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PRODUCTION OF PLUTONIUM 239

Patent ·
OSTI ID:4216352
;
A graphite- and heavy-water-moderated reactor is described in which Pu/ sup 239/ and U/sup 233/ can be produced. The liquid UF/sub 6/ fuel is circulated through a graphite moderator. The circulation system has means for heat removal and bleeding or adding UF/sub 6/. The UF/sub 6/ removed is continuously processed for Pu and fission product separation. (T.R.H.)
Research Organization:
Originating Research Org. not identified
NSA Number:
NSA-13-018690
OSTI ID:
4216352
Report Number(s):
GB 815641
Country of Publication:
United Kingdom
Language:
English

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Related Subjects

BREEDING
FISSION PRODUCTS
FUSED SALT FUEL
GRAPHITE MODERATOR
HEAT TRANSFER
HEAVY WATER MODERATOR
IN PILE LOOPS
PATENT
PLUTONIUM 239
PRODUCTION
REACTORS
REPROCESSING
SEPARATION PROCESSES
URANIUM 233
URANIUM HEXAFLUORIDE