堆芯多物理耦合的不确定性分析方法研究及应用  

Uncertainty analysis method for multiphysics coupling in reactor cores and applications

作　　者：邹晓阳 万承辉 曹良志 ZOU Xiaoyang;WAN Chenghui;CAO Liangzhi(Xi′an Nuclear Energy Creative Power Co.,Ltd.,Xi′an 710076,China;School of Nuclear Science and Technology,Xi′an Jiaotong University,Xi′an 710049,China)

机构地区：[1]西安核创能源科技有限公司,陕西西安710076 [2]西安交通大学核科学与技术系,陕西西安710049

出　　处：《哈尔滨工程大学学报》2024年第12期2400-2407,共8页Journal of Harbin Engineering University

摘　　要：为了研究核反应堆堆芯中子学、热工水力和燃料性能分析等多物理耦合计算的不确定性,本文基于“两步法”计算软件Bamboo-C和燃料性能分析程序FEMAXI,通过再抽样方法实现了堆芯多物理耦合计算功能,采用统计学抽样方法对“华龙一号”堆芯多物理耦合关键响应进行不确定性分析。结果表明:“华龙一号”堆芯首循环临界硼浓度的不确定度为45.4×10-6~46.1×10-6;寿初期状态下径向和轴向功率分布的最大相对不确定度分别为2.1%和0.96%;寿末期状态下径向和轴向功率分布的最大相对不确定度分别为0.8%和0.83%。本文建立的多物理耦合不确定性分析方法为核反应堆的设计、运行和安全分析提供了有效的工具,有助于提高反应堆的安全性和经济性。This study examines the uncertainties in multiphysics coupled calculations for neutronics,thermohydraulics,and fuel performance analysis in a nuclear reactor core.Using the“two-step”computational software Bamboo-C and the fuel performance analysis program FEMAXI,the multiphysics coupling function was implemented via the Uncertain Tabular method.Subsequently,a statistical sampling approach was applied to analyze uncertainties in the key responses of the Hualong One reactor core.The findings reveal that,for the first cycle at the beginning of life(BOL),the uncertainty in critical boron concentration ranges from 45.4×10-6 to 46.1×10-6.The maximum relative uncertainties in radial and axial power distributions at BOL are 2.1%and 0.96%,respectively.At the end of life,these uncertainties decrease to 0.8%for radial and 0.83%for axial power distributions.The uncertainty analysis method developed in this study offers an effective tool for reactor design,operation,and safety assessments and enhances the safety and economic performance of nuclear reactors.

关 键 词：不确定性分析 抽样方法 多物理耦合 核数据 工程参数 中子学 热工水力 燃料性能分析 

分 类 号：TL32[核科学技术—核技术及应用]