摘要
为分析卡轴工况下事故容错燃料(ATF)对反应堆安全的潜在影响,以中国改进型三环路压水堆(CPR1000)为参考电站,基于系统分析程序NUSOL-SYS进行了二次开发,研究了不同ATF组合在卡轴工况下的表现,并对ATF包壳表面特性变化可能引起的换热系数和临界热流密度(CHF)变化开展了敏感性分析。分析结果表明,在卡轴工况下,ATF包壳表面特性变化导致的换热系数和CHF变化会对芯块最高温度和包壳峰值温度(PCT)产生较大影响,热导率大的ATF芯块能极大地降低芯块温度,比热容大的ATF材料能降低PCT。
To analyze the potential impact of accident tolerant fuel(ATF) on reactor safety under pump shaft-stuck accident,China's improved three-loop pressurized water reactor CPR1000was used as reference power station to carry out second development based on the system analysis code NUSOL-SYS.The performance of CPR1000 with different ATF combinations under pump shaft-stuck accident was studied,and the sensitivity analysis was carried out to study the change of heat transfer coefficient and critical heat flux(CHF) caused by the change of ATF cladding surface characteristics.The results show that the change of heat transfer coefficient and CHF caused by the change of ATF cladding surface characteristics has a great influence on the maximum temperature of pellets and the peak cladding temperature(PCT).ATF pellets with high thermal conductivity can greatly reduce the pellet temperature,while ATF materials with high specific heat capacity can reduce the PCT.
作者
吴和鑫
金德升
苟军利
单建强
程毅
Wu Hexin;Jin Desheng;Gou Junli;Shan Jianqiang;Cheng Yi(School of Energy and Power Engineering,Xi’an Jiaotong University,Xi’an,710049,China;China Nuclear Power Technology Research Institute,Shenzhen,Guangdong,518026,China)
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2023年第S01期75-80,共6页
Nuclear Power Engineering
