CORE DESIGN OF A DIRECT-CYCLE, SUPERCRITICAL-WATER-COOLED FAST BREEDER REACTOR

被引:15
|
作者
JEVREMOVIC, T
OKA, Y
KOSHIZUKA, S
机构
[1] UNIV BELGRADE, BELGRADE, YUGOSLAVIA
[2] UNIV TOKYO, TOKYO, JAPAN
关键词
D O I
10.13182/NT94-A35040
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
The conceptual design of a direct-cycle fast breeder reactor (FBR) core cooled by supercritical water is carried out as a step toward a low-cost FBR plant. The supercritical water does not exhibit change of phase. The turbines are directly driven by the core outlet coolant. In comparison with a boiling water reactor (BWR), the recirculation systems, steam separators, and dryers are eliminated. The reactor system is much simpler than the conventional steam-cooled FBRs, which adopted Loeffler boilers and complicated coolant loops for generating steam and separating it from water. Negative complete and partial coolant void reactivity are proved without much deterioration in the breeding performances by inserting thin zirconium-hydride layers between the seeds and blankets in a radially heterogeneous core. The net electric power is 1245 MW(electric). The estimated compound system doubling time is 25 yr. The discharge burnup is 77.7 GWd/t, and the refueling period is 15 months with a 73% load factor. The thermal efficiency is high (41.5%), an improvement of 24% relative to a BWR's. The pressure vessel is not thick at 30.3 cm.
引用
收藏
页码:24 / 32
页数:9
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