SCWR for Future Large-Scale Nuclear Power Generation

被引:0
|
作者
Cheng Xu(School of Nuclear Science and Engineering
机构
关键词
supercritical water cooled reactor; mixed core; coupled method;
D O I
暂无
中图分类号
TL33 [反应堆热工水力学及其设计、计算];
学科分类号
082701 ;
摘要
The ambitious nuclear power program motivates the Chinese nuclear community to develop advanced reactor concepts of generation IV,in order to ensure the long-term,stable and sustainable development of nuclear power.The supercritical water-cooled reactor(SCWR)has favorable features in economics,sustainability and technology availability.It is the logical extension of the existing PWR technology and has very promising perspectives in large-scale power generation in China.This paper describes the main features of SCWR.New designs of SCWR core structure and fuel assemblies are proposed.Preliminary analysis using a coupled neutron-physics/thermal-hydraulics method is carried out and shows a good feasibility of the new design proposal.
引用
收藏
页码:68 / 75
页数:8
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