2. To: (Receiving Organization) 5. PrDj./Prog./Dept./Div.: Distribution 11. Receiver Remarks: 11A. Design Easeline Document? [] Yes [XI No 3. From: (Originating Organization) 6. Design Authority/ Design AgentlCog. Criticality and Shielding R. A. Schwarz/E. H. Rantlklev Engr.: IAI Item 181 DocumentlDrawing No. NO ANSMITTED IEI Title or Description of Data Transmitted ID1 Re". NO IC) Sheet NO. - 0 Approval Designator IF1 Reason for Transmittal IGI E. S. 0. D or NIA 1 Approval 4 Review (see WHC-CM-3-5. 2 Release 5 Post-Review sec.12.71 3 Information 6 Dist. IRempt Acknow. Required) ~ Dose Rate Calculations for Strontium Fluoride Disposition IHI & Ill 1. Approved 4. Reviewed nolcomment 2. Approved wlcornment 5 Reviewed wlcomment 3. Disapproved Wlcomment 6 Receipt acknowledged Capsules and Cesium Chloride Capsules and for such Capsules as Overpacked f o r Disposal IGI R~~~ IJI Name IKI Signature iLI Date IMI MSlN SO" Design Authority . R e l a t e d EOT No.: 619209 . Purchase Order No.: IGI IHI R ~ ~ . Diap, IJI Name IKI Signature ILI Date IMl MSlN son . Equip./Component No.: 0. System/Eldg./Facility: 2. Major Assm. Dug. No.: 3. PermitlPermit Application NO.: 4. Required Response Date: (F) Approval Desig- "ator bason ongi- Trans- Dispa- rnlnai sitlo" c I Safety I Env. I - 20. 21. DOE APPROVAL (if required) Ctrl. No. pproved Wcomnents Originator for Receiving Organization ED-7400-172-2 (05/96) GEF097 BD-7400-172-1
22
Embed
I/67531/metadc676304/m2/1/high...R. A. Schwarz/E. H. Rantlklev Engr.: IAI Item 181 DocumentlDrawing No. NO ... (2.5527 cm) or 0.989 in. (2.51206 cm) depending on the capsule wall thickness.
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2. T o : (Rece iv ing Organ iza t ion)
5. PrDj./Prog./Dept./Div.:
D i s t r i b u t i o n
11. Rece iver Remarks: 11A. Des ign Ease l ine Document? [ ] Yes [ X I No
3. From: ( O r i g i n a t i n g Organ iza t ion)
6 . Des ign A u t h o r i t y / Des ign AgentlCog.
C r i t i c a l i t y and Shielding
R . A . Schwarz/E. H. Rantlklev Engr.:
IAI Item 181 DocumentlDrawing No. N O
ANSMITTED
IEI Title or Description of Data Transmitted
ID1 Re". NO
IC) Sheet NO.
- 0
Approval Designator IF1 Reason for Transmittal IGI E. S. 0. D or NIA 1 Approval 4 Review (see WHC-CM-3-5. 2 Release 5 Post-Review sec.12.71 3 Information 6 Dist. IRempt Acknow. Required)
~
Dose Rate Calcu la t ions f o r Strontium Fluoride
Disposition IHI & I l l 1 . Approved 4. Reviewed nolcomment 2. Approved wlcornment 5 Reviewed wlcomment 3. Disapproved Wlcomment 6 Receipt acknowledged
Capsules and Cesium Chloride Capsules and f o r such Capsules as Overpacked f o r Disposal
IGI R~~~ IJI Name IKI Signature iLI Date IMI MSlN SO"
Des ign A u t h o r i t y
. R e l a t e d EOT No.:
619209 . Purchase Order No.:
IGI IHI R ~ ~ . Diap, IJI Name IKI Signature ILI Date IMl MSlN son
. Equip./Component No.:
0. Sys tem/E ldg . /Fac i l i t y :
2. Major Assm. Dug. No.:
3 . P e r m i t l P e r m i t A p p l i c a t i o n NO.:
4 . Requ i red Response Date:
(F) Approval
Desig- "ator
b a s o n ongi-
Trans- Dispa- rn lna i sitlo"
c I
S a f e t y
I Env. I - 20. 21. DOE APPROVAL ( i f r e q u i r e d )
C t r l . No.
