铀氢锆堆物理计算及燃料管理软件包  

Code Package of the Physics Calculation and FuelManagement of Uranium HydrideZirconium Reactor

作　　者：陈伟[1,2] 谢仲生[1,2] 陈达[1,2] 

机构地区：[1]西安交通大学 [2]西北核技术研究所

出　　处：《核动力工程》1998年第4期320-325,共6页Nuclear Power Engineering

摘　　要：建立了一套铀氢锆堆物理计算软件包。首先考虑氢化锆中氢的热化特殊性，按ＷＩＭＳ格式制作了氢化锆中氢的６９群群常数并入ＷＩＭＳＤ／４数据库中，形成了ＷＩＭＳＮ１库和ＷＩＭＳＮ２库；应用ＷＩＭＳＮ２库和国际通用的ＷＩＭＳＤ／４程序包计算了铀氢锆堆各类栅元的群常数，应用差分程序ＣＩＴＡＴＩＯＮ和六角形节块程序ＳＩＸＴＵＳ进行扩散计算，同时在ＳＩＸＴＵＳ２程序的基础上编制了燃料管理程序ＸＰＲＩＣＦＭ。为检验软件包的计算精度及可靠性，对国外ＴＲＩＧＡ堆、国内铀氢锆模式堆和西安脉冲堆进行临界ｋｅｆ和控制棒价值等计算，结果与测量值符合良好。The code package of uranium hydride zirconium reactor physics calculation is established.Considering the thermalization of H in ZrH,the nuclear data of H in ZrH in WIMS library pattern are provided and WIMS N2 library is obtained.The cell parameters are calculated using WIMS D/4 code and WIMS N2 library.The diffusion calculation is performed using CITATION code and SIXTUS 2 code.The in core fuel management code XPR ICFM is obtained on the basis of SIXTUS 2 code.To check the accuracy and reliability of the code package,the critical keff and the value of the control rod of abroad TRIGA,the pulsed reactor in china are calculated.The results are satisfied.

关 键 词：铀氢锆堆 物理计算 燃料管理 软件包 

分 类 号：TL329[核科学技术—核技术及应用]