摘要
以典型热管冷却空间反应堆(SAIRS)为对象,针对其各个模块进行建模,研制了基于SAIRS的系统瞬态计算程序(TAPIRS),并用该程序分析了反应堆的3种典型瞬态工况。计算结果表明:在控制鼓故障引入极大反应性、碱金属热电转换装置(AMTEC)部分失效和散热板丧失部分散热面积事故工况下,燃料温度控制在安全限值以内,验证了反应堆系统在事故工况下具有应对单一故障和自稳自调的能力。
A transient analysis code TAPIRS was developed to analyze the behavior of the heat pipe cooled space reactor power system based on the SAIRS models. Three typical accidents are analyzed using TAPIRS. The results show that the fuel temperature is below a safe limit under the control drum failure, the AMTEC failure and partial loss of the heat transfer area of radiator. This demonstrates that the reactor system is with the characteristics of self-stabilization ability under accident conditions.
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2016年第5期119-124,共6页
Nuclear Power Engineering
