基于评价核数据库的燃耗数据库制作及验证  

Process and Validation of Depletion Database Based on Evaluated Nuclear Data Libraries

作　　者：骆浩 李杰 黄善仿[1] 王侃[1] LUO Hao;LI Jie;HUANG Shanfang;WANG Kan(Department of Engineering Physics,Tsinghua University,Beijing 100084,China)

机构地区：[1]清华大学工程物理系,北京100084

出　　处：《原子能科学技术》2024年第7期1505-1513,共9页Atomic Energy Science and Technology

摘　　要：核反应堆燃料组成及辐照特性分析对于反应堆设计、取证、安全分析及退役具有重要的支撑作用。精细的燃耗、活化及源项分析需要数据库提供包括衰变常量、衰变反应分支比、衰变辐射谱、衰变能、中子反应截面、裂变产物产额等关键参数。本文基于评价核数据库,包括ENDF/B-Ⅷ.0、ENDF/B-Ⅶ.1、JEFF-3.3和JENDL-5等,开展精细燃耗数据库加工方法研究。使用自主研发的数据库制作程序ALG(Automatic Library Generator),制作了基于HDF5格式的燃耗核数据库,同时分析了不同数据库中关键核素的关键参数的差异。基于最新制作的数据库,反应堆蒙特卡罗程序RMC中的点燃耗子程序DEPTH的数据库得到了显著提升,包括新增衰变辐射谱、能量依赖的裂变产物产额以及细群中子反应截面参数,为开展更精细的核燃料循环研究奠定了基础。Analysis of nuclear reactor fuel composition and irradiation characteristics plays a crucial role in reactor design,licensing,safety analysis,and decommissioning.Through in-depth analysis of fuel composition and irradiation processes,it is possible to assess reactor performance,predict fuel lifespan and behavior,and optimize fuel management strategies.To conduct accurate and comprehensive analyses,a robust and reliable database is essential.This database should provide a wide range of key parameters that are vital for fuel analysis,including decay constants,decay branching ratios,decay radiation spectra,decay energies,neutron reaction cross sections,and fission product yields.These parameters are necessary for modeling and simulating the behavior of nuclear materials under different irradiation conditions.In this study,the focus was on developing an advanced methodology for processing refined depletion databases.Several evaluated nuclear databases,including ENDF/B-Ⅷ.0,ENDF/B-Ⅶ.1,JEFF-3.3,and JENDL-5,were utilized as sources of nuclear data.The researchers developed a specialized database generation program called ALG(automatic library generator)to facilitate the creation of a high-quality depletion nuclear database.The resulting database was designed using the HDF5 format,which offers efficient storage and retrieval of large amounts of data.Comparative analyses were conducted to assess the differences in key parameters of critical nuclides among the different evaluated nuclear databases.Three validation cases were conducted,including the pure decay of ^(237)Np,the neutron activation of UO_(2),and the pulse fission case of ^(235)U.In the first case,which involved the decay of ^(237)Np,excellent results were achieved,with only slight differences observed for short-lived nuclides when compared to the ORIGEN databases.Significant differences were observed in the UO_(2) activation cases,primarily due to variations in neutron cross sections resulting from different neutron weight spectra.These discrepancies highlig

关 键 词：燃耗 活化 源项 数据库 RMC 

分 类 号：TL329[核科学技术—核技术及应用]