CNP1500堆芯燃料管理设计

In-Core Fuel Management Design for CNP1500

CNP1500是一个轻水慢化和冷却的四环路压水堆核电站。反应堆堆芯由205个AFA-3GXL燃料组件组成；堆芯冷态活性段高度为426．7cm；等效直径为347．0cm。反应堆热功率输出为4250MW,平均线功率密度为179．5W/cm。计算结果表明,平衡循环堆芯的循环长度为470等效满功率天；各循环堆芯所有状态下的慢化剂温度系数均为负值；各循环热态满功率、无控制棒、平衡氙状态下的核焓升因子氏FQ(ΔH)都低于限值；最大卸料组件燃耗小于55000MW·d/t(U)；各循环寿期末停堆裕量满足设计准则；低泄漏堆芯装载降低了反应堆压力容器的辐照损伤,有利于延长压力容器的使用寿命。本文介绍了四环路压水堆核电站堆芯燃料管理设计方案及主要计算结果。

CNP 1500 is a four-loop PWR nuclear power plant with light water as moderator and coolant. The reactor core is composed of 205 AFA-3GXL fuel assemblies. The active core height at cold is 426.4cm and equivalent diameter is 347.0cm. The reactor thermal output is 4250MW, and the average linear power density is 179.5W/cm. Calculation results show that the cycle length of equilibrium cycle core reaches to 470 equivalent full power days, and for all cycles, the moderator temperature coefficients at all conditions are negative values, the nuclear enthalpy rise factors F△H at hot full power, all control rods out and equilibrium xenon are less than the limit value, the maximum discharge assembly burnup is less 55000MW·d/t（U）, and the shutdown margin values at the end of life meet design criteria. The low-leakage core loading reduces radiation damage on pressure vessel and is beneficial to prolong use lifetime of it. This paper presents the in-core fuel management design scheme and main calculation results for CNP 1500 nuclear power plant.