小型压水堆小破口失水事故  

SBLOCA of small pressurized water reactor

作　　者：杨晓敏 陈玉清[1] 蔡琦[1] 饶彧先 王伟[1] 王海峰[1] YANG Xiaomin;CHEN Yuqing;CAI Qi;RAO Yuxian;WANG Wei;WANG Haifeng(College of Nuclear Science and Technology, Naval University of Engineering, Wuhan 430033, China)

机构地区：[1]海军工程大学核科学技术学院,武汉430033

出　　处：《兵器装备工程学报》2022年第4期86-91,共6页Journal of Ordnance Equipment Engineering

摘　　要：针对某小型压水堆,采用最佳估算加不确定性分析的方法,以最佳估算程序RELAP5/SCDAPSIM为工具开展小破口失水事故的瞬态特性分析;基于Wilks公式的非参数统计方法,对源系数所带来的不确定性传播进行量化评估;进而通过敏感性分析,确定了对燃料包壳峰值温度影响关键的源系数是壁面传热系数、冷却剂导热系数和相间界面传热系数,研究结果表明:这7种源系数所带来的不确定性传播影响不显著,适用于小型压水堆的小破口失水事故分析计算。For a small pressurized water reactor,the method of Best-estimate Plus the Uncertainty(BEPU)was adopted,and the best estimation program RELAP5/SCDAPSIM was used as a tool to carry out the small break loss of coolant accident(SBLOCA)transient characteristics analysis;Non-parametric statistical method based on Wilks formula quantitatively evaluated the uncertainty propagation caused by the source code coefficients;It is determined that the critical source code coefficients affecting the peak temperature of fuel cladding are the heat transfer coefficient of wall surface,the thermal conductivity coefficient of coolant and the inter-facial heat transfer coefficient through sensitivity analysis;The results show that the influence of the seven source code coefficients on the propagation of uncertainty is not significant,which can be applied to the analysis and calculation of the small break loss of coolant accident(SBLOCA)about small pressurized water reactor.

关 键 词：小型压水堆 SBLOCA 源系数 不确定性分析 敏感性分析 

分 类 号：TL36[核科学技术—核技术及应用]