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Extra resources for Annual Progress Rpt - Fuel Element development 
Figures 24, 25, and 26 i l l u s t r a t e t h e appearance of t h e m a t e r i a l i n t h e u n i r r a d i a t e d condition, i n t h e i r r a d i a t e d asp o l i s h e d condition, and i n t h e i r r a d i a t e d etched c o n d i t i o n , r e s p e c t i v e l y . The p o r o s i t y i n t h e U02 as shown i n Figures 25 and 26 i s probably due t o f i s s i o n gas agglomeration and i n d i c a t e s t h a t t h e U02 has r e c e i v e d a r e l a t i v e l y high burnup. Two d i s t i n c t l a y e r s between t h e U02 and aluminum a r e apparent b o t h i n t h e a s - p o l i s h e d and as-etched s t r u c t u r e s , I n t h e a s - p o l i s h e d c o n d i t i o n a dark l a y e r l i e s immediately a d j a c e n t t o t h e U02 with a l i g h t - a p p e a r i n g l a y e r v i s i b l e o u t s i d e t h i s .
Burnout P a t t e r n o f MTR F u e l Element C-423 P l a t e s . - 47 - 0 2 Id 1 4 -18- 6 -20- 8 v) ” W c :IC + \ W l- a J LI U 0 ;12 + - a 0 U IL W g I4 2 - -- Y D I€ I€ /-- c 2c /24 2; 2L Plate Plate 6 7 i’ Plate Plate 8 34 b. IO PPCo - B - 4 3 0 8 Contour Figure Plate 9 Numbers Burnout P a t t e r n of MTR F u e l Element - 48 - Show % Of U - 2 3 5 Fissioned C-423 P l a t e s , y' I -14--1 -4 -I6\ 4 J4 i' 22 PPto - 8 - 4 3 0 9 Plate I I Plate 12 P l a t e 13 Contour Figure 34 c . P l a t e 14 Plate 15 Numbers S h o w % O f U-235 Ftssioned Burnout P a t t e r n of MTIi F u e l Element C-423 P l a t e s .
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.