Evaluation of Neutron Nuclear Data on Hafnium Isotopes for JENDL-4
スポンサーリンク
概要
- 論文の詳細を見る
Neutron nuclear data on 174,176,177,178,179,180,181,182Hf have been evaluated for the evaluated nuclear data library JENDL-4 in the energy region from 10−5 eV to 20 MeV. The resolved resonance parameters of the previous library JENDL-3.3 were updated by considering recent measurements. The statistical model was applied to calculate the cross sections above the resolved resonance region. Neutron transmission coefficients were obtained by the coupled-channel method, together with the total cross sections, the shape elastic scattering cross sections, and the direct-reaction components of inelastic scattering cross sections. Preequilibrium and direct-reaction processes were taken into account in addition to the compound process. The present evaluation is almost consistent with available experimental data, and it is compiled into JENDL-4.
- 2010-02-01
著者
-
SHIBATA Keiichi
Nuclear Data Center, Japan Atomic Energy Agency
-
Shibata Keiichi
Nuclear Data Center Japan Atomic Energy Agency
関連論文
- Evaluation of Neutron Nuclear Data on Hafnium Isotopes for JENDL-4
- Evaluation of Neutron Nuclear Data on Arsenic-75 for JENDL-4
- Calculation of Neutron Cross Sections on ^Zr for JENDL-4
- Calculation of Neutron Nuclear Data on Selenium Isotopes for JENDL-4
- Evaluation of Neutron Nuclear Data on Bromine and Krypton Isotopes for JENDL-4.0
- Evaluation of Neutron Nuclear Data for Mercury
- Calculation of Neutron Nuclear Data on Rubidium and Strontium Isotopes for JENDL-4
- Calculation of Neutron Nuclear Data on Molybdenum Isotopes for JENDL-4
- Calculation of Neutron Cross Sections on ^Y for JENDL-4
- Calculation of Neutron Cross Sections on ^Nb for JENDL-4
- Calculation of Neutron Nuclear Data on Silicon Isotopes for JENDL-4
- Uranium-235 Neutron Capture Cross Section at keV Energies
- Evaluation of Neutron Nuclear Data on Bromine and Krypton Isotopes for JENDL-4.0
- Evaluation of Covariance Data for Chromium, Iron and Nickel Contained in JENDL-3. 2
- Uncertainty Analyses of Neutron Cross Sections for Nitrogen-15, Lead-206,207,208, Bismuth-209, Plutonium-238, Americium-242m, and Curium-244 in JENDL-3.3
- Evaluation of the ^Bi/^Bi Branching Ratio of the ^Bi(n,γ)^Bi Cross Section in the Neutron Energy Range from 200keV to 3.0 MeV
- Evaluation of neutron nuclear data for erbium