New Evaluation of Neutron Nuclear Data for Zinc Isotopes

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Neutron nuclear data of 99 Tc 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 coupledchannels method was performed for the interaction of neutrons with 99 Tc, 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, a) and (n, n 0 a) reactions, and g-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 g-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 crosssection increases at the energies below 1 MeV, relative to that in JENDL-4.0. This makes the transmutation efficiency of 99 Tc into stable 100 Ru by accelerator driven system enhanced. The production cross-section of 99 Mo important for the medical use of nuclear diagnostics reduces by 5-30% at the energies above 12 MeV, compared with JENDL-4.0.

Section: (N P) Reaction Cross-sectionsupporting

confidence: 80%

Section: Evaluation Methodsmentioning

confidence: 77%

Evaluation of neutron nuclear data for Technetium-99

Iwamoto

2012

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“…The theoretical models used to calculate the reaction cross sections were almost the same as those in the previous evaluation of neutron nuclear data for zinc isotopes. 13) However, since there are a few modifications for the present work, the current setup in this evaluation is described in this section.…”

Section: Nuclear Reaction Modelsmentioning

confidence: 99%

Neutron Nuclear Data Evaluation of Cesium Isotopes for JENDL-4.0

Iwamoto

2011

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For the development of JENDL-4.0, neutron nuclear data for fission product nuclides, 133;134;135;136;137 Cs, were revised in the incident neutron energy range from 1 eV to 20 MeV by using a coupled-channels optical model (OM), and nuclear reaction models. The OM potential parameters were determined for stable 133 Cs to reproduce the experimental data of total and elastic scattering cross sections and angular distributions of elastically scattered neutrons. The present results reasonably reproduce measured data for (n; 2n), (n; p), (n; ), and capture reactions on 133 Cs. Cs production is marginally consistent with measured data. However, a large discrepancy is recognized for 138m Cs production. The -ray emission data were evaluated with available measurements, and newly compiled in JENDL-4.0. Maxwellian-averaged capture cross sections were calculated in the energy range from 1 to 10 3 keV, and are compared with other derived data.

“…Although they provide important activation data in a wide energy range, the measured data are sometimes considerably larger than other experimental data or evaluated data, as seen in Refs. [39,54,55]. After changing various model parameters, it was found that fitting to the data of Bormann et al [53] led to poor reproduction of the other reaction cross sections of 69 Ga.…”

Section: Comparison With Experimental and Other Evaluated Data In Thementioning

confidence: 99%

Evaluation of neutron nuclear data for gallium

Shibata

2013

Neutron nuclear data on 69,71 Ga have been evaluated for the next version of the Japanese Evaluated Nuclear Data Library (JENDL) general purpose file in the energy region from 10 −5 eV to 20 MeV. The resolved resonance parameters at negative energies were adjusted so as to reproduce measured thermal capture cross sections. The statistical model was applied to calculate the cross sections above the resolved resonance region. In the calculations, coupled-channel optical model parameters were used for neutrons. Preequilibrium and direct-reaction processes were taken into account in addition to the compound process. The present evaluation is consistent with available experimental data. The evaluated data are compiled into an ENDF-formatted data file.