摘要
用由ＥＮＤＦ／ＢⅣ产生的ＺｒＨ中Ｈ及Ｅｒ等元素的６９群群常数，补充了ＷＩＭＳＤ／４库中的核数据，形成了用于铀氢锆脉冲堆计算的ＷＩＭＳＣＮＤＣ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ＷＩＭＳＤ／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 69 groups constants of H in ZrH and Er generated from ENDF/B Ⅳ library are maked up into WIMS D/4 library.WIMS CNDC library is obtained which used on uranium zirconium hydride reactor calculation.The scattering cross section for H in ZrH is checked.The energy spectrum,group constants,k∞,power distribution and negative temperature coefficient of uranium zirconium hydridereactor fuel cell are calculated.The critical core is calculated by TRIGAP coed.These results agree very well with those of references.
出处
《核动力工程》
EI
CAS
CSCD
北大核心
1998年第1期7-11,42,共6页
Nuclear Power Engineering
