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Extra resources for Core Fuel Systems fora Fast Breeder Power Reactor
A l s o , t h e n u m b e r of f i s s i o n s p e r ur:mium-235 a t o m d e s t r o y e d does not v a r y with burnup. The plutonium-240 content could b e neglected i n all but t h e final economics. Consistent with Item (a) above, it i s a s s u m e d t h a t t h e c o r e i s at s o m e e q u i l i b r i u m condition s u c h t h a t e a c h element is loaded with e x c e s s f u e l initially, a n d t h e a v e r a g e amount of f u e l i n t h e c o r e at any time is j u s t t h e calculated c r i t i c a l mass.
A l l of the components will be vapor d e g r e a s e d , washed, and a s s e m b l e d i n a j i g . The a s s e m b l y will b e e n c l o s e d i n a light s t a i n l e s s s t e e l container which will be evacua t e d and s e a l e d . The s e a l e d a s s e m b l y will then be subjected to a h e l i u m p r e s s u r e of 1 0 , 0 0 0 p s i at an elevated t e m p e r a t u r e . T h e components Wit1 b e a s s e m b l e d a s shown i n F i g u r e 15. After p r e s s u r e bonding, the s t a i n l e s s envelope will be s t r i p p e d and the Ti-Name1 s t r i p s will be pickled p r e f e r e n t i a l l y t o f o r m channels i n the a s s e m b l y .
O molybdenum L1-2 Cerainic plates(b) (see Figure 23, 90 per c e n t dense U02 ne-3 C erainic pins (see Figure 3), 90 per cent dense UO2 pellets -~ G2-6 616 G16 616 23 1291 3516 3511 1259 17 529 1256 . OS3 . os1 . - (a) Estimated. (b) Estimated; accouiits for b u n u p . (c) Leaks fissioii gas to coolant. R A T T E L L E M E M 0 R I A L. I N S T I T U T E 47 CALCULATIONS FOR APDA CORE I1 D, in. __- w1, in. w2, in. Plate(") Uranium -238/ Uranium-235 Ratio ~--_-____ Uranium - 238/ Uranium -235 Ratio(a) in YO2 ~ _ Uraniiim-238/ Uranium -235 Ratio(a) in Uranium-10 w/o hlolybdenuin _ __ Initial@) Uranium - 2 3 5 Loading, kg __-.