用由ＥＮＤＦ／ＢⅣ产生的ＺｒＨ中Ｈ及Ｅｒ等元素的６９群群常数，补充了ＷＩＭＳＤ／４库中的核数据，形成了用于铀氢锆脉冲堆计算的ＷＩＭＳＣＮＤＣ库。校核了该库中ＺｒＨ中Ｈ的散射截面，并利用该库及栅元计算程序ＷＩＭＳＤ／４，计算了铀氢锆脉冲堆燃料栅元的能谱、群常数、ｋ∞、功率分布以及温度系数。最后用一维两群扩散程序ＴＲＩＧＡＰ进行了堆芯临界计算。以上结果均与有关文献符合得很好。 The WIMSCNDC library for the uranium-zirconium hydride zirconium pulse heap calculation was formed by supplementing the core data of WIMSD / 4 library with 69 group constants of elements such as H and Er in ZrH generated by ENDF / BⅣ. The cross section of H in ZrH in the library was checked, and the energy spectra, group constants, k∞, power distributions of uranyl zirconium-zirconium pulse impulse fuel cells were calculated by using WIMSD / 4. As well as the temperature coefficient. Finally, one-dimensional two-group diffusion program TRIGAP was used to calculate the criticality of the core. The above results are in good agreement with the relevant literature.