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Evaluation of neutron nuclear data for Technetium-99
Authors:Nobuyuki Iwamoto
Affiliation:1. Nuclear Data Center, Nuclear Science and Engineering Directorate, Japan Atomic Energy Agency , Tokai , Ibaraki , 319-1195 , Japan iwamoto.nobuyuki@jaea.go.jp
Abstract:Neutron nuclear data of 99Tc was evaluated, considering cross-sections and spectra provided from recent experiments. The evaluation was made in the incident neutron energy range from 1 keV to 20 MeV, using the optical model and nuclear reaction models. The optical model calculation based on the coupled-channels method was performed for the interaction of neutrons with 99Tc, and potential parameters appropriately chosen reasonably explain the measured data of total cross-section. The cross-section of inelastic scattering, capture, (n, 2n), (n, p), (n, α) and (n, nα) reactions, and γ-ray emission spectra were calculated on the basis of statistical model with preequilibrium and direct components, and they were compared with available experimental data. It is found that the presently evaluated cross-sections and γ-ray emission spectra well reproduce those experimental values and that there is a large discrepancy among the present result and evaluated data for neutron emission spectra. The obtained capture cross-section increases at the energies below 1 MeV, relative to that in JENDL-4.0. This makes the transmutation efficiency of 99Tc into stable 100Ru by accelerator driven system enhanced. The production cross-section of 99Mo important for the medical use of nuclear diagnostics reduces by 5–30% at the energies above 12 MeV, compared with JENDL-4.0.
Keywords: evaluation    neutron nuclear data    cross-section    spectrum    fission product    Technetium-99    radioactive waste    Molybdenum-99    nuclear diagnostics    Maxwellian-averaged capture cross-section
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