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| 005 | 20240712084608.0 | ||
| 024 | 7 | _ | |2 ISSN |a 0944-2952 |
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| 088 | 1 | _ | |a Juel-4325 |
| 088 | _ | _ | |a Juel-4325 |2 JUEL |
| 100 | 1 | _ | |a Brockmann, H. |b 0 |e Corresponding author |u fzj |
| 245 | _ | _ | |a TOTMOS: An Integral Transport Code for Calculating Neutron Spectra and Multigroup Cross Sections |
| 260 | _ | _ | |a Jülich |b Forschungszentrum Jülich GmbH Zentralbibliothek, Verlag |c 2010 |
| 300 | _ | _ | |a IV, 79 p. |
| 336 | 7 | _ | |0 PUB:(DE-HGