Abstract
Nuclear data evaluation for {sup 237}U, {sup 236}Np and {sup 238}Np was made in the neutron energy range from 10{sup -5} eV to 20 MeV. Quantities evaluated are the total, elastic and inelastic scattering, capture, fission, (n,2n) and (n,3n) reaction cross sections, the angular and energy distributions of secondary neutrons, and the number of neutrons emitted per fission. Since experimental data are very scarce for these nuclides, the evaluation was made on the basis of optical and statistical model calculations, and systematics of data. Results were complied in ENDF format. (author).
Nakagawa, Tsuneo;
Kikuchi, Yasuyuki
[1]
- Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
Citation Formats
Nakagawa, Tsuneo, and Kikuchi, Yasuyuki.
Evaluation of nuclear data of {sup 237}U, {sup 236}Np and {sup 238}Np.
Japan: N. p.,
1994.
Web.
Nakagawa, Tsuneo, & Kikuchi, Yasuyuki.
Evaluation of nuclear data of {sup 237}U, {sup 236}Np and {sup 238}Np.
Japan.
Nakagawa, Tsuneo, and Kikuchi, Yasuyuki.
1994.
"Evaluation of nuclear data of {sup 237}U, {sup 236}Np and {sup 238}Np."
Japan.
@misc{etde_10156042,
title = {Evaluation of nuclear data of {sup 237}U, {sup 236}Np and {sup 238}Np}
author = {Nakagawa, Tsuneo, and Kikuchi, Yasuyuki}
abstractNote = {Nuclear data evaluation for {sup 237}U, {sup 236}Np and {sup 238}Np was made in the neutron energy range from 10{sup -5} eV to 20 MeV. Quantities evaluated are the total, elastic and inelastic scattering, capture, fission, (n,2n) and (n,3n) reaction cross sections, the angular and energy distributions of secondary neutrons, and the number of neutrons emitted per fission. Since experimental data are very scarce for these nuclides, the evaluation was made on the basis of optical and statistical model calculations, and systematics of data. Results were complied in ENDF format. (author).}
place = {Japan}
year = {1994}
month = {Feb}
}
title = {Evaluation of nuclear data of {sup 237}U, {sup 236}Np and {sup 238}Np}
author = {Nakagawa, Tsuneo, and Kikuchi, Yasuyuki}
abstractNote = {Nuclear data evaluation for {sup 237}U, {sup 236}Np and {sup 238}Np was made in the neutron energy range from 10{sup -5} eV to 20 MeV. Quantities evaluated are the total, elastic and inelastic scattering, capture, fission, (n,2n) and (n,3n) reaction cross sections, the angular and energy distributions of secondary neutrons, and the number of neutrons emitted per fission. Since experimental data are very scarce for these nuclides, the evaluation was made on the basis of optical and statistical model calculations, and systematics of data. Results were complied in ENDF format. (author).}
place = {Japan}
year = {1994}
month = {Feb}
}