铀氢锆脉冲堆堆芯核安全参数的计算

Study of nuclear safety parameters of uranium zirconium hydride pulsed research reactor core

摘要: 应用自己扩充的含有氢化锆中氢、铒-166和铒-167核素数据的WIMS-N1/N2数据库以及国际通用的栅元计算程序WIMS-D/4和六角形节块程序SIXTUS,分析了铀氢锆脉冲堆堆芯重要的核安全参数:功率峰因子和燃料负温度系数。

Abstract: By using lattice calculation code WIMS-D/4,hexagonal nodal diffusion code SIXTUS and the WIMS-N1/N2 library which include the data of the nuclide H in ZrH,Er-166 and Er-167,nuclear safety parameters are analyzed of uranium zirconium hydride pulsed reactor core,power peaking factor and fuel temperature coefficient.