【摘要】 介绍了压水堆核电厂换料堆芯功率能力验证分析的原理和方法。利用中子学计算程序对换料堆芯正常运行工况(一类工况或工况I)和中等频率事故工况(二类工况或工况II)中可能的堆芯功率分布进行模拟。从反应堆物理和热工水力学的角度论证反映一、二类工况堆芯安全性的线功率密度裕量和偏离泡核沸腾比(DNBR)裕量,从而验证一类工况反应堆运行区域和二类工况超温、超功率保护限值。本文还给出了大亚湾核电站18个月换料堆芯功率能力验证分析的结果。更多还原

【Abstract】 The Principle and methodology of pressurized water reactor nuclear power plant core power capability verification for reload are introduced. The radial and axial power distributions of normal operation (category I or condition I) and abnormal operation (category II or condition II) are simulated by using neutronics calculation code. The linear power density margin and DNBR margin for both categories, which reflect core safety, are analyzed form the point view of reactor physics and T/H, and thus category I operating domain and category II protection set point are verified. Besides, The verification results of reference NPP are also given.更多还原