摘要
基于最新发布的评价核数据库ENDF/B-VII.1,以重要介质轻水和重水、氢化锆、石墨等材料为例,详细地说明了采用NJOY加工热化截面库的方法。将自制库与MCNP自带的基于ENDF/B-V的热化截面库tmccs进行比较分析,并开展了微观截面比对和积分计算。验证结果表明,自制库K_(inf)计算结果与tmccs库总体偏差很小,可以用于超临界水冷堆相关中子学参数的计算。
Based on the recently released ENDF/B-VII.1 library, light water and heavy water, zirconium hydride and graphite were used to develop the thermal scatting library. The available thermal scatting library named tmccs (from ENDF/B-V) released with MCNP were investigated and compared with the self-produced scatting library. The validation of the self-produced scatting library was done by comparing cross-section and integral calculation. The results of Kinf showed that there is only a little difference between the two libraries,which means the self-produced scatting library can be used to calculate the neutronics parameters of the supercritical water-cooled reactors.
出处
《科学技术与工程》
北大核心
2013年第5期1165-1169,共5页
Science Technology and Engineering
基金
国家自然科学基金重大研究计划(91126018/A050504)
湖南省教育厅项目(12C0333)资助