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ORNL -4189
C o n t r a c t No. W-7405 -eng-26
I S O T O P E S DEVELOPMEPIT CENTER
C O M P A T I B I L I T Y DATA SHEETS FOR CERIUM-144, CESIUM-13r( , CURIUM-, A.ID STRONTIUM-90
S. J. Rimshaw
E. E . Ketchen
Isotopes Division
NOVEMBER 1967
OAK R I D G E NATIONAL LABORATORY Oak R i d g e , Tennessee
operated. by UNION CABBIDE CORPORATION
f o r the U. S. P.TOMIC ENERGY COMMISSION
4
iii
CONTENTS Fage
CERIUIV.144 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1
CERIUM OXYSULFIDE ( C e 2 o 2 S ) . . . . . . . . . . . . . . . . . . . . % I
CERIUM S ~ F I D E (Ce2S3) . . . . . . . . . . . . . . . . . . . . . . 1
CEROUS FLUORIDE ( C e F 3 ) . . . . . . . . . . . . . . . . . . . . . . 1
CESIUN.137 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2
CESIUM CHLORIDE ( C s C 1 ) . . . . . . . . . . . . . . . . . . . . . . 2
cm.1m . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2
CURIUM-244 SESQUIOXIDE ( Cm20s) . . . . . . . . . . . . . . . . . . 2
CURIUM-242 OXIDE CERMET . . . . . . . . . . . . . . . . . . . . . 2
STRONTIUM-90 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3
STRONTIUM-90 METAL . . . . . . . . . . . . . . . . . . . . . . . . 3
STROrJTIUM TITANATE (S rT i03) . . . . . . . . . . . . . . . . . . . 3
STRONTIUM OXIDE (SrO) . . . . . . . . . . . . . . . . . . . . . . 3
S T R O I V I L M FLUORIDE (SrF2) . . . . . . . . . . . . . . . . . . . . 4
i i
I
COMPATIBILITY DATA SHEZTS FOR CERIUM-144, CESIUM-137, CURIUM, A.ND STRONTIUM-90
CERIUM-144
REFERENCE COLUMN
The compatibil i . ty o f Ce202S with var ious containment ma te r i a l s 1 a t 1000°C and a t 1850"~ i s summarized as follows.
Container Maximum penet ra t ion observed, m i l s ma te r i a l 168 h r 500 hr 1000 hr
1000 " c Xastel loy X No a t t a c k Traces Traces Tungsten DTo a t t a c k No a t t a c k 2.0
Nionel 2.0 - - N-15 5 - - 2.5
1850"~
Molybdenum No a t t a c k No a t t a c k Traces Tantalum Traces Traces Traces Tungsten Traces Traces Traces
CERIUM SULFIDE (Ce2S3)
The compat ib i l i ty of Ce2S3 wi th var ious containment ma te r i a l s 2, 3 a t 1000°C i s summarized a s follows.
Container mat e r i a l
. Haynes 25 Molybdenum Ta n t alum Tungsten TZM Has te l loy X Nionel N-155
Maximum penet ra t ion observed, m i l s 168 hr 500 h r 1000 hr
1.5 1 . 5 0.1 0.1
N o a t t a c k Traces No a t t a c k No a t t a c k
0.1 0.2-1.0 No a t t a c k No a t t a c k No a t t a c k 6 Traces Traces
2.0 1.0
0.5-1.0 No a t t a c k
1.0 Traces
6 Traces
CEROUS FLUORIDE ( CeF3)
The compat ib i l i ty of CeF3 w i t h var ious containment ma te r i a l s 4 a t 1000°C f o r 1000 h r i s as follows.
Container ma te r i a l
I ias te l loy X Haynes 25 Molybdenum Niobium Nionel N - 1 5 5 Tantalum Tungsten
Remarks
S l igh t r eac t ion S l i g h t r eac t ion No v i s i b l e r eac t ion N o v i s i b l e r eac t ion Mo v i s i b l e r eac t ion N o v i s i b l e r eac t ion S l i g h t r e a c t ion Some r e a c t ion
REFERENCE COLIJMN CESTITM-137
CESIUM CI-IT.JOXIDE (csc1)
A C s C l source which was encapsulated i n s t a i n l e s s s t e e l and 5 contained 1540 cur i e s of 137Cs showed no s igns of r eac t ion a f t e r being opened nine years l a t e r . The source operated a t slightly above ambient room temperature.