pproved Wcomnents
Originator for Receiving Organization
ED-7400-172-2 (05/96) GEF097
BD-7400-172-1
\>
WHC-SD-WM-TI-790, Rev. 0
Dose Rate Calculations for Strontium Fluoride Capsules and Cesium Chloride Capsules and for such Capsules as Overpacked for Disposal
R. A. Schwarz/E. H. Randklev F l u o r Danie l Northwest, Inc. , Richland, WA 99352 U . S . Department o f Energy Contract DE-AC06-96RL13200
EDT/ECN: 619209 UC: 507 Org Code: 403 Charge Code: D5222 B&R Code: EW3130010 To ta l Pages: Kid
Key Words: Cesium Ch lo r ide Capsule, St ront ium F l u o r i d e Capsules, Dose Rates, Sh ie ld ing
Abs t rac t : Th i s documents the dose r a t e c a l c u l a t i o n s f o r t h e S t ron t i um F l u o r i d e and Cesium Ch lo r ide capsules and Overpacked Capsules
TRADEMARK DISCLAIMER. Reference h e r e i n t o any s p e c i f i c comnercial product, process, o r s e r v i c e by t r a d e name, trademark, manufacturer, o r otherwise, does no t necessar i l y c o n s t i t u t e o r imp ly i t s endorsement, recornendat ion, o r f a v o r i n g by t h e Un i ted Sta tes Government O P any agency thereo f OP i t s c o n t r a c t o r s o r subcontractors.
P r i n t e d i n t h e U n i t e d Sta tes of America. To o b t a i n copies of t h i s document, con tac t : WHCIBCS Document Cont ro l Services, P.O. Box 1970. M a i l s t o p H6-OB, Rich land WA 99352, Phone (509) 372-2420; F ~ K (509) 376-6989.
Figure 1. Con f igu ra t i on f o r tube-in-tube overpack concept . . . . . . . . 8
LIST OF TABLES
Table 1. Dose Rates f o r a s i n g l e SrF, capsule w i t h a d e n s i t y o f 2 . 9 g/cc . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4
Dose Rates f o r a s i n g l e SrF, capsule w i t h a d e n s i t y o f 3.8 g/cc . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4
Dose Rates f o r 8 SrF, Capsules i n an Overpack w i t h a d e n s i t y o f 2 . 9 g / c c . . . . . . . . . . . . . . . . . . . . . . . . . 5
Dose Rates f o r 8 SrF, Capsules i n an Overpack w i t h a d e n s i t y o f 3 . 8 g / c c . . . . . . . . . . . . . . . . . . . . . . . . . 5
Dose Rates f o r 8 CsCl Capsules i n an Overpack w i t h a d e n s i t y o f 2 . 6 g / c c . . . . . . . . . . . . . . . . . . . . . . . . . 6
Dose Rates f o r 8 CsCl Capsules i n an Overpack w i t h a d e n s i t y o f 3 . 8 g / c c . . . . . . . . . . . . . . . . . . . . . . . . . 6
Table 2 .
Table 3 .
Table 4 .
Table 5.
Table 6.
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WHC-SD-WM-TI-790 R E V 0
DOSE RATE CALCULATIONS FOR STRONTIUM FLUORIDE CAPSULES AND CESIUM CHLORIDE CAPSULES AND FOR SUCH CAPSULES AS OVERPACKED FOR DISPOSAL
1.0 INTRODUCTION
Dose Rates were est imated f o r both s i n g l e and mul t ip le capsule grouping of s t ront ium f l u o r i d e capsules and a l s o f o r cesium chlor ide capsules . work was done t o support TWRS program evalua t ions of planning opt ions f o r capsule d i s p o s a l , i f they a r e eventua l ly declared waste.
Dose r a t e s were ca lcu la ted a t 1 cm and 1 m away from t h e o u t e r sur face of a s i n g l e s t ront ium f l u o r i d e (SrF,) capsule u n i t , which i s composed of two encapsulat ion b a r r i e r s , each f u l l y weld-sealed, on i n s i d e t h e o t h e r . Dose r a t e s were a l s o s i m i l a r l y ca lcu la ted r e l a t e d t o t h e outs ide sur face of a th in- walled tube-in-tube overpack conf igura t ion with a set of 8 s t ront ium f l u o r i d e capsules pos i t ioned end-to-end w i t h i n a holder tube c o n c e n t r i c a l l y loca ted along t h e ax ia l c e n t e r l i n e . This work i s an extension of t h e cesium c h l o r i d e dose r a t e c a l c u l a t i o n s i d e n t i f i e d in Reference 1. Because t h e o u t e r dimension of t h e overpack has changed s i n c e t h e re ference (cesium c h l o r i d e ) c a l c u l a t i o n s , an addi t iona l t a b l e i s included in t h i s r e p o r t updating t h e dose r a t e values f o r 8 cesium chlor ide capsules in an overpack.
