压水堆燃耗数据库制作研究
Research on Development of Burnup Library for PWR

燃耗数据库的精准性是影响燃耗计算结果精准性的主要因素。本文开发了燃耗库加工程序PSTL，并基于评价核数据库ENDF/B-VIII.0、EAF-2010和TENDL-2019制作了一个用于ORIGEN-S程序的压水堆燃耗数据库。该数据库包含两个子库：中子截面-裂变产额库和衰变库。中子截面数据首先应用NJOY2016程序将ENDF/B-VIII.0等评价库中的点连续截面处理为172群截面，然后采用指定燃耗深度下的组件或栅元中子能谱将172群截面并为三群截面；裂变产额数据取自MF8/MT454和MT459；衰变数据取自MF8/MT457。最后采用OECD/NEA机构的压水堆核素积存量基准题进行验证分析，结果表明：中子能谱对燃耗库以及核素积存量有显著影响，对于²³⁸Pu、²³⁷Np和¹⁴⁷Sm等核素，由组件中子能谱所加工的燃耗库的计算结果更接近实验值，提高了ORIGEN-S的计算精度。
The accuracy of burnup library is the main factor affecting the accuracy of burnup calculation results. In this paper, the library processing program PSTL is developed, and a PWR burnup library for ORIGEN-S program is made based on the evaluated nuclear libraries ENDF/B-VIII.0, EAF-2010 and TENDL-2019. The library contains two sublibraries, namely neutron cross section-fission yield library and decay library. First, the point continuous cross sections in ENDF/B-VIII.0 evaluated library and so on are processed into 172-group cross sections by NJOY2016 program. Then the 172-group cross section is further merged into three-group cross sections by using the neutron spectrum of the assembly or cell at the specified burnup depth. Fission yield data are taken from MF8/MT454 and MT459. Decay data are taken from MF8/MT457. Finally, the benchmark of nuclide inventory in PWR of OECD/NEA is used to verify and analyze. The results show that the neutron energy spectrum has a significant effect on burnup library and nuclide inventory. For such nuclides as ²³⁸Pu, ²³⁷Np and ¹⁴⁷Sm, the calculated results of the burnup library processed by the assembly neutron spectrum are closer to the experimental values, which improves the calculation accuracy of ORIGEN-S.