Development of the CASIR code system for SCWR core steady state design

摘要：

A coupled neutronic and thermal-hydraulic code system CASIR (Core Analysis System forInnovation Reactor) for SCWR core steady state design is developed due to the requirementfor the design and technology research on SCWR nuclear system. The CASIR system, inwhich the neutronic codes are well validated in PWR and the sub-channel thermal-hydrauliccode is validated for SCWR, can be used to simulate SCWR core with square assemblies.Compared with Monte Carlo code, it shows that the CASIR system is accurate to simulate theSCWR core, and the current code system is a suitable tool for SCWR core conceptual design.

作者: Yongqiang Ma Xiaoming Chai Yuwei Wang Junjie Pan

作者单位: Science and Technology on Reactor System Design Technology Laboratory,Chengdu,China

会议类型: 国际会议

会议名称: 3rd China-Canada Joint Workshop on Supercritical Water-Cooled Reactors(第三届中国-加拿大超临界水堆研讨会 (CCSC-2012)

会议地点: 西安

会议语种:英文

页码: 1-10

在线出版日期: 2012-04-18（万方平台首次上网日期，不代表论文的发表时间）