This
2.0 SUMMARY
Table 1 l i s t s the dose r a t e s ca lcu la ted f o r a s i n g l e s t ront ium f l u o r i d e capsule w i t h a s a l t (SrF,) dens i ty of 2.9 g /cc . corresponding s i n g l e capsule dose r a t e s f o r a s a l t dens i ty of 3 . 8 g/cc. For overpacked capsules , Table 3 l i s t s t h e dose r a t e s ca lcu la ted f o r 8 s t ront ium f l u o r i d e capsules placed i n s i d e t h e proposed overpack with a s a l t (SrF ) d e n s i t y of 2.9 g /cc . Table 4 l i s t s t h e corresponding overpacked ca,su!e dose r a t e s f o r a s a l t dens i ty of 3 . 8 g/cc. Because t h e decay chain f o r 'Sr i s dominated by beta r a d i a t i o n emissions, t h e dose r a t e s a r e more than a f a c t o r of ten lower than t h e dose r a t e s reported in Reference 1 f o r t h e decay of 137Cs, which i s dominated by gamma r a d i a t i o n emissions.
Table 5 l i s t s t h e updated dose r a t e s f o r 8 cesium c h l o r i d e capsules i n s i d e an overpack with a s a l t (CsC1) dens i ty of 2 .6 g /cc , and Table 6 l i s t s t h e c a l c u l a t e d dose r a t e s f o r t h i s same conf igura t ion f o r a s a l t d e n s i t y of 3.8 g /cc . reported in Reference 1, but r e f l e c t t h e modified overpack diameter .
Table 2 l i s t s t h e
These updated cesium chlor ide dose r a t e s a r e s i m i l a r t o those
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WHC-SD-WM-TI-790 REV 0
Table 1. Dose Rates f o r a s i n g l e SrF, capsule w i t h a dens i t y o f 2.9 g/cc.
Locat i on I- Table 2. Dose Rates f o r a s i n g l e SrF, capsule w i t h a dens i t y o f 3.8 g/cc.
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WHC-SD-WM-TI-790 REV 0
Tab le 3 . Dose Rates f o r 8 SrF, Capsules i n an Overpack w i t h a d e n s i t y o f 2 . 9 g / c c .
Inner
Dose I Thick Location ( i n . )
Capsule
0.136
0.136
Outer Capsule
th ick ( i n . )
0.109
0.109
0.136
0.136
Dens i ty (glee)
2.90
2.90
2.90
2.90
Caosule Dose Rates tremfhr)
12/31/2000 I 12/31/2010 I 12/31/2030
Tab le 4 . Dose Rates f o r 8 SrF, Capsules i n an Overpack w i t h a d e n s i t y o f 3 .8 g /cc .
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WHC-SD-WM-TI-790 REV 0
Table 5. Dose Rates f o r 8 CsCl Capsules i n an Overpack w i t h a d e n s i t y o f 2.6 g /cc.
Table 6 .
0.095
0.103
0.103
0.136
0.136
Dose Rates for 8 CsCl Capsules i n an Overpack w i t h a d e n s i t y o f 3 .8 g/cc.
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WHC-SD-WM-TI-790 R E V 0
3.0 MODEL FOR A SINGLE STRONTIUM FLUORIDE CAPSULE
Per d iscuss ions with E . H. Randklev, two d i f f e r e n t s t ront ium f l u o r i d e d e n s i t i e s were used in t h e c a l c u l a t i o n s . A dens i ty of 2.9 g/cc (2.02 g/cc s t ront ium, 0.88 g/cc f l u o r i d e ) was used t o represent a smeared d e n s i t y a s referenced i n t h e BUSS cask Safety Analysis Report f o r Packaging (SARP). 2.9 g/cc i s 70 % of t h e o r e t i c a l dens i ty . A dens i ty of 3.8 g/cc (2.65 g/cc s t ront ium, 1.15 g/cc f l u o r i d e ) was used t o represent the actual expected d e n s i t y a s provided by re ference information from E. H . Randklev. Dose r a t e s were c a l c u l a t e d a t both 1 cm and 1 m away from t h e outer sur face of t h e o u t e r capsule envelope of t h e doubly encapsulated s a l t column. Appendix A includes t h e ISOSHIELD input f i l e s used f o r t h i s case.
