压水堆燃料组件变形的中子学分析
Neutronics Analysis of the Fuel-assembly-bowing Effect in Pressurized Water Reactor
何明涛 1孟晗 1李学仲 1王欣欣 1赵常有 1李志军1
作者信息
- 1. 中广核研究院有限公司,广东 深圳 518000
- 折叠
摘要
压水堆燃料组件在堆芯中受轴向压紧力和横向力作用,同时受高中子注量率辐照,进而产生各种形式的组件变形以及组件内的棒弯曲现象.这会影响局部栅格的慢化条件,进而影响中子学参数以及堆芯运行的安全裕量.本文基于燃料组件变形以及组件内棒弯曲的测量数据,分别建立含不同组件变形及棒弯曲效应的堆芯计算模型,分析组件变形引起的局部慢化条件变化及其对功率分布的影响,尤其是堆芯功率周向分布特性的影响.同时,也评估了不同反射层设计下的影响程度差异.结果表明组件变形对功率分布有影响,且重反射层条件下该效应相对更为显著.
Abstract
In pressurized water reactors,fuel assemblies are subjected to axial compression and lateral forces,as well as high neutron flux,which result in various forms of assembly deformation and rod bending.Assembly deformation affects the local moderation effect,thereby affecting the neutronics parameters and the safety margin of the core.In this study,based on the measurement data,core neutron calculation models with different deformation and bending effects are established to analyze the changes of local moderation effects caused by deformation and the influence on core power distribution.At the same time,the effect of deformation under different reflector designs is also evaluated.The results show that the deformation has an impact on the power distribution,and the effect will be more significant for the heavy-reflector design.
关键词
燃料组件/组件变形/棒弯曲/局部慢化Key words
Fuel assembly/Assembly bowing/Rod bending/Local moderated引用本文复制引用
出版年
2024
NETL
NSTL
万方数据