摘要
气体透平氦气模块堆(GT MHR)标准题是国际原子能机构(IAEA)关于“高温气冷堆在事故工况下的热传输和余热载出”问题的合作研究计划(CRP)的一部分。本文用THERMIX程序计算了稳态和两类丧失强迫冷却事故瞬态的反应堆温度分布以及空腔冷却系统(RCCS)的载热能力。计算结果表明 ,稳态及事故中燃料和压力容器的最高温度不超过安全限值 ,RCCS能够有效带出堆芯余热 。
The benchmark problem for GT MHR plutonium burner accidents is a part of the IAEA Coordinated Research Program(CRP) on “heat transport and afterheat removal for GCR under accident conditions' The reactor performance and RCCS capability during normal operation and two loss of forced convection(LOFC) accidents are analyzed using THERMIX code Results shows that the core fuel temperature and the vessel temperature below the safety limits,and the RCCS can remove the residual heat from the core after the accidents to remain the reactorin safety
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2000年第2期146-151,共6页
Nuclear Power Engineering
基金
IAEA国际合作研究计划
关键词
气体透平氦气模块堆
冷却事故
事故分析
Gas turbine modular helium reactor Loss of forced convection Reactor cavity cooling system (RCCS)
