HFETR堆芯不锈钢反射层的研究  

Study on Stainless Steel Reflector of Core for HFETR

作　　者：孙寿华[1] 林继森[1] 唐学仁 段天元[1] 

机构地区：[1]中国核动力研究设计院

出　　处：《核动力工程》1999年第2期178-181,共4页Nuclear Power Engineering

摘　　要：用快中子分出截面法估算了不锈钢棒对压力容器处快中子注量率的减弱程度，用二维多群粒子输运程序ＤＯＴ３．５计算了不锈钢棒的γ释热，计算了高通量工程试验堆（ＨＦＥＴＲ）设计工况和目前运行工况下不锈钢壁面温度和中心温度，对承重栅板的安全性进行了讨论，分析了不锈钢棒对堆芯的性能影响。结果表明，用不锈钢代替铝棒作最外层反射层，堆芯安全性能不变，压力容器处快中子注量率被大幅度降低。The attenuation of the fast neutron flux at the pressure vessel has been estimated through the method of the fast neutron removing cross section.The gamma_induced internal heating in the stainless steel rod has been computed by DOT3.5 Code.The wall temperature and centre tenperature has been computed under the design status and current operating status of High Flux Engineering Test Reactor (HFETR),The safety evaluation of the lattice sheet and the analysis of the core preformance have been done.These results show that the core safety isn't variation,and the fast neutron flux at the pressure vessel will be decreased greatly after replacemeat of the aluinum rod by the stainless steel rod as the outermost reflector of the core for HFETR.

关 键 词：工程试验堆 不锈钢棒 快中子注量率 压力容器 

分 类 号：TL411.605[核科学技术—核技术及应用] TL351.6