Nuclear Data Evaluations for JENDL High‐Energy File
Nuclear Data Evaluations for JENDL High‐Energy File
复制标题
JENDL 高能文件的核数据评估
DOI:
10.1063/1.1945015
复制
发表时间:
2005
影响因子:
1.4
通讯作者:
S. Chiba
中科院分区:
文献类型:
--
作者:
Y. Watanabe;T. Fukahori;K. Kosako;N. Shigyo;T. Murata;N. Yamano;T. Hino;K. Maki;H. Nakashima;N. Odano;S. Chiba
An overview is presented of recent nuclear data evaluations performed for the JENDL high‐energy (JENDL‐HE) file, in which neutron and proton cross sections for energies up to 3 GeV are included for the whole 132 nuclides. The current version of the JENDL‐HE file consists of neutron total cross sections, nucleon elastic scattering cross sections and angular distributions, nonelastic cross sections, production cross sections and double‐differential cross sections of secondary light particles (n, p, d, t, 3He, α, and π) and gamma‐rays, isotope production cross sections, and fission cross sections in the ENDF6 format. The present evaluations are performed on the basis of experimental data and theoretical model calculations. For the cross section calculations, we have constructed a hybrid calculation code system with some available nuclear model codes and systematics‐based codes, such as ECIS96, OPTMAN, GNASH, JQMD, JAM, TOTELA, FISCAL, and so on. The evaluated cross sections are compared with available experimental data and the other evaluations. Future plans of our JENDL‐HE project are discussed along with prospective needs for high‐energy cross section data.An overview is presented of recent nuclear data evaluations performed for the JENDL high‐energy (JENDL‐HE) file, in which neutron and proton cross sections for energies up to 3 GeV are included for the whole 132 nuclides. The current version of the JENDL‐HE file consists of neutron total cross sections, nucleon elastic scattering cross sections and angular distributions, nonelastic cross sections, production cross sections and double‐differential cross sections of secondary light particles (n, p, d, t, 3He, α, and π) and gamma‐rays, isotope production cross sections, and fission cross sections in the ENDF6 format. The present evaluations are performed on the basis of experimental data and theoretical model calculations. For the cross section calculations, we have constructed a hybrid calculation code system with some available nuclear model codes and systematics‐based codes, such as ECIS96, OPTMAN, GNASH, JQMD, JAM, TOTELA, FISCAL, and so on. The evaluated cross sections are compared with available experi...