高通量工程试验堆中子能谱计算  

HFETR CORE NEUTRON SPECTRA CALCULATION

作　　者：彭凤[1] 刘水清[1] 

机构地区：[1]中国核动力研究设计院

出　　处：《核科学与工程》1993年第2期135-142,6,共8页Nuclear Science and Engineering

摘　　要：采用ANISN程序,DOT 3.5程序和组合几何全能区蒙特卡罗程序计算了HFETR中子能谱。计算中堆芯简化为由燃料元件、铍组件、铝组件和水层的同心环所组成。堆芯中心K11位置放置不同部件。对各种方案计算分析后,得到了HFETR最佳圆柱形热阱半径、超热中子谱表达式等有实用价值的结果。计算结果与已有的能谱和能谱参数实验值进行了比较,在误差范围内是相符的。In this paper, the ANISN code, the DOT 3. 5 code and the Combinatorial Geometry Full Energy Range Monte Carlo code are used to calculate the core neutron spectra of HFETR. HFETR core is simplified as composed of fuels, beryllium reflector, surrounded by aluminium and water. Irradiation channels and capsules are put into the central position of the core (K11). By analysing the calculation results of different core arrangements, some valuable conclusions are derived for the optimal radius of a cylinder flux trap, the analytical expression of epithermal neutron spectra, etc. Calculated results are compared with experimental results of spectra and spectrum parameters. Agreements are within errors.

关 键 词：计算 HFETR 试验堆 中子谱 

分 类 号：TL411.6[核科学技术—核技术及应用]