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U.S. Department of Energy
Office of Scientific and Technical Information

STEAM SUPERHEAT BOILING WATER NUCLEAR REACTOR

Patent ·
OSTI ID:4822154
An improved superheat boiling reactor is designed which has its core divided into a boiler region and a superheat region. The moderator and coolant in the boiler region is water, while in the superheat region the moderator is a solid, e.g., graphite, beryllium, or a metal hydride. Some of the advantages of a solid moderator in the superheat region are elimination of insulation between steam and moderator, simpler core design, and lower uranium enrichment requirements. An embodiment of the reactor having a power of 420 Mw(t) or 150 Mv(e) is described. (D.L.C.)
Research Organization:
Originating Research Org. not identified
NSA Number:
NSA-16-001261
OSTI ID:
4822154
Report Number(s):
GB 879282
Country of Publication:
United Kingdom
Language:
English