摘要
借助中子学与热工水力学耦合的安全分析程序对铅铋冷却快堆概念设计模型的有停堆保护瞬态超功率(PTOP)和无停堆保护瞬态超功率(UTOP)进行了模拟,并对反应堆的安全特性进行了分析。结果表明,在有停堆保护瞬态超功率过程中,由于停堆保护作用,燃料、包壳及冷却剂温度都远远低于设计限值;对于无停堆保护情况,燃料、包壳及冷却剂等的温度先增大后减小,在约200 s后达到了新的稳态,各参数的峰值均小于安全限值,表明反应堆是安全的。
Protected and unprotected transient overpower accidents for a conceptual model of LBE-cooled fast reactor were simulated by two-dimensional neutronics and thermal-hydraulics coupled simulation program, and the safety characteristics of the reactor during the accidents were analyzed. The results showed that during the protected transient overpower process,due to the reactor scram,the temperatures of the fuel,cladding and coolant were much smaller than the design safety limits. And during the unprotected one,though the temperatures of the fuel,cladding and coolant firstly increased quickly and then decreased, they were still under the safety limits and the reactor turned stable again at about 200 s, which showed that the reactor was safe under this condition.
出处
《核安全》
2015年第3期60-64,共5页
Nuclear Safety
基金
中科院战略性先导科技专项
项目编号XDA03040000
国家自然科学基金重大研究计划项目
项目编号91026004
关键词
有保护瞬态超功率
无保护瞬态超功率
安全分析
快堆
protected transient overpower
unprotected transient overpower
safety analysis
fast reactor