The
Tables 1 and 2 l i s t t h e dose r a t e s ca lcu la ted f o r a s i n g l e s t ront ium f l u o r i d e capsule f o r two d i f f e r e n t s a l t dens i ty values . The Hanford s t ront ium f l u o r i d e capsules c o n s i s t of two m e t a l l i c encapsulat ion envelopes, one i n s i d e t h e o t h e r and f u l l y sealed by welding, both made of metal a l l o y tubing t h a t i s end capped. cy l inder 18.92 i n . (48.06 cm) long with a rad ius of 1.005 i n . (2.5527 cm) o r 0.989 i n . (2.51206 cm) depending on t h e capsule wall th ickness . Surrounding t h e s a l t column i s an inner capsule o f Hastel loy C-276 (nickel base a l l o y ) . Two cases of inner capsule wall th icknesses were modeled; namely a minimum th ickness of 0.12 i n . (0.3048 cm) and a maximum th ickness of 0.136 i n . (0.34544 cm) Surrounding t h e inner capsule i s an outer capsule made of 316 s t a i n l e s s s t e e l . capsule were modeled only as t h e minimum th ickness o f 0.109 i n . (0.27686 cm) and a maximum th ickness of 0.136 i n . (0.34544 cm), f o r t h i s a n a l y s i s .
The s i n g l e s t ront ium f l u o r i d e s a l t column was modeled a s a
The t h r e e generat ions of wall th ickness f o r t h e o u t e r
The Has te l loy C-276 was modeled as 6.6639 g/cc n i c k e l , 0.4443 g/cc i r o n , 1.4216 g / c c chrome and 0.3554 g/cc tungsten f o r a t o t a l dens i ty of 8.885 g/cc (0.321 l b s / c c ) The 316 s t a i n l e s s s t e e l a l l o y f o r t h e o u t e r b a r r i e r of t h e Hanford SrF capsules was modeled as having a composition of 1.106 g/cc n i c k e l , 5.352 g/cc i ron and 1.422 g/cc chrome and a d e n s i t y of 7.90 g/cc.
4.0 MODEL FOR 8 STRONTIUM FLUORIDE CAPSULES IN AN OVERPACK
Figure 1 provides a general i l l u s t r a t i o n (Randklev) of t h e capsule loaded overpack design concept t h a t was used in these analyses . 4 l i s t t h e dose r a t e s ca lcu la ted f o r 8 st ront ium f l u o r i d e capsules placed end- to-end i n a thin-wal led s t a i n l e s s s t e e l tube-type overpack des ign . conf igura t ion , t h e s a l t column of s t ront ium f l u o r i d e i s modeled as a cy l inder with a rad ius of 1.005 i n . (2.5527 cm) o r 0.989 i n . (2.51206 cm) depending on t h e capsule wall th ickness . Surrounding the s a l t column i s an inner capsule of Has te l loy C-276 (Nickel base a l l o y ) with a minimum th ickness of 0.12 i n . (0.3048 cm) and a maximum th ickness of 0.136 i n . (0.34544 cm) Surrounding t h e inner capsule i s an outer s t a i n l e s s s t e e l capsule , which was modeled a s a minimum th ickness of 0.109 i n . (0.27686 cm) and a maximum th ickness of 0.136 i n . (0.34544 cm), from the s e t of t h r e e generat ions of tubing design.
Tables 3 and
For t h i s
7
0 Capsules Per Overpack (max.)
CsCl Capsules 8 SrF2 Capsules Will Be In Separate Overpack Units
* c 5 (D
0 < H96030154.3
W m < 0
WHC-SD-WM-TI-790 R E V 0
Surrounding t h e s t r i n g of e i g h t capsules , posi t ioned end-to-end, i s a 3 . 0 i n . OD, 0.25 i n . t h i c k s t a i n l e s s s t e e l tube t h a t i s pos i t ioned down t h e ax ia l c e n t e r l i n e of th is overpack. This tube i s then surrounded by t h e o u t e r s h e l l of t h e overpack, which c o n s i s t s of a 24 i n . OD, 3/8 i n . t h i c k s t a i n l e s s s t e e l tube , which i s c losed w i t h weld-sealed caps a t both ends (Randklev 1996b) .
