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铀氢锆堆物理计算及燃料管理软件包
引用本文:陈伟 陈达. 铀氢锆堆物理计算及燃料管理软件包[J]. 核动力工程, 1998, 19(4): 320-325
作者姓名:陈伟 陈达
作者单位:西安交通大学,西北核技术研究所
摘    要:
建立了一套铀氢锆堆物计算软件包,首先考虑氢化锆中的热化特殊性,按WMS格式制作 了氢化锆 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和六角形节块和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和XPR-ICF

关 键 词:铀氢锆堆 物理计算 燃料管理 软件包

Code Package of the Physics Calculation and FuelManagement of Uranium HydrideZirconium Reactor
Chen Wei Xie Zhongsheng. Code Package of the Physics Calculation and FuelManagement of Uranium HydrideZirconium Reactor[J]. Nuclear Power Engineering, 1998, 19(4): 320-325
Authors:Chen Wei Xie Zhongsheng
Abstract:
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.
Keywords:Uranium hydride zirconium reactor Physics calculation Fuel management Code package
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