Conceptual design of compact supercritical water-cooled fast reactor with thermal hydraulic coupling

被引:46
作者
Yoo, Jaewoon
Ishiwatari, Yuki
Oka, Yoshiaki
Liu, Jie
机构
[1] Univ Tokyo, Sch Engn, Nucl Profess Sch, Tokai, Ibaraki 3191106, Japan
[2] Univ Tokyo, Sch Engn, Dept Nucl Engn & Management, Bunkyo Ku, Tokyo 1138656, Japan
关键词
D O I
10.1016/j.anucene.2006.07.004
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
Fuel rod design for high power density supercritical water-cooled fast reactor was conducted with mixed-oxide (MOX) fuel and stainless steel (SUS304) cladding under the limiting cladding surface temperature of 650 degrees C. Fuel and cladding integrities, and flow-induced vibration were taken into account as design criteria. Designed fuel rod has the diameter of 7.6 mm and is arranged in the fuel assembly with pitch-to-diameter ratio of 1.14. New core arrangement for negative void reactivity is proposed by three-dimensional tri-z core calculation fully coupled with thermal hydraulic calculation, where ZrH layer concept is used for negative void reactivity. The core has high power density of 156 W/cm(3) and its equivalent diameter is only 2.7 m for 1000 MWe class reactor core. High average core outlet temperature of 500 degrees C is achieved by introducing radial fuel enrichment zoning and downward flow in seed assembly. Small pressure vessel size and simplified direct steam cycle with higher thermal efficiency give an economical potential in aspect of capital and operating cost. (c) 2006 Elsevier Ltd. All rights reserved.
引用
收藏
页码:945 / 956
页数:12
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