CAJ | 학술논문

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。
위모의계산상관중자학문제，중국핵수거중심연제료 ACE격식적다온도련속능량점절면고CENACE。기중，위계산열중자상관문제，채용NJOY99정서，장ENDF/B-Ⅶ.1고중18충재료적열산사솔수거제성ACE격식적열중자산사수거。위험증열중자ACE문당적완정성화가용성，대가공득도적수거진행회도측시，병장열산사절면적계산결과여실험측량치진행비교。측시결과표명，소유ACE문당수거준학가고，불존재이상혹불합리등현상；대우상견반응퇴만화제재료，신제작적열산사수거여실험치부합량호，개별재료적열산사솔평개수거유대진일보개진。
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 .