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A direct-cycle, supercritical light-water-cooled FBR, SCFBR-D

Conference · · Transactions of the American Nuclear Society; (United States)
OSTI ID:7129821
We have been studying supercritical-pressure light-water-cooled reactors (SCLWRS) for improving thermal efficiency, simplifying the light water reactor (LWR) system, and moving toward a low-cost fast breeder reactor (FBR) based on long-standing water coolant technology of a fossil-fired power plants and LWRs. This paper summarizes the conceptual design of a direct-cycle, supercritical-pressure FBR, the SCFBR-D. The fuel is U-Pu mixed oxides (MOX). The cladding material is stainless steel. The maximum surface temperature is limited below 450[degrees]C. It is very low compared with the maximum steam temperature of current fossil-fired power plants (FPPs), 566[degrees]C. Therefore, the cladding is the noncollapsed type and will be free from oxidation-induced corrosion problems. The thermal efficiency is, however, improved by 24% over that of a boiling water reactor (BWR) even under the current limit, 450[degrees]C. The efficiency is comparable with a supercritical FPP because heat is not wasted as exhaust gas in nuclear reactors. The system pressure is 250 bars. Supercritical fluid does not exhibit a change of phase. The water coolant density decreases continuously from the inlet (0.725 g/cm[sup 3]) to the outlet (0.137 g/cm[sup 3]). The coolant is fed directly to turbines. This eliminates the recirculation system, steam separators, and dryers.
OSTI ID:
7129821
Report Number(s):
CONF-931160--
Conference Information:
Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 69
Country of Publication:
United States
Language:
English