1959
DOI: 10.2172/4265274
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THE HGCR-1, A DESIGN STUDY OF A NUCLEAR POWER STATION EMPLOYING A HIGH- TEMPERATURE GAS-COOLED REACTOR WITH GRAPHITE-UO$sub 2$ FUEL ELEMENTS

Abstract: T h e preliminary design o f a 3095-Mw(thermal), helium-cooled, graphite-moderated reactor employing graphite-U02 fuel elements has been investigated. At design conditions, 150OOF reactor outlet gas would be circulated t o eight steam generators to produce 1O5O0F, 1450-psi steam which would be converted to electrical power i n eight 157-Mw(electrica1) turbine-generators. The overall efficiency of t h i s nuclear power station i s 36.5%. The significant a c t i v i t i e s released from the unclad graphite-U02 … Show more

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“…To achieve these turbine temperatures out of the heat exchanger in an indirect cycle gas reactor, an outlet gas temperature of about 1500°F is required. (114) If turbo machinery were available to operate with 1500°F gas inlet temperatures, then this gas temperature could be employed in a direct cycle with definite improvement in efficiency, which would result in lower power costs. To achieve this goal, a development program would be required for turbines, compressors, seals, expansion joints, and bearings.…”
Section: An Examination Ofmentioning
confidence: 99%
“…To achieve these turbine temperatures out of the heat exchanger in an indirect cycle gas reactor, an outlet gas temperature of about 1500°F is required. (114) If turbo machinery were available to operate with 1500°F gas inlet temperatures, then this gas temperature could be employed in a direct cycle with definite improvement in efficiency, which would result in lower power costs. To achieve this goal, a development program would be required for turbines, compressors, seals, expansion joints, and bearings.…”
Section: An Examination Ofmentioning
confidence: 99%