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Additional resources for Postirradiation Examination, Analysis of Performance of HFIR Fuel Elements
14. Comparison Between Oxidk Spalling P a t t e r n s on Fuel P l a t e s from Element 5-0 with t h e Predicted Oxide Thickness P a t t e r n f o r an Outer Annulus HFIR Fuel P l a t e . ~ ~ 28 Fig. 15. Typical Appearance of Fuel P l a t e s from HFIR Fuel Element 21-0. The dark, p a r a l l e l l i n e s on t h e convex surfaces of t h e s e f u e l p l a t e s a r e r u s t s t a i n s from s e c t i o n s of a s t e e l t a p e used a s p o s i t i o n i n d i c a t o r s during disassembly of t h i s f u e l element and not an i r r a d i a t i o n e f f e c t .
003 i n . deep). Although not r e a d i l y apparent a t lower magnifications shown i n Appendix E, the microstructure of the U308-aluminum fuel dispersion v a r i e d considerably along and across eLch of t h e t h r e e i r r a d i a t e d f u e l plates. These d i f f e r e n c e s a r e perhapsimore c l e a r l y shown i n Fig. 31, I which compares t h e m i c r o s t r u c t u r e of t h e f u e l d i s p e r s i o n of an u n i r r a d i a t e d HFIR f u e l p l a t e w i t h t h a t from khe low-burnup, low-temperature and high-burnup, high-temperature regions.
Such hardness i n c r e a s e s a r e probably p r i m a r i l y a r e s u l t of fast neutron displacement-type damage. These hardness i n c r e a s e s a r e probably 12W. K. Barney and B. D. Wemple, Metallography of I r r a d i a t e d U02Containing Fuel Elements, KAPL-1836 (June 1 9 5 6 ) . 70 . 80 - I 'SPECIMEN BURNUP (x4o20)] [fissions/cm3 I 60 NOMINAL CLADDING IRRADIATION TEMPERATURE 1°C) E f f e c t of I r a a d i a t i o n Temperature upon t h e Extent o:t"Reaction i n t'rle Cores o f t h e Inner (Top) and Outer (Bottom) Annulus H F I R Fuel P l a t e s .