Fuel adjacency effects on fast reactor cladding mechanical properties. [LMFBR]
Description:
Simulated transient tests were conducted on 234 cladding specimens from EBR-II irradiated mixed oxide fuel pins; approximately 75% of the specimens were from the fuel column region, with the remainder from the plenum and below the fuel column. The cladding specimens were taken from the N-E, N-F,, PNL-9, PNL-10, PNL-11, P-23A, P-23B, P-23C, and WSA-3 fuel pins irradiated at 15.2 to 37 KW/cm to burnup levels from 11 to 110 MWd/Kg. All the fuel pins used 20% cold worked Type 316 stainless steel cl…
more
Date:
December 6, 1978
Creator:
Hunter, C. W. & Johnson, G. D.
Item Type:
Refine your search to only
Article
Partner:
UNT Libraries Government Documents Department