铀氢锆堆群常数库的生成及堆芯的物理和安全参数的计算

Generation of a Group Constants Library for Uranium Zirconium Hydride Reactor and Some Calculations of Core and Safety Parameters

应用栅元计算程序ＷＩＭＳ－Ｄ／４及含有氢化锆中氢核素数据的ＷＩＭＳ－Ｎ２核数据库，计算了我国第１座商用铀氢锆堆（西安脉冲堆）的栅元参数，生成了两群群常数随燃耗变化的数据库．用所产生的群常数库和ＴＲＩＧＡＣ程序对西安脉冲堆堆芯重要的物理和安全参数———堆芯通量分布、Ｋｅｆ随燃耗的变化、负温度系数以及功率峰因子等进行了计算，这些参数对堆芯燃料管理和核安全分析具有重要的意义．

The lattice of the first uranium zirconium hydride reactor of China (Xi′an pulsed reactor) is calculted using the WIMSD/4 code and the WIMSN2 nuclear data library which includes the data of the nuclide H in ZrH. The library of two group constants as a function of burn up is generated. Using the created library of group constants and the TRIGAC code, the reactor core safety parameters, such as the distributions of flux, K eff as a function of burn up, negative temperature coefficient, power peaking factor and so on, are calculated. They are very important for the in core fuel management and nuclear safety analysis.