PRELIMINARY LOFA ANALYSIS OF A PRESSURE TUBE SCWR WITHOUT SAFETY SYSTEM

摘要：

PT-SCWR is a pressure-tube supercritical water cooled reactor under research based on the existingknowledge of operating water-cooled CANDU reactors and fossil fuel fired Super Critical Water(SCW) plants. Loss of Flow Accident (LOFA) is a key challenge for PT-SCWR. A preconceptualPT-SCWR design with no safety system has been considered to evaluate the safetycharacteristics during LOFA transient using SCTRAN code. The analysis shows that PT-SCWRmay achieve potential no core melt goal during LOFA transient, relying on moderator to removedecay heat.

作者: Henan WANG Jianqiang SHAN Junli GOU

作者单位: Xian Jiaotong University,Xian,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: 1-7

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）