摘要
参考压水堆回路模型,基于次临界能源堆(SER)概念设计建立其系统模型,利用RELAP5/MOD3.3程序进行初始稳态运行验证,并对功率突升事故、冷却剂失流事故和热阱丧失事故进行瞬态安全分析。初步给出次临界能源堆在事故工况下的限值。
The system model of Subcritical Energy Reactor （SER） was primarily established, which was based on SER conceptual design and by taking PWR loop model as references. With RELAP5/MOD3.3 code, initial steady state and transient conditions including power increase accident, loss of coolant flow accident and loss of heat sink accident were analyzed. The results show the limit value during the accidents and make the safety characteristics of SER clear. Suggestions have been offered for SER safety. The work could give references for the following conceptual design and engineering design in hybrid energy reactors.
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2013年第4期106-110,共5页
Nuclear Power Engineering
基金
国家磁约束核聚变能研究专项资助(2010GB111001)
