NUCLEAR SAFETY CRITERIA FOR U$sup 233$-ALLOY FUEL FABRICATION
Technical Report
·
OSTI ID:4627111
Safety criteria are presented for the handling of U/sup 233/ in finely divided fuel, unmoderated U/sup 233/ fuel systems, and water. These criteria are compared with those for U/sup 235/ fuels. It is estimated that the maximum safe batch size of contained U/sup 235/ is 1/3 to 1/2 that for the corresponding U/sup 235/ fuels, depending on the fuel form, size, and degree of water moderation and reflection. For finely divided systems of fuel and water, the maximum safe batch size for U/sup 235/ 250 g compared to 350 g for U/sup 235/ fuels. It is stressed that all fuel-handling operations, in which unclad fuel is involved, should be conducted in hoods. (C.H.)
- Research Organization:
- Atomics International. Div. of North American Aviation, Inc., Canoga Park, Calif.
- DOE Contract Number:
- AT(11-1)-GEN-8
- NSA Number:
- NSA-17-039289
- OSTI ID:
- 4627111
- Report Number(s):
- NAA-SR-Memo-8915
- Country of Publication:
- United States
- Language:
- English
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