Annual Progress Rpt - Fuel Element Development [1961] by PDF

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However, e x t r a p o l a t i o n of t h e s e r e a c t i v i t y responses t o give t h e response i n some h y p o t h e t i c a l measurement c o n d i t i o n i s n o t p a s s i b l e because of t h e l i m i t e d range of measurement c o n d i t i o n s a v a i l a b l e i n t h e RMF's h i g h l y t h e r m a l i z e d c e n t e r h o l e . An RME' l a t t i c e p o s i t i o n would be n e c e s s a r y t o approximate MTR c o n d i t i o n s ; a t t h e p r e s e n t time, t h i s i s impossible.

He MTP, canal a f t e r b e i n g ir-ediated f o r various periods. All p l a t e s c o n t a i n I 8 W t $ U-AI.. alloy cores. c € Unirradiated I 8% U235 Burnup A. e 35% U235 Burnup 20% U235 Burnup 50% U235 Burnup 6061 Al Alloy Cladding P a I L B. APM M257 A1 Alloy Cladding Figure 21 Appearance after Irradiation of Two A1 Alloy Claddings on Fully-Enriched, 45 wt$ U - A l Alloy Cores 20% '$35 8% U235 Burnup A. 18 w t $ U-A1 Alloy Core B. 32 w t $ U-A1 A l l o y Core C F i g u r e 22 Burnup . 98 30 380 37 5 Cladding Matrix Particle The photomicrographs o f specimens from 18 weight p e r c e n t UAl a l l o y f u e l which were i r r a d i a t e d t o 51% and 69% U235 burnup are shown i n Figure 23.

The burnups o f some i r r a d i a t e d p l a t e s were r e - c a l c u l a t e d u s i n g f l u x i n o b t a i n i n g flux p e r t u r b a t i o n These burnups a r e p r e s e n t e d i n Table '1. t h e v a l u e s of position-dependent factors. P r e l i m i n a r y c a l c u l a t i o n s have been made t o c o r r e c t f o r f l u x d i s t r i b u t i o n s i n t h e d i r e c t i o n p a r a l l e l t o t h e f u e l p l a t e f a c e (right a n g l e s t o t h e h o r i z o n t a l d i r e c t i o n used i n t h e computations) and a l s o v e r t i c a l l y through t h e s e t o f e i g h t h o l d e r s .

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Annual Progress Rpt - Fuel Element Development [1961]


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