APA-H程序应用于田湾核电站1号机组堆芯物理参数计算验证

Validation of APA-H Code Calculation Based on Core Physical Parameter for Tianwan NPP Unit 1

摘要: 为验证APA-H(ALPHA-H/PHOENIX-H/ANC-H)程序系统应用于田湾核电站1号机组(VVER1000)堆芯物理参数计算的可行性，针对田湾核电站1号机组第6~9燃料循环的燃料管理开展计算研究。对临界硼酸浓度、组件相对功率分布以及启动物理试验进行模拟计算，并与试验测量数据进行比对。结果表明，计算值与试验测量数据符合良好，满足验收准则。APA-H程序系统可用于田湾核电站1号机组的堆芯物理参数计算。

Abstract: To validate the feasibility of APA-H (ALPHA-H/PHOENIX-H/ANC-H) code system used to the Tianwan NPP Unit 1 (VVER1000) core physical parameter calculation, the fuel management calculations for Tianwan NPP Unit 1 cycles 6-9 were studied. The calculations of critical boric acid concentration, relative assembly power distribution and startup physics tests were carried out and compared with the experimental data. The results show that the calculation values are in good agreement with the experimental data, and meet the acceptance criteria. APA-H code system is suitable to the Tianwan NPP Unit 1 core physical parameter calculation.