Because t h e ISOSHIELD code can only model a t most 5 " s h i e l d s " ( i . e . r a d i a t i o n sh ie ld ing b a r r i e r s ) , t h e above geometry was modeled w i t h t h e fol lowing 5 choices f o r t h e "sh ie lds" . Shield 1 i s t h e source region ( i . e . s a l t column) with a minimum radius of 0.989 i n . (2.51206 cm) and a maximum radius of 1.005 i n . (2.5527 cm). Shield 2 i s t h e Hastel loy C-276 ( i n n e r capsule b a r r i e r ) w i t h a minimum wall- thickness of 0.12 i n . (0.3048 cm) and a maximum wall- thickness of 0.136 i n . (0.34554 cm) ( i . e . , per t h e two genera t ions of capsule tubing des ign) . th ickness opt ions were taken from t h e Washburn (1989) re ference , and were a l s o used in performing t h e dose r a t e c a l c u l a t i o n s reported in t h e Schwarz (1995) re ference . Shie ld 3 i s modeled a s a s t h e dimensional combination of t h e r e s p e c t i v e wall th icknesses of two 316 s t a i n l e s s s t e e l components of t h e overpacked capsule conf igura t ion . Shield 3 combines the o u t e r capsule wall and t h e 0 .25 i n . t h i c k (capsule) holder tube of t h e thin-wal led overpack design concept (Figure 1 ) . in . (0 .109 i n . + 0.25 i n . ) (0.91186 cm) and a maximum th ickness of 0.386 i n . (0.136 i n . t 0.25 i n . ) (0.98044 cm), where t h e 0.109in. and 0.136 i n . values represent t h e f i r s t and t h i r d generat ions of ou ter capsule tubing design, r e s p e c t i v e l y , f o r t h e t h r e e generat ions used in such Hanford capsule product ion. (25.68956 cm) and a maximum th ickness of 10.141 i n . (25.75814 cm). Shie ld 5 i s a 316 s t a i n l e s s s t e e l s h i e l d ( i . e . ou ter wall of t h e overpack) with a th ickness of 0.375 i n . (0.9525 cm).
s i n g l e capsule case as discussed in Sect ion 3.0. a t 1 cm and 1 m away from e x t e r i o r sur face of t h e o u t e r b a r r i e r of t h e overpack.
The dimensions f o r the capsule wall
Shield 3 has a minimum th ickness of 0.359
Shie ld 4 i s an a i r gap with a minimum th ickness of 10.114 i n .
The " s h i e l d " mater ia l compositions a r e t h e same as those assumed f o r the Dose r a t e s were c a l c u l a t e d
The ISOSHIELD input f i l e f o r t h i s case i s l i s t e d i n Appendix 8.
5 .0 MODEL FOR 8 CESIUM CHLORIDE CAPSULES I N AN OVERPACK
Tables 5 and 6 l i s t t h e dose r a t e s ca lcu la ted f o r 8 cesium c h l o r i d e capsules placed i n t h e proposed overpack. Again, r e f e r t o Figure 1 ( Randklev) f o r a general i l l u s t r a t i o n of t h i s design concept. For t h i s conf igura t ion , t h e cesium chlor ide s a l t column i s modeled as a c y l i n d e r with a nominal rad ius of 1.03 i n . (2.6162 cm), 1.022 i n . (2.59588 cm) o r 0.9915 i n . (2.51841 cm) depending on the respec t ive wall th ickness of the t h r e e genera t ions of s t a i n l e s s s t e e l tubing used during t h e production h i s t o r y (Washburn, 1989). Surrounding t h e s a l t column ( r a d i a t i o n source) region i s an inner and an o u t e r set of 316 s t a i n l e s s s t e e l tubes with each tube capped and f u l l y sea led by welding. The capsules a r e encased i n a 3.0 i n . OD, 0.25 i n . t h i c k s t e e l tube . This tube i s then surrounded by t h e outer s h e l l l a y e r of
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WHC-SD-WM-TI-790 REV 0
the overpack which i s s t a i n l e s s s t e e l t u b i n g t h a t i s 24 i n . OD, and 3/8 i n t h i c k .
Because the ISOSHIELD code can on ly model up t o 5 " s h i e l d s " ( i . e . r a d i a t i o n s h i e l d i n g b a r r i e r s ) , t he above geometry was modeled w i t h t h e f o l l o w i n g 4 choices f o r t h e "sh ie lds " . Sh ie ld 1 i s t h e source r e g i o n ( i . e . s a l t column) w i t h a rad ius o f 1.03 i n . (2.6162 cm), 1.022 i n . (2.59588 cm) o r 0.9915 i n . (2.51841 cm). Sh ie ld 2 i s composed o f t h ree s t a i n l e s s s t e e l components o f t h e overpacked capsules, as viewed i n a r a d i a l cross-sect ion; namely, t h e i n n e r and o u t e r capsule b a r r i e r t u b i n g w a l l s p l u s t h e th i ckness of t he capsule ho lde r tube component o f t he overpack des ign. . Hence S h i e l d 2 i s a s t e e l m u l t i - l a y e r e d s h i e l d w i t h a combined th i ckness o f 0.454 i n . (0.095 i n . t 0.109 i n . t 0.25 i n . ) (1.15316 cm), 0.472 i n . (0.103 i n . t 0.119 i n . t 0.25 i n . ) (1.19888 cm) o r 0.522 i n . (0.136 i n . t 0.136 i n . t 0.25 i n . ) (1.32588 cm). S h i e l d 3 i s an a i r gap w i t h a th i ckness o f 10.141 i n . (25.75814 cm), 10.131 i n . (25.73274 cm), o r 10.1115 i n . (25.68321 cm), which correspond t o such gap dimensioning when adjusted, respec t i ve l y , f o r t he t h r e e generat ions o f capsule t u b i n g w a l l design. Sh ie ld 4 i s t he w a l l t h i ckness f o r t h e o u t e r s h e l l o f t h e s t a i n l e s s s t e e l overpack design, and i s nomina l l y 0.375 i n . (0.9525 cm) t h i c k .
