~(239)Pu是反应堆的重要核材料之一,它的全套评价中子核数据在反应堆工程设计中有着重要的应用。本评价是在实验数据分析评价和核理论模型计算的基础上进行的。入射中子能区为10~(-5)eV到20MeV,数据类型包括文档1—5,即给出了裂变平均中子数■ ~ (239) Pu is one of the important nuclear materials of the reactor. Its complete evaluation of neutron data has important applications in reactor engineering design. This evaluation is based on experimental data analysis and evaluation and nuclear theoretical model based on the calculation. The incident neutron energies range from 10 -5 eV to 20 MeV and the data types include documents 1-5, which gives the average fissile neutron number