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MENDF—一个计算200 MeV以下裂变核数据的程序(英文)
引用本文:蔡崇海.MENDF—一个计算200 MeV以下裂变核数据的程序(英文)[J].原子核物理评论,2011,28(4):489-497.
作者姓名:蔡崇海
作者单位:南开大学物理科学学院, 天津 300071
摘    要:基于球型光学模型、 预平衡发射和Hauser-Feshbach统计等理论, 编制了MENDF(Medium Energy Nuclear Data for Fission)程序, 该程序适用于裂变核在入射粒子能量低于200 MeV的中低能区的全套核数据计算。 对于中子和质子在200 MeV以下诱发的核反应, 其全截面、 反应截面、 弹性散射微分截面、 裂变截面和裂变中子谱、 5种发射粒子的单举截面和相应的能谱等理论计算值与相应的实验值基本符合。 MENDF在我国已被广泛用于核数据计算及建立中能核数据库。Based on the spherical optical model, pre equilibrium and Hauser Feshbach statistical theory, the code MENDF (Medium Energy Nuclear Data for Fission) is written to calculate a complete set of nuclear data for fission nuclei in the medium low energy region (≤200 MeV). For neutron and proton induced reactions below 200 MeV, the total cross sections, reaction cross sections, elastic scattering differential cross sections, fission cross section, energy spectra of fission neutron and five kinds of emitting particles, etc. are calculated by MENDF. The calculated data generally agree with their corresponding experimental data. MENDF is widely used for nuclear data calculation and to establish ENDF 6 formatted files for the medium low energy region in China.

关 键 词:MENDF程序    裂变    核反应    核数据
收稿时间:1900-01-01

MENDF—A Code for Calculating Nuclear Data of Fission Nuclei below 200 MeV
CAI,Chong-hai.MENDF—A Code for Calculating Nuclear Data of Fission Nuclei below 200 MeV[J].Nuclear Physics Review,2011,28(4):489-497.
Authors:CAI  Chong-hai
Institution:Institute of Physics, Nankai University, Tianjin 300071, China
Abstract:Based on the spherical optical model, pre equilibrium and Hauser Feshbach statistical theory, the code MENDF (Medium Energy Nuclear Data for Fission) is written to calculate a complete set of nuclear data for fission nuclei in the medium low energy region (≤200 MeV). For neutron and proton induced reactions below 200 MeV, the total cross sections, reaction cross sections, elastic scattering differential cross sections, fission cross section, energy spectra of fission neutron and five kinds of emitting particles, etc. are calculated by MENDF. The calculated data generally agree with their corresponding experimental data. MENDF is widely used for nuclear data calculation and to establish ENDF 6 formatted files for the medium low energy region in China.
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