高温气冷堆堆芯中子时空动力学模拟计算  

Core Neutron Space-time Kinetics of High Temperature Gas Cooled Reactor

作　　者：宋英明[1] 马远乐[1] 单文志[1] 周志伟[1] 经荥清[1] 

机构地区：[1]清华大学核能与新能源技术研究院,北京100084

出　　处：《计算物理》2009年第6期911-916,共6页Chinese Journal of Computational Physics

基　　金：国家"十一五"科技重大专项资助项目

摘　　要：研究开发三维圆柱几何堆芯多群中子时空动力学改进准静态方法模拟计算程序.对给定的模块式高温气冷堆模型进行模拟计算.初始状态下,计算结果与中子扩散程序CITATION吻合很好.动态情况下,模拟堆芯反应性、堆内各能群中子平均注量率和堆芯相对功率等物理量随时间变化,计算结果与理论分析一致.3D-cylinder reactor core neutron space-time kinetics is simulated with an improved quasi-static method.The program is developed.In a supposable 250 MW modular HTGR model,the core neutron space-time kinetics is simulated.Calculated results obtained from this program and CITATION code agree well with each other at initiatory state.Variance of the core reactivity,average neutron flux of each group,and relative power with time is computed.

关 键 词：高温气冷堆 中子时空动力学 改进准静态方法 动态模拟 CITATION 

分 类 号：TL327[核科学技术—核技术及应用]