论文部分内容阅读
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。
The nuclear physics and thermal performance of the retrofitted normal fuel assemblies and the repaired fuel assemblies were analyzed and evaluated using China Advanced Three-Circuit PWR (CPR1000) nuclear power plant with AFA3G fuel assemblies. The results show that the effect of replacing one fuel rod in the fuel assembly on the reactivity of the fuel assembly is less than -0.03%, and the effect is negligible; the relative power of the fuel rods in the fuel assembly around the change rod position increases slightly by about 5.6% Replacing a stainless steel rod within the assembly has a relative power contribution of about 0.1372% to 0.2698% for the fuel assembly, about 0.11% for the assembly fuel burnup, about 0.03% for the core moderator temperature coefficient, The effect of exit moderator temperature is about 0.03%; there is almost no effect on the core power peak factor, core critical boron concentration, core shutdown allowance, and core outlet moderator temperature.