l e v e l s ( i . e . 3.8 g/cc and 2.6 g/cc) t o approximate t h e nominal smear dens i t y , i n c l u d i n g t h e range above and below a s o l i d s t a t e CsCl phase t rans fo rma t ion , which i s a l so mod i f i ed by se lected i m p u r i t i e s . tubes o f t h e cesium c h l o r i d e capsule des ign are made o f 316 s t a i n l e s s s t e e l . Dose r a t e s were c a l c u l a t e d a t 1 cm and 1 m away from t h e ou ts ide o f t he overpack. The ISOSHIELD i n p u t f i l e s ( i . e . 1 f i l e f o r each o f t h e two d e n s i t y assumptions) f o r these cases are l i s t e d i n Appendix C .
The cesium c h l o r i d e r a d i a t i o n source was a l so modeled f o r two d e n s i t y
Both o f t h e encapsulat ion
6.0 SOURCE DESCRIPTION
The capsule rad io i so tope inven to ry sources f o r t he dose r a t e analyses r e s u l t s i n Tables 1 through 3 were obta ined from Randklev (1996b) f o r decay t imes o f 12/31/2000, 12/31/2010 and 12/31/2030. Dose r a t e s were c a l c u l a t e d a t each decay t ime f o r both the average and maximum est imates o f capsule i n v e n t o r y ( K i l o c u r i e s ) and f o r t he maximum and minimum capsule w a l l th icknesses.
7.0 CALCULATION
A l l c a l c u l a t i o n s were done us ing the ISOSHIELD computer code (Reference 3), t h e "bu i l dup f a c t o r " ( i . e . f a c t o r t o account f o r c o l l i s i o n s w i t h i n t h e sh ie lds ) pr imary s h i e l d i n g m a t e r i a l was s p e c i f i e d f o r t h e l a s t ( s t e e l ) s h i e l d l a y e r r a d i a l l y outward from t h e cen te r o f t h e capsule, across t h e r a d i a l cross sec t i on , f o r t h e two general ana lys i s cases ( i . e . both s i n g l e capsule and overpacked capsule) . The ANSI/ANS(1991) f l uence t o dose convers ion f a c t o r s were used i n c a l c u l a t i n g t h e dose r a t e s w i t h t h e assumption t h a t t he r a d i a t i o n
10
WHC-SD-WM-TI-790 REV 0
i s e n t e r i n g t h e body assuming an a n t e r i o r - p o s t e r i o r o r i e n t a t i o n ( i . e . f r o n t t o back).
8.0 REFERENCES
ANSI/ANS, 1991, ANSI/ANS-6.1.1-1991, "Neutron and Gamma-Ray Fluence-to-Dose Factors , " American Nuclear Society .
Randklev, E . H., 1996, In formal Memorandum t o Randy Schwarz, Eldon Cramer, , "Watts/Capsule and Ki locur ies/Capsule f o r Cesium Ch lo r ide Capsules and S t ron t i um F l u o r i d e Capsules Estimated Per a Set o f Decay Dates and I n s t r u c t i o n s on Which Dates t o Use i n Your Analys is" , dated September 20, 1996.
Randklev, E. H., 1994, pe r T. J . Coates t o E. H. Randklev l e t t e r t r a n s m i t t a l ( A p r i l 8, 1994) o f Haynes Corp. C-276 A l l o y - Product B u l l e t i n (H-2002B ; 111891), Haynes I n t e r n a t i o n a l , I nc . , Kokomo, Ind iana, 46904 . Rittman, P. D.,1995, " I S O - P C Vers ion 1.98 - User 's Guide," WHC-SD-WM-UM-030, Rev. 0, 1995, Westinghouse Hanford Company, Richland, WA 99352.
Schwarz, R. A., 1995, L e t t e r Report t o E. H. Randklev, "Dose Rate C a l c u l a t i o n s f o r CsCl Capsules", 8M730-RAS-95-003, dated June 2, 1995, Westinghouse Hanford Company, Richland, WA 99352.
