摘要
基于修改后的最佳估算程序ATHLET-SC建立了典型的超临界水冷反应堆系统模型。对3种典型的非失水事故(失去给水加热、汽轮机失去负载且旁排未开启、给水泵卡轴)进行了模拟和敏感性分析,得到了堆功率、质量流量、最高包壳温度和最高燃料中心温度随时间变化的计算结果。结果表明,上述事故中系统压力、最高燃料包壳温度和最高燃料中心温度均可满足事故安全准则。
Based on the revised best-estimate code AHTLET-SC,a typical supercritical water cooled reactor（SCWR） system was modeled.Three non-LOCA accidents（loss of feed water heating,loss of turbine load without turbine bypass and reactor coolant pump seizure） were chosen to perform accident simulation and sensitivity analysis.Some important results e.g.core power,mass flow rate,the highest cladding temperature,and the highest fuel pellet centerline temperature were obtained.The results indicate that all parameters satisfy the safety criteria in the accidents mentioned above.
出处
《原子能科学技术》
EI
CAS
CSCD
北大核心
2013年第7期1162-1168,共7页
Atomic Energy Science and Technology
