部分参数统计方法在30万kW核电厂应用的初步研究  

Preliminary Research on Part-statistical Methodology for 300 MWe Nuclear Power Plant Application

作　　者：王喆[1] 许志红[1] 

机构地区：[1]上海核工程研究设计院,上海200233

出　　处：《原子能科学技术》2016年第10期1801-1804,共4页Atomic Energy Science and Technology

摘　　要：偏离泡核沸腾(DNB)设计基准是反应堆热工水力设计中的重要基准之一,为评价该设计基准是否满足热工水力设计要求,需确定堆芯偏离泡核沸腾比(DNBR)设计限值。本文研究了使用统计学方法确定不确定性的部分参数统计方法原理,并应用该方法和堆芯子通道分析程序对30万kW核电厂DNBR设计限值进行计算。计算结果表明,反应堆冷却剂流量全部丧失事故最小DNBR分析采用部分参数统计较STDP额外获得了约5%的裕量。本文结果为DNBR设计基准的验证提供了关键判据。Departure from nucleate boiling（DNB）design basis is one of the most important bases for reactor core thermal-hydraulic design.In order to evaluate whether the DNB design basis meets the requirement of thermal-hydraulic design,the departure from nucleate boiling ratio（DNBR）design limit should be determined.The part-statistical methodology was described in detail.The part-statistical methodology and a reactor subchannel code were applied to calculate the DNBR design limit for 300 MWe nuclear power plant.The part-statistical methodology was used to replace STDP for DNBR analyses,and the results indicate that for complete loss of reactor coolant flow accident,about 5% DNBR margin can be got.The conclusions are presented to provide the key acceptable criterion for DNBR design basis.

关 键 词：DNBR 设计限值 部分参数统计方法 

分 类 号：TL364.4[核科学技术—核技术及应用]