压水堆高保真换料循环计算功能开发与验证应用

在自主开发的数值反应堆物理计算程序NECP-X基础上开发了压水堆的换料循环计算功能,并针对某M310机组首循环、第2循环和第3循环的启动物理实验,以及针对前2个循环的燃耗进行了精细建模计算。计算值与实测值的比较结果表明：首循环、第2循环和第3循环启动物理实验的临界硼浓度、控制棒价值、温度系数计算结果误差均较小,符合验收准则;不同燃耗深度下的临界硼浓度、堆芯功率分布与实测值的比较结果显示,稳定燃耗点处最大硼浓度偏差为-39ppm(1ppm=10^-6),最大的组件功率误差小于4.5%,随着燃耗的加深,堆芯功率的分布逐渐展平,误差逐渐减小。计算结果表明NECP-X程序已经具备商用压水堆启动物理实验和多燃料循环的计算能力。

Development and Validated Application of Calculation Function of High Fidelity Refueling Cycle for Pressurized Water Reactor

The refueling cycle calculation function for pressurized water reactor (PWR) is developed on the basis of the self-developed numerical nuclear reactor physics calculation code NECP-X. Startup physics experiments are conducted for the first, second and third cycles of an M310 reactor, and fine modeling calculation is carried out for the first two cycles. By comparing the calculated values with the measured values, it shows that the errors of calculation results of critical boron concentration, control rod worth and temperature coefficient in the startup physics experiments for the first, second and third cycles are relatively small, which meet the acceptance criteria. The results of comparison of the critical boron concentration and core power distribution with the measured values at different burnup levels show that the maximum boron concentration deviation at the stable burnup point is ?39ppm (1ppm = 10?6), and the maximum assembly power error is less than 4.5%. With the increase of burnup level, the core power distribution flattens out and the error decreases gradually. The calculation results show that NECP-X already has the calculation function for the startup physics experiments and multi-fuel cycle of commercial PWRs.