| 1080196 |
80-Hg-196 |
New evaluation |
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Remake mf6mt5 using corrected gnash code, to fix an earlier bug. Impact is reduced sec. particle prod for new ENDF/B-VII release EVALUATION OF n + 196HG CROSS SECTIONS FOR THE ENERGY RANGE 1.0E-11 to 150 MeV This evaluation provides a complete representation of the nuclear data needed for transport, damage, heating, radioactivity, and shielding applications over the incident neutron energy range from 1.0E-11 to 150 MeV. INCIDENT NEUTRON ENERGIES < 20 MeV Below 20 MeV the evaluation is based completely on the HG-196 evaluation for JENDL-3.3 documented in (Sh97). INCIDENT NEUTRON ENERGIES > 20 MeV The evaluation above 20 MeV utilizes MF=6, MT=5 to represent all reaction data. Production cross sections and emission spectra are given for neutrons, protons, deuterons, tritons, alpha particles, gamma rays, and all residual nuclides produced (A>5) in the reaction chains. |