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Title: SURVEY OF LOW ENRICHMENT MOLTEN-SALT REACTORS

Technical Report ·
DOI:https://doi.org/10.2172/4143508· OSTI ID:4143508

A rough survey of the nuclear charactenistics of graphite-moderated molten-salt reactors utilizing an initial complement of low enrichment uranium fuel has been made. Reactors can be constructed with initial enrichinents as low as 1.25% U-235; initial conversion ratios of as high as 0.8 can be obtained with enrichinent of less than 2%. Highly enriched uraninm would be added as make-up fuel, and such reactors could probably be operated for bunnups as high as 60,000 Mwd/ton before buildup of fission preducts wpuld make replacement of the fuel desirable. A typical circulating fuel reactor of this class might contain an initial inventory of 3600 tons of 1.8% enriched uranium, operated at 640 Mw (thermal), and generate a net of 260 Mw (electrical). The total fuel cycle cost would be approximately 1.3 mills/kwhr, of which 1.0 mill is bunnup of enniched U- 235. (auth)

Research Organization:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
NSA Number:
NSA-14-018617
OSTI ID:
4143508
Report Number(s):
CF-58-10-60
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-60
Country of Publication:
United States
Language:
English