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Reactor Design and Feasibility Study: Fused Salt Fast Breeder

Technical Report ·
DOI:https://doi.org/10.2172/1083566· OSTI ID:1083566
An externally cooled, fused salt, fast breeder reactor producing 700 MW of heat has been designed utilizing plutonium as the fuel in a mixture of the chlorides of sodium, magnesium, uranium and plutonium. Depleted uranium is used as the fertile material in a blanket of uranium oxide in sodium.
Research Organization:
Oak Ridge School of Reactor Technology, Oak Ridge, TN (United States)
Sponsoring Organization:
USDOE; US Atomic Energy Commission (AEC)
OSTI ID:
1083566
Report Number(s):
CF--56-8-204(DEL)
Country of Publication:
United States
Language:
English

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