In order to simulate the calculation of related neutronics problems ,an ACE format multiple-temperature continuous energy cross section library CENACE was developed by China Nuclear Data Center .Thermal scattering data of 18 materials from ENDF/B-Ⅶ.1 were processed into ACE format with NJOY99 program on the purpose of calculating problems related to thermal neutron .In order to verify the integrity and availability of this thermal neutron ACE file ,drawing test was done for the data ,and calculation result of thermal scattering cross section was also compared with the experimental value .T he test result show s that all the ACE format data are accurate and reliable ,and there is no abnormal and unreasonable phenomenon ;for common reactor moderator materials , the new generated thermal neutron scattering data are in good agreement with experimental values except individual data need to be improved .%为模拟计算相关中子学问题，中国核数据中心研制了 ACE格式的多温度连续能量点截面库CENACE。其中，为计算热中子相关问题，采用NJOY99程序，将ENDF/B-Ⅶ.1库中18种材料的热散射率数据制成ACE格式的热中子散射数据。为验证热中子ACE文档的完整性和可用性，对加工得到的数据进行绘图测试，并将热散射截面的计算结果与实验测量值进行比较。测试结果表明，所有ACE文档数据准确可靠，不存在异常或不合理等现象；对于常见反应堆慢化剂材料，新制作的热散射数据与实验值符合良好，个别材料的热散射率评价数据有待进一步改进。
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