POST-IRRADIATION EXAMINATION OF CORED, EDGE LOADED, THORIA-URANIA NUCLEAR FUEL
Technical Report
·
OSTI ID:4789713
In a program devoted to development of a reactor fuel capable of operating at high heat flux, specific power, and burnup, three edge-loaded thoria- urania nuclear fuel samples were assembled into a capsule, irradiated to approximately 2000 Mwd/t at a maximum surface heat flux of 10/sup 6/ indicated good fuel stability even in samples whose cladding had ruptured. The circumferential ruptures appeared to be caused by stresses induced from cycling of longitudinal thermal gradients in the stainless cladding material. This irradiation was the first of a series to develop thoria-urania fuel for high heat flux, specific power, and burn-up operation in a sodium graphite reactor. (auth)
- Research Organization:
- General Electric Co. Vallecitos Atomic Lab., Pleasanton, Calif.
- NSA Number:
- NSA-16-029370
- OSTI ID:
- 4789713
- Report Number(s):
- GEAP-3216
- Country of Publication:
- United States
- Language:
- English
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