig. 11. slitting Apparatus Showing Rotating Chuck Holding Capsule
in Position for End Cap Removal.
tub.com and
mamae

-..
•
Fig. 12. Device for Measuring Diameters of Irradiated Spheres.

Machadon
.
t
wym
..
more here

منها
'
.
.
.:
V
ver
with mandi
hayo...- ..
.oo hot mondotti
..
.
vid. min Voog
the
window
we
would
Fig. 13. Compression. Tester for Graphite Spheres.
with motor drive and sphere containment cup.
Shows load-cell
$
.-


urin
-
.
mis m
...
inum
.
air technikai
- -
-
.
-
-
-
.
. .-..
...nem
..
-1
2.
"Imamo
Anxi!..
(b)
Fig. 14. Fuel Spheres After Compression Testing. (A) Failure at
1450 pounds; lack of bonding of fuel core to wfueled shell evident.
(b)Failure at 2500 pounds; good bonding of fuel core to unfueled shell
evident.

. .
:
:
і
:.
Impact Tester for Graphite Spheres Showing Sprocket Drive and
Weighted Beam. Sphere to be tested in containment cup.
Fig. 15.
u
...
r
и
..
.
.
... ...
. , ..••• а.
...
г р
{. эг: •.::...
слухом
. .: :.....
ук, ~. .. .
.
у
.
..
... ...
•
хандлага
сальпінізуші:
nie
en distinktas
—
.
..
-

ASK.
Cami T


.
:
acce
...owian..!!
17
.
....
7.
."
- -
-
-
- -
-
.
-
-
.
.A
(9)
..
.
-..-
-.
Fig. 16. Fuel Spheres After Impact Testing. (a) Showing failure after two
impacts; unfueled shell split at equator. (b) Puel sphere with no unfueled
shell after 85 impacts.
doi.si istirnawaambia mnamo
ic.
T
beim
T

.
na: ****
e
..
3
C
..
I LFELTE
.
...***
minni.
maliwanag
xoʻz
wewe na maswali

..-9-!::
vode mine.......canismo se h
$3HONE
crirea si

.:
ace
:.
.....
:
Xooz
Fig. 17. Pyrolytic Carbon Coated (U,Th) C2 Particles with a Th/U Ratio
of 2.2. (a) Appearance of the as-polished surface of an unirradiated particle
after being exposed to the atmosphere for 3 minutes. (b) There is no evidence
of any reaction of the as-polished surface of this particle with the atmosphere
after several hours exposure. The Irradiated particle reached a B.U. of only
2.7 atom % heavy metal. Mag. 200X.

.
-
-
La
Lips. "
and
be
i.ima
power ..
.
ens..---------...
mi
-
.se
.. ... ..
'
'
*
Diana
.
7**
osutuoli
winddicht.
.
3
: .-me
- We .
----
.
.......
lo)
1o)
10i
Fig. 18. Pyrolytic Carbon Coated (U,T.) C2 Particles with a Th/U Ratio
of 0.61. (a) Unirradiated particles; l'op, as-polished; Buttom Etched.
(b) Irradiated particles that contain natural uranium: Tor, As-Polished;
Bottam, Etched. (c) Irradiated particles that contain 93% enriched uraniums
Top, As-Polished; Bottom, Sched. Original Mag. 2008. (Reduced 50_%).
Scene in

bilincs visi
...
----
-
tohy
x
.
-
...
Fig. 19. A Positive Print of an Autoradiograph. Made from a
Metallographic Specimen that contained a Portion of an Irradiated
Fueled Graphite Sphere. The larger, bright spots were the result
of fully enriched particles while the smaller, dim spots were
caused by particles of normal enrichment.
-
.
..
DATE FILMED
12/ 2 /164




:
.
-
S2
VI
LEGAL NOTICE -
This report was prepared as an account of Government sponsored work. Neither the United
States, nor the Commission, nor any person acting on behalf of the Cummission:
A. Makes any warranty or representation, expressed or implied, with respect w the accu-
racy, completeness, or usefulness of the information contained in this report, or that the use
of any information, apparatus, method, or process disclosed in this report may not infringe
privately owned rights; or
B. Assumes any liabilities with respect to the use of, or for damages resulting from the
use of any information, apparatus, method, or process disclosed in this report.
As usod in the above, “person acting on behalf of the Commission" includes any em-
ployce or contractor of the Commission, or employee of such contractor, to the extent that
such employee or contractor of the Commission, or employee of such contractor prepares,
disseminates, or provides access to, any information pursuant to his employment or contract
with the Commission, or his employment with such contractor.

.
!
.
:
-
-
*.
-
END