Annual Progress Rpt - Fuel Element development [1962]

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I W U z e9 26 Plate 6 Plate 7 Plate 8 Plate 9 PPCO . c - 4 3 1 2 Contour Figure 3 l b . P l a t e IO Numbers Show % O f U-235 Fissioned Burnout P a t t e r n of ETR F u e l Element u-620 P l a t e s - 36 - \ \ \ \ \ \ \ \ I I I I I I I Plate I I Plate I2 Plate 13 Plate 14 Plate 15 PPco-c-4111 Contour Figure 31 c . Numbers Show % O f U-235 Fissioned Burnout P a t t e r n o f ETR F u e l Element u-620 P l a t e s , - 37 - I 0 tt M co I W a P W W I W I I W N W 0 I I N W I N I N I I I P N- N m 8 I DISTANCE FROM TOP OF PLATE (Inches) 01 N 0 I N I I e I W N I e I m I 0 0 1 IO 2-12- 4 - -14\ 16- 6- c\ 18 \8 o2---- / IO - YZ2\ 12 - 14 - 5 -- I 16- W t 2 18 0 LL iE : I- 20 r t W 222- E a 24 - 26 - 28 - 30 - PPCO - E - % , , Plate 2 Plote Contour Figure 32 a .

0 cc H f . An u n i r r a d i a t e d sample w a s prepared i n t h e same manner f o r comparison. The samples were examined and photomicrographs obtained i n t h e a s - p o l i s h e d and etched c o n d i t i o n s on t h e l i g h t microscope. 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 .

Ll) It is observed when burnup on the order of 50 a/o of the uranium are achieved. 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.

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