MCNP温度相关热中子散射数据库研制  

Development of Temperature Related Thermal Neutron Scattering Database for MCNP

作　　者：梅龙伟[1,2] 蔡翔舟[1] 蒋大真[1] 陈金根[1] 郭威[1] 

机构地区：[1]中国科学院上海应用物理研究所,上海201800 [2]中国科学院大学,北京100049

出　　处：《核科学与工程》2013年第4期362-367,403,共7页Nuclear Science and Engineering

基　　金：中国科学院战略先导科技专项资助;任务编号XDA02010100;自然科学基金(10805067)

摘　　要：基于ENDF/B-Ⅶ中子库,完成了针对熔盐堆的慢化剂热中子散射库thermal库的制作。温度点选取为熔盐堆特征温度。针对加工的ACE格式热中子散射库进行了热散射截面分析,并通过了基准题的积分检验,同时还与MCNP自带热中子散射库tmccs做了对比,偏差在合理范围内,证明得到的热散射库可以用作熔盐堆设计。Based on ENDF/B-VIIneutron library, the thermal neutron scattering library S（α,β） for molten salt reactor moderatorswas developed. The temperatures of this library were chose as the characteristic temperatureof the molten salt reactor. Thecross section of the thermal neutron scattering of ACE format was investigated, and this library was also validated by the benchmarks of ICSBEP. The uncertainties shown in the validation were in reasonable range when compared with the thermal neutron scattering library tmccs which included inthe MCNP data library. It was proved that the thermal neutron scattering library processed in this study could be used in the molten salt reactor design.

关 键 词：慢化剂 热中子散射 NJOY S(α β) 

分 类 号：TL329.3[核科学技术—核技术及应用]