Washburn, D. F., 1989, " I n t e r i m Report: Resolut ion o f Specia l Form Issues Associated w i t h Cesium Ch lo r ide Capsules Manufactured a t WESF," SD-WM-DIC-004, EDT 461236, Westinghouse Hanford Company, Richland, Washington, 99352.
(See APPENDIX D f o r a copy.)
11
WHC-SD-WM-TI-790 REV 0
Appendix A. ISOSHIELD I n p u t F i l e f o r 1 Stront ium F l u o r i d e Capsule.
0 2 Dose Rats SRF2 with a density of 2.9 glcc One capsule. MIN DEN. MIN STEEL, AVG SRC. 2000 &Input N e a r 1. Option= 1. Dunit=l. Iconc=O.
lgeom= 7. Slth= 48 06. Y=24.03. Npsi=100. Nthotil= 100. Del,= 0.1, X I l I = 4.33375. 103.33375. Nshid= 4. Jbuf= 4. T111=2.5527. T121=0.3048. Tl3l=0.19939. TI41 = O 27686. Weight1821 =33390, Weight1841 =33390 &
sr 18 2.02 F 24 0.88 Ni 10 66639 1.106 Fe 9 0.4443 5.372 Cr 34 14216 1.422 W 13 0.3554
1 Air 3 0.00129 Ons CapwIe MIN DEN. MAX STEEL, AVG SRC. 2000 &Input Next= 4. T111=2 51206. T12)=0.34544. T131=0.13081. T141=0.34544 &
One Capsule MAX DEN, MAX STEEL, AVG SRC. 2000 &Input Next= 1 & SI 18 2 6 5 F 24 1.15 Ni 10 66639 1.106 Fe 9 0.4443 5.372 Cr 34 1.4216 1.422 W 13 0.3554
1 Air 3 0 001 29 One Capsule MAX DEN, MIN STEEL, AVG SRC. 2000 &Input Next= 4, TIll=2.5527. T12l=0.3048, T131=0.19939, T141=0.27686 &
END OF RUN &InputNext= 6 &
A- 1
WHC-SD-WM-TI-790 REV 0
Appendix B. ISOSHIELD Input File for 8 Strontium Fluoride Capsules.
0 Eight Capsules MAX DEN, MIN STEEL, AVG SRC. 2000 &Input Next= 1. Option= 1. Dunit=l. Iconc=O.
Appendix D.--Copy o f Randklev (1996) reference--Informal Memorandum
D- 1
1
DON'T SAY IT --- W r i t e It! DATE: Sept. 20, 1996
TO: Randy Schwarz/WHC HO-35 FROM: Ed Randklev/WHC H5-27
Telephone: 376-1456 E l don Cramer/WHC HO-34
C C : V i c t o r Roetman HO-35 EHR f i l e
Watts/Capsule and Ki locur ies/Capsule f o r Cesium Ch lo r ide Capsules and Stront ium F l u o r i d e Capsules Estimated Per a Set o f Decay Dates and I n s t r u c t i o n s on Which Dates t o Use i n Your Analyses
SUBJECT:
Randv Schwarz: Rad ia t i on Analvs is Work - (Cey> j*s\%;, o c ~ L L ) 1. Cesium Ch lo r ide Capsule Analyses:
a. Please no te t h a t I am now i n t e r e s t e d i n an e a r l i e r s t a r t da te (per new in fo . on d isposal process ing scenar ios) than t h e 2010 da te I noted i n my l e t t e r o f 8/30/96. i n t e r e s t f o r moving and process ing such capsules pe r some o f t h e scenar io op t i ons . ma t te rs f o r t he MCNP decay energy depos i t i on p r o f i l e problem you are ana lyz ing ( i . e . , what you g e t f o r an answer pe r a 2010 decay da te w i l l be t h e same). See Attachment I f o r t he CsCl capsule values f o r severa l decay dates.
b. I am now i n t e r e s t e d i n knowing what the est imated dose r a t e s w i l l be f o r a s i n g l e capsule and an overpack f i l l e d w i t h 8 capsules ( i . e . , l i k e what was done i n FY-95 f o r me f o r t h e decay years o f 2010 and 2035). Again, c o r r e c t me i f I am wrong, bu t I am assuming t h a t I can s u i t a b l y est imate t h e dose r a t e values I need f o r t he 2000 decay date, and 2030, by j u s t p r o p o r t i o n a l l y a d j u s t i n g the FY-95 values r e l a t i v e t o the kCi /capsule values ( i . e . , we do n o t need t o f o r m a l l y r u n t h i s case i n t h e code). Please l e t me know your recommendation.
