Three alternative concepts for a 300 kWe space reactor power system were recently analyzed by the General Electric Company. All three concepts were based upon the results of previous SP-100 conceptual design studies for a 100 kWe system. These studies recommended the use of a lithium-cooled fast spectrum reactor, a conductively coupled thermoelectric conversion subsystem, and a potassium heat pipe radiator. The three alternative concepts, which all incorporated these features, differed principally in the means of waste heat removal. In two of the concepts, waste heat removal was accomplished by directly coupling radiator heat pipes to the cold-side of the thermoelectric conversion subsystem. In the third concept, an intermediate liquid-metal pumped loop was employed. The principal trade-off factors considered in comparing these approaches included radiator area and mass, available payload volume (assuming a shuttle launch), growth limits, ease of design integration, adaptability to changing user requirements, ease of operation, fabricability and testability. This paper presents the results of these comparative analyses and indicates the direction of further design evolution.
Comparison of concepts for a 300 kWe nuclear power system
Vergleich von Konzepten fuer ein 300 kWe Kernenergiesystem
1986
5 Seiten, 5 Bilder, 1 Quelle
Aufsatz (Konferenz)
Englisch
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