CURIUM
CU~~IUM-244 SESQUIOXIDE ( cm2o3)
A molybdenum a l l o y containing 0. S$ t i t a n t i u m and 0.1% zirconium (TZM) was contacted with an oxide mixture containing 29 w t 6 244 Cm203, 57 w t $ 2 4 1 ~ 0 2 , and, 1 4 w t $ 2 3 9 ~ 0 2 . S t a t i c c a p s d e t e s t s a t 1.1-00"C for periods of 250 and. 1.030 hr and a t 2000°C f o r 25 h r showed no r eac t ion with molybdenum, even though t h e oxide
- -- 6
f u e l w a s molten a t 2000°C.
System
Cm203 powder i n W c ruc ib le
Cm203 powder on W f i lament
Cm203 powder on Ir f i lament
Cm203 powder on Pt-5O$ Rh f i lament
13 vo l $I B-type Cm203 i n a Ta rnatr i x
Temp, Time, "C hr A t m ---..- _I_ -I__
18 00
2150 (melted )
2150
1700
(melt e d )
1400
1 4% H2- 96$ He
1 He
10 02
1 2 10 -6 tor i -
Extent of r eac t ion
None detec ted v i s u a l l y 7
No reac t ion , wet t ing, o r 7 penetl 'dtion de tec ted by metallography o r by f i s - s ion fragment au toradi - 0 g I- a PhY
Curium penet ra t ion and 7 surface reaction'
No curium penet ra t ion 7 but poss ib le sur face r eac t i on
An un iden t i f i ed reac- 8 t i o n product was observed by metallography and X-ray d i f f r a c t i o n
Tes is at, 1100°C f o r 1000 h r and at, 2030°C f o r 24 hr w i t h an 6 oxide mixture containing 29 w t Cm203, >7' w t % Am02, and 1 4 w t :'o F u O 2 showed t h a t t h i s oxide mixkure was compatible with t h e a l l o y Mo-O.5% Ti-0.1% Zr (TZM).
With t h e use of i r idium in a metal-metal oxide cermet, a l l oy ing of i r idium with molybdenum was observed a t 2C)OO"C. A l s o t h e molten oxide mix appeared t o reac-t, wi th iridium t o form a lower melt ing a l loy . A'c 1000°C t h e r eac t ion between i r id ium and molybdenum was Loo slow t o be observed, a t l e a s t over ;I period of t jme of 1000 h r .
i . 3
STRONTIUM-90 REFERENCE COLUMN
STRONTIUM-90 METAL
Af te r exposure of 2036 h r a t 925°C t o l i q u i d s t ront ium metal, 9 it was found t h a t molybdenum and s t a i n l e s s s t e e l 321 showed good compat ib i l i ty with l i q u i d s t ront ium metal; t h a t wrought i r o n and Haynes 25 were worthy of f u r t h e r study; and t h a t Hastel loy C, Hastel loy N, Hastel loy X, and t i tanium had d i s - solved and were incompatible with s t ront ium metal.
No a t t a c k on molybdenum was observed a f t e r 5000-hr contact with l i q u i d s t ront ium metal a t 1000°C.
STRONTIUM TITANATE ( SrTi03)
The fol lowing results were obtained on stable SrTi03.
Container Maximum penet ra t ion observed, m i l s mat e r i a l 168 h r $00 hr 1000 h r
1000 O c Haynes 25 Traces 0.1 0.2
Nionel 1 .5 1.7 2.0 Tung s t en Traces 0.2 1 . 5 TZM No a t t a c k No a t t a c k No a t t a c k
Molybdenum N o a t t a c k N o a t t a c k No a t t a c k
1850"~ Molybdenum No a t t a c k No a t t a c k No a t t a c k
No a t t a c k Niobium No a t t a c k - Tantalum No a t t a c k Traces 3.0 Tungsten No a t t a c k - No a t t a c k TZM No a t t a c k Traces 5.0
STRONTIUM OXIDE (SrO)
The following r e s u l t s were obtained with SrO-7$ Be0 ma te r i a l a t 1000°C.