c. A t present I do n o t t h i n k you have need f o r t he decay values f o r 2035 t h a t I p u t i n my l e t t e r o f 8/30/96. Th is s i t u a t i o n w i l l on l y be r e l e v a n t t o t h e thermal ana lys i s work t h a t Eldon Cramer w i l l be doing.
d. I am s t i l l somewhat concerned about the s a l t d e n s i t y va lue t h a t you use i n your analyses. I can see where the "smeared" d e n s i t y va lue used i n t h e pas t s h i e l d i n g c a l c u l a t i o n s (per r e f . t o SARP work on BUSS cask) w i l l y i e l d conserva t i ve dose r a t e values. However, f o r MCNP and t h e energy d e p o s i t i o n p r o f i l e , g i ven ou r pr imary concern about sa1t:metal i n t e r f a c e temperatures, I am concerned about any use o f such a "smeared" d e n s i t y va lue i n MCNP. To what ex ten t i s MCNP even s e n s i t i v e t o t h e d e n s i t y va lue used f o r t he s a l t ? ACTION/Randy: Get back t o me on t h i s one.
Please do the dose r a t e determinat ions f o r t h e decay years o f 2000, 2010 and 2030 f o r a s i n g l e capsule (max. and ave. i n v e n t o r i e s ) and an overpacked se t o f 8 capsules (max. and ave. i n v e n t o r i e s ) .
Namely, 2000 i s now the e a r l i e s t s t a r t da te o f
Please l e t me know i f I am wrong, b u t I do NOT t h i n k t h i s
2. S t ron t i um F l u o r i d e Capsule Analyses: a.
A-3000.723 (01/95) GEF014 E- I
CESIUM CAPSULES (1328)
Act iv i ty
Maximum Wattage
Average Wattage
Minimum Wattage
*Does not i n c l u d e t r a c e r capsu le S-2. Actua l number o f capsules cou ld be as h igh as 636.
CHECKLIST FOR INDEPENDENT TECHNICAL REVIEW NUMBER:WHC-SD-TI-790 Rev 0 DOCUMENT REVIEWED Dose Rate Calculations for Strontium Fluoride Caosules and Cesium Chloride Caosules and for such CaDsules as Overoacked for Disposal AUTHOR(s)Randolph Schwarz
I . Method(s) of Review
( X ) Input data checked for accuracy ( X ) Independent calculation performed
( ) Hand calculation ( X ) Alternate computer code: MCNP
( ) Comparison to experiment or previous results ( ) Alternate method (define)
11. Checklist (either check or enter NA if not applied)
( X ) Task completely defined ( X ) Activity consistent with task specification ( X ) Necessary assumptions explicitly stated and supported ( X ) Resources properly identified and referenced ( X ) Resource documentation appropriate for this application ( X ) Input data explicitly stated ( X ) Input data verified to be consistent with original source ( X ) Geometric model adequate representation of actual geometry ( X ) Material properties appropriate and reasonable (NA ) Mathematical derivations checked including dimensional consistency (NA ) Hand calculations checked for errors ( X ) Assumptions explicitly stated and justified ( X ) Computer software appropriate for task and used within range of
(NA ) Use of resource outside range of established validity is justified ( X ) Software runstreams correct and consistent with results ( X ) Software output consistent with input (NA ) Results consistent with applicable previous experimental or
analytical findings ( X ) Results and conclusions address all points and are consistent with
task requirements and/or established limits or criteria ( X ) Conclusions consistent with analytical results and established
limits (NA ) ( ) Other (define)
validity
Uncertainty assesment appropriate and reasonable
111. Comments:
IV. REV1EWER:Victor Roetman Mw~ DATE: Ll / \%[db
DISTRIBUTION SHEET To I From I Page 1 of 1 D i s t r i b u t i o n I C r i t i c a l i t y and Shielding Date
November 13, 1996 Project T i t l d W o r k Order I EDT No. 619209 Dose Rate Calcu la t ions f o r Strontium Fluoride Capsules and Cesium Chloride Capsules and f o r such Capsules as Overpacked f o r Disposal
ECN No.
R . D . Claghorn H5-49 X
E. R . Cramer HO-34 X
J . Greenborg HO-35 X
E . H. Randklev H5-27 X
V . E . Roetman HO-35 X
R . A. Schwarz K8-34 X
Central F i l e s ( 1 + Orig ina l ) AS-a8 X
Name
A-6000-135 (01/93) UEF067
T e x t T e x t Only At tach. / EDT/ECN M S l N W i t h All Appendix Only