PWR-GALE是美国核管会编制并使用的压水堆核电厂气液态流出物源项计算程序,现有的配套核数据库已有长达四十年之久未进行更新,无法确定是否能够满足先进压水堆的计算和审评需求,需要通过基于最新版本的核评价数据库制作新的配套数据库对其进行适用性的评价.因此,本文基于核评价数据库ENDF/B-Ⅶ.0,提取衰变子库中相关信息,根据直接裂变产额、衰变信息以及保留的裂变产物核素得到更新的沿衰变链归并的产额数据,通过中子学-燃耗耦合计算获得了更新的中子微观反应截面数据;并与现有的配套数据库进行了对比分析;然后,通过计算一系列面向不同机型的算例进行了整体的对比验证与分析.结果表明:现有的PWR-GALE配套核数据可以满足先进压水堆的计算和评审需求.%PWR-GALE is a computation code that was coded and used by the U.S.Nuclear Regulatory Commission to calculate the releases of radioactive material in liquid effluents of Pressurized Water Reactor nuclear power plant.However,the corresponding nuclear library has remained unchanged for over 40 years;as a consequence it has become an unresolved question of whether the code is applicable to advanced PWR for regulatory purposes.The applicability evaluation urges the need of updating the nuclear library based on latest versions of evaluated nuclear data libraries.Therefore,this paper utilized ENDF/B-Ⅶ.0 as the initial data source to update the nuclear library.More specifically,the decay data was extracted and applied accordingly;the cumulative fission product yields were obtained by cumulating the fission product yields along decay chains on the basis of independent fission yield data,decay data and reserved nuclides;the neutron microscopic cross section data were calculated updated through coupled neutronic-depletion calculations.The direct data comparisons were carried out between the updated and the original nuclear libraries.Then a series of test cases with varying reactor types were calculated for integral verifications and analysis.Numerical results showed that the original nuclear library is applicable to regulatory purposes of advanced PWR.
展开▼
