摘要
以采用AFA3G燃料组件的中国改进型三环路压水堆(CPR1000)核电机组为研究对象,对装入反应堆后的正常燃料组件和修复燃料组件的堆芯物理和热工性能进行分析评估。结果表明:燃料组件内更换1根燃料棒对燃料组件反应性的影响小于-0.03%,该影响可以忽略;修复的燃料组件在换棒位置周围的燃料棒相对功率略微升高约5.6%;燃料组件内更换1根不锈钢棒对燃料组件的相对功率影响约为0.1372%~0.2698%,对组件燃耗的影响大约为0.11%,对堆芯慢化剂温度系数的影响大约为0.03%,对组件出口慢化剂温度的影响大约为0.03%;对堆芯功率峰因子、堆芯临界硼浓度、堆芯停堆裕量和堆芯出口慢化剂温度基本没有影响。
This report takes CPR1000 unit with AFA3G fuel assembly as the research object, and analyzes the physical characteristics and power distribution of normal fuel assembly and damaged fuel assembly after repairment. It can be found that the effect on the fuel assembly reactivity is about -0.03% for the fuel assembly replaced with a stainless steel rod, and the effect can be ignored. The relative power of fuel rods near the stainless steel rod increases about 5.6%. The stainless steel rod replaced in the fuel assembly has effect on the relative power of fuel assembly about 0.1372% to 0.2698%, on burnup about 0.11%, core moderator temperature coefficient about 2%, and these effects can be ignored. The stainless steel rod replaced in the fuel assembly has no effect on the reactor core power peak factor, core critical boron concentration, core shutdown margin, fuel assembly outlet moderator temperature and core outlet coolant temperature.
作者
陈秋炀
薛峰
高拥军
Chen Qiuyang Xue Feng Gao Yongjun(Nuclear Safety Technology Center, Suzhou Nuclear Power Research Institute,, Suzhou, Jiangsu, 215004, China)
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2017年第5期119-122,共4页
Nuclear Power Engineering
关键词
燃料组件
修复
反应性
功率
Fuel assembly, Repairment, Reactivity, Power
