组件燃耗对堆芯裂变中子源参数的影响  

Impact of Fuel Assemblies Burn-Up on Core Fission Neutron Source Parameter

作　　者：杨玉中[1] 芮旻[1] 章宗耀[1] 

机构地区：[1]中国核动力研究设计院,成都610041

出　　处：《核动力工程》2003年第3期201-203,共3页Nuclear Power Engineering

摘　　要：在中子输运计算中,准确的裂变中子源是保证计算结果可靠性的前提和基础。随着组件燃耗的加深,235U等核素不断消耗,239Pu、240Pu、241Pu等核素不断积累,导致每次裂变产生的平均中子数ν和裂变释放的平均能量E也随之变化,裂变中子源的归一化因子随燃耗增加而增加。因此,在中子输运计算中,必须考虑组件燃耗对堆芯的裂变中子源参数的影响。For the neutron transportation calculation, accurate fission neutron source is the prerequisite and fundament ensuring that the calculation results are reliable. As the fuel assemblies burn-up is increased, nuclides such as 235U gradually consumed, and nuclides such as 239Pu、240Pu、241Pu gradually accumulated, resulting in the variation of average number of fission neutrons (ν) and average releasing energy of each fission(E), and the value of ν/E raised along with the increasing of fuel assemblies burn-up. So the impact of fuel assemblies burn-up on core fission neutron source parameters shall be considered in the neutron transportation calculation.

关 键 词：组件燃耗 堆芯裂变中子源 中子输运计算 

分 类 号：TL329[核科学技术—核技术及应用]