Container Maximum penet ra t ion observed, m i l s ma te r i a l 168 'rir 500 h r 1000 h r
Haynes 25 2.0 2.0 4.0 Molybde num - No a t t a c k N o a t t a c k
4.0 4.0-8.0 Nionel - N-155 1.0 1 .5 2.0-4.0 Tung s t en No a t t a c k N o a t t a c k No a t t a c k TZM No a t t a c k No a t t a c k No a t t a c k
10
2
2
4
- STRONTIUM FLUORIDE ( SrF2) REFEFBNCE C O L T J ~
Metallographic examination of t e s t specimens exposed f o r 11 19 months a t 925°C gave t h e following r e s u l t s .
Encapsulating Penetrat ion, in . mat e r i a1 Max irnux Average
Simulated SrF2 f u e l (1 w t $-eCa, 0.5 w t $ Fe)
Haynes 25 0.0006 nil. Ta l i n e r i n Coiiiplete pene t r a t ion of
Hastel loy C 0.001 0.0004 Hastel loy N 0. 00? 0.001 Haste l loy X 0.03 15 3.00L)L
Hayne s 25 'Ta 1 i ne r
Simulated aged feed ma te r i a l (SYF~ -1- 2-1/2 w t $ %r a s Zro2)
Haynes 25 0.0015 0.0008
Hastel loy C 0.0007 0.0003 Hastel loy N 0.0028 0.0011 Hastel loy X 0.0055 0. 00.lI-
'Fa l i n e r i n Complete pene t ra t ion of Iiaynes 25 Ta liner
i 5
REFERENCES
1. Oak Ridge National Laboratory, unpublished da ta ( c l a s s i f i e d ) , October 1965.
2. Oak Ridge National. Laboratory, unpublished da ta ( c l a s s i f i e d ) , May 1965.
3 . Oak Ridge National Laboratory, unpublished da ta ( c l a s s i f i e d ) , December 1965.
4. W. D. Box, personal communication, Oak Ridge National Laboratory, September 1966.
5. K. W. Haff, Examination of a Nine-Year-Old 137CsC1 Source Capsule, USAEC Rpt. ORNL TM-584, Oak Ridge National Laboratory (August 1963).
6 . J. R. DiStephano and E. J. Manthos, unpublished da ta , Oak Ridge Nat ional Lqboratory, August 1966.
7. Savannah River Laboratory, current experimental da ta , September 1966.
8. J. A. Donovan, unpublished da ta , Savannah River Laboratory, June 196-7.
9. Martin Company, unpublished da ta , January-March 1966.
10. Oak Ridge Nat ional Laboratory, unpublished da ta ( c l a s s i f i e d ) , June 1966.
11. Martin Company, unpublished da ta ( c l a s s i f i e d ) , May 1966.
I
ORNL-4189 C-92a - Systems f o r Nuclear Auxil iary Power
14-3679 (52nd ed . ) (SNAP)-Isotopic SNAP Program
INTERNAL DISTRIBUTION
1-3. Centra l Research Library 4-5. ORNL - Y-12 Technical Library
Document Reference Sec t ion 6-15. Laboratory Records Department
16. Laboratory Records, ORNL R . C .
EXTERNAL DISTRIBUTION
17. E. Lamb 18. H. G. MacPherson 1 9 . S. J. R i m s h a w 20. A. M . Weiriberg
21. R . T. Carpenter, Divis ion of Space Nuclear Systems, AEC, Washington 22. D. C . Davis, AEC, OR0 23. G . P. Dix, Divis ion of Space Nuclear Systems, AEC, Washington 24. S. L. Fawcett, D i rec to r , Battelle-Northwest Laboratory, Richland
25-27. E. E. Fowler, Divis ion of Isotopes Development, AEC, Washington 28. W. P. Overbeck, D i rec to r , Savannah River Laboratory, Aiken 29. J . A. Powers, Divis ion of Space Nuclear Systems, AEC, Washington 30. F. C . Schwenk, Divis ion of Space Nuclear Systems, AEC, Washington 31. D. 2. S c o t t , P lan t Manager, Mound Laboratory, Miamisburg, Ohio 32. S. J . Seiken, Divis ion of Reactor Development and Technology,
33. Univers i ty and Laboratory Div is ion , AEC, OR0 A E C , Washington
34-166. Given d i s t r i b u t i o n as shown i n M-3679 (52nd e d . ) under Systems f o r Nuclear Auxilia-ry Power (SNAP)-Isotopic SNAP Program category