Abstract
APOLLO-II is a new-generation multigroup transport code for assembly calculation. The code has been designed to be used as a tool for reactor design as well as for the analysis and interpretation of small nuclear facilities. As the first step in a criticality calculation, the collision probability module of the APOLLO-II code can be used to generate cell or assembly homogenized reaction-rate preserving cross sections that account for self-shielding effects as well as for the fine-energy within cell flux spectral variations. These cross section data can then be used either directly within the APOLLO-II code in a direct discrete ordinate multigroup transport calculation of a small nuclear facility or, more generally, be formatted by a post-processing module to be used by the multigroup diffusion code CRONOS-II or by the multigroup Monte Carlo code TRIMARAN.
Citation Formats
Coste, M, Mathonniere, G, Sanchez, R, Stankovski, Z, Van der Gucht, C, and Zmijarevic, I.
Use of the Apollo-II multigroup transport code for criticality calculations.
France: N. p.,
1992.
Web.
Coste, M, Mathonniere, G, Sanchez, R, Stankovski, Z, Van der Gucht, C, & Zmijarevic, I.
Use of the Apollo-II multigroup transport code for criticality calculations.
France.
Coste, M, Mathonniere, G, Sanchez, R, Stankovski, Z, Van der Gucht, C, and Zmijarevic, I.
1992.
"Use of the Apollo-II multigroup transport code for criticality calculations."
France.
@misc{etde_10129282,
title = {Use of the Apollo-II multigroup transport code for criticality calculations}
author = {Coste, M, Mathonniere, G, Sanchez, R, Stankovski, Z, Van der Gucht, C, and Zmijarevic, I}
abstractNote = {APOLLO-II is a new-generation multigroup transport code for assembly calculation. The code has been designed to be used as a tool for reactor design as well as for the analysis and interpretation of small nuclear facilities. As the first step in a criticality calculation, the collision probability module of the APOLLO-II code can be used to generate cell or assembly homogenized reaction-rate preserving cross sections that account for self-shielding effects as well as for the fine-energy within cell flux spectral variations. These cross section data can then be used either directly within the APOLLO-II code in a direct discrete ordinate multigroup transport calculation of a small nuclear facility or, more generally, be formatted by a post-processing module to be used by the multigroup diffusion code CRONOS-II or by the multigroup Monte Carlo code TRIMARAN.}
place = {France}
year = {1992}
month = {Dec}
}
title = {Use of the Apollo-II multigroup transport code for criticality calculations}
author = {Coste, M, Mathonniere, G, Sanchez, R, Stankovski, Z, Van der Gucht, C, and Zmijarevic, I}
abstractNote = {APOLLO-II is a new-generation multigroup transport code for assembly calculation. The code has been designed to be used as a tool for reactor design as well as for the analysis and interpretation of small nuclear facilities. As the first step in a criticality calculation, the collision probability module of the APOLLO-II code can be used to generate cell or assembly homogenized reaction-rate preserving cross sections that account for self-shielding effects as well as for the fine-energy within cell flux spectral variations. These cross section data can then be used either directly within the APOLLO-II code in a direct discrete ordinate multigroup transport calculation of a small nuclear facility or, more generally, be formatted by a post-processing module to be used by the multigroup diffusion code CRONOS-II or by the multigroup Monte Carlo code TRIMARAN.}
place = {France}
year = {1992}
month = {Dec}
}