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Additional resources for Annual Progress Rpt - Fuel Element development 
This rim has never been identified but may result from segregation of fission-product oxides out of the U02. , the U02 particles appear to have been liquid. The irradiation temperatures for the U02-A1 dispersions were low, x 300°F. " 3. Gamma Scanning of Fuel Plates It has long been of interest to determine just how closely the fuel burnout f o l l o w e d the vertical neutron f l u x distribution measured by flux wires in the water channels between the fuel plates. Particularly of interest is the flux peaking measured at the lower end of the fuel element and which is usually the basis for locating the hot spot in this area.
3 w/o U 08 i n A1 Cermet, I r r a d i a t e d t o 54% Burnup, and Post-Irra&ationAnnealed a t 500'F for 3 hours. 006 P- A s Polished Figure 17 500 x M i c r o s t r u c t u r e of 32 w/o U02 i n A 1 Cermet, as F a b r i c a t e d . 006 A s Polished 520 x Figure 18 Microstructure o f 42 w/o U02 i n A1 Cermet, Heat Treated 40 Hours a t 1110" F. 8 w/o UO2 i n A1 Cermet, I r r a d i a t e d t o 30% Burnup. 006 A As Polished 500 x Figure 20 Microstructure of 24 w/o U 0 2 in A1 Cermet, Irradiated to M-716 8-17 45% Burnup.
The f a b r i c a t e d p o edures used t o produce t h i s p l a t e have been d e s c r i b e d i n ID0 16727f 2 7 The p l a t e had been i r r a d i a t e d t o a burnup of 50% of t h e o r i g i n a l U-235. The r e s u l t s of t h i s i n v e s t i g a t i o n a r e summarized i n t h e f o l l o w h g e x c e r p t s from t h e BMT r e p o r t ( 9 ) . "The i r r a d i a t e d f u e l p l a t e w a s examined and s e c t i o n e d f o r metallographic examination. The sample was mounted f l a t i n "Hysol" p l a s t i c and w a s ground t o t h e c e n t e r l i n e on 600 g r i t S i c paper.
Annual Progress Rpt - Fuel Element development