URANIUM FUEL REPROCESSING BY THE FLUORIDE DISTILLATION METHOD (in Czech)
Journal Article
·
· Jaderna energie
OSTI ID:4163371
Methods are described for reprocessing irradiated nuclear fuel by fluoride distillation. A methcd operating at 120 deg C using BrF/sub 3/ as fluorination agent, a high temperature methcd operating in fused salts NaF + ZrF/ sub 4/, and a methcd using fluidization techniques for prcduction of UF/sub 6/ are described. (auth)
- Research Organization:
- Inst. of Nuclear Research, Czechoslovak Academy of Sciences, Prague
- NSA Number:
- NSA-14-021586
- OSTI ID:
- 4163371
- Journal Information:
- Jaderna energie, Journal Name: Jaderna energie Vol. Vol: 6
- Country of Publication:
- Country unknown/Code not available
- Language:
- Czech
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