中文摘要：

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。

英文摘要：

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.