热能区入射中子能量变化范围是1×10-5~5 eV，在这一范围内的中子能量与反应堆内材料靶核热运动的能量相当，中子与靶核的反应过程与其他能区截然不同。在该能区，需要考虑中子与堆内材料发生散射时，化学键、晶格结构以及分子热运动对反应过程的显著影响，对不同类型的材料，需要使用不同的理论方法和处理手段得到供输运程序使用的热化数据。基于热化数据处理的相关理论，研究了热中子散射数据的处理方法，同时在自主研发核数据处理软件RXSP中，开发了相应的核数据处理模块Thermc。在此基础上，使用Thermc模块基于ENDF/BVII.1核数据库加工得到热中子散射数据，经过与经典核数据处理软件NJOY的相应结果的微观比较以及若干宏观基准题检验，热化数据精度与准确性得到充分验证。

The incident energy of thermal neutron ranges from 1×10-5 eV to 5 eV, which is comparable to energy of thermal motion of nuclide in the reactor, the reactions between neutron and target have vastly different characteristic in this energy range. The considerable effect of chemical bond, crystal lattice structure and thermal motion need to be taken into account. Distinct theoretical and processing methods have to be employed for different materials to obtain thermal scattering data used for transport codes. Correlative processing methods for thermal scattering data are introduced in this paper, Thermc module used for processing thermal scattering data was developed based on some of these methods. In addition, thermal scattering data result from Thermc module of RXSP and Thermr module of NJOY were compared in detail, macro examination was also carried out base on benchmark, results of comparison and examination demonstrate that data from Thermc are accurate.