Abstract
The procedure to calculate the effective cross section in the criticality safety evaluation code system JACS was to interpolate the Multigroup Cross Section Library MGCL with respect to the background cross section. For a reference calculation to the calculation following the Bondarenko method, a computational module RABTH has been developed to obtain the eigen ultra-fine (64,194 group) neutron flux with the collision probability method and the effective cross section by weighting with the flux. In the RABTH code module, the neutron source has an energy spectrum of fission neutrons from {sup 235}U. The module utilizes the RABBLE code to solve the equations for one-dimensional cells in the fast energy groups, higher than about 1.9 eV, and the THERMOS code in the thermal energy groups, less than this energy. In this way the neutron flux distribution that covers the whole energy range is obtained. Both codes have been extended to treat not only slab and cylindrical cells but also a spherical cell in both complete reflective and vacuum boundary conditions, and the THERMOS code has been further revised for higher precision. This report includes practical information to treat RABTH module and basic equations for the extension and revision made to RABBLE
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Naito, Yoshitaka;
Okuno, Hiroshi;
[1]
Okuda, Yasuhisa
- Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
Citation Formats
Naito, Yoshitaka, Okuno, Hiroshi, and Okuda, Yasuhisa.
A manual for RABTH, a code module to build effective cross section by solving one-dimensional ultra-fine energy group transport equation.
Japan: N. p.,
1993.
Web.
Naito, Yoshitaka, Okuno, Hiroshi, & Okuda, Yasuhisa.
A manual for RABTH, a code module to build effective cross section by solving one-dimensional ultra-fine energy group transport equation.
Japan.
Naito, Yoshitaka, Okuno, Hiroshi, and Okuda, Yasuhisa.
1993.
"A manual for RABTH, a code module to build effective cross section by solving one-dimensional ultra-fine energy group transport equation."
Japan.
@misc{etde_10131619,
title = {A manual for RABTH, a code module to build effective cross section by solving one-dimensional ultra-fine energy group transport equation}
author = {Naito, Yoshitaka, Okuno, Hiroshi, and Okuda, Yasuhisa}
abstractNote = {The procedure to calculate the effective cross section in the criticality safety evaluation code system JACS was to interpolate the Multigroup Cross Section Library MGCL with respect to the background cross section. For a reference calculation to the calculation following the Bondarenko method, a computational module RABTH has been developed to obtain the eigen ultra-fine (64,194 group) neutron flux with the collision probability method and the effective cross section by weighting with the flux. In the RABTH code module, the neutron source has an energy spectrum of fission neutrons from {sup 235}U. The module utilizes the RABBLE code to solve the equations for one-dimensional cells in the fast energy groups, higher than about 1.9 eV, and the THERMOS code in the thermal energy groups, less than this energy. In this way the neutron flux distribution that covers the whole energy range is obtained. Both codes have been extended to treat not only slab and cylindrical cells but also a spherical cell in both complete reflective and vacuum boundary conditions, and the THERMOS code has been further revised for higher precision. This report includes practical information to treat RABTH module and basic equations for the extension and revision made to RABBLE and THERMOS codes. (author).}
place = {Japan}
year = {1993}
month = {Sep}
}
title = {A manual for RABTH, a code module to build effective cross section by solving one-dimensional ultra-fine energy group transport equation}
author = {Naito, Yoshitaka, Okuno, Hiroshi, and Okuda, Yasuhisa}
abstractNote = {The procedure to calculate the effective cross section in the criticality safety evaluation code system JACS was to interpolate the Multigroup Cross Section Library MGCL with respect to the background cross section. For a reference calculation to the calculation following the Bondarenko method, a computational module RABTH has been developed to obtain the eigen ultra-fine (64,194 group) neutron flux with the collision probability method and the effective cross section by weighting with the flux. In the RABTH code module, the neutron source has an energy spectrum of fission neutrons from {sup 235}U. The module utilizes the RABBLE code to solve the equations for one-dimensional cells in the fast energy groups, higher than about 1.9 eV, and the THERMOS code in the thermal energy groups, less than this energy. In this way the neutron flux distribution that covers the whole energy range is obtained. Both codes have been extended to treat not only slab and cylindrical cells but also a spherical cell in both complete reflective and vacuum boundary conditions, and the THERMOS code has been further revised for higher precision. This report includes practical information to treat RABTH module and basic equations for the extension and revision made to RABBLE and THERMOS codes. (author).}
place = {Japan}
year = {1993}
month = {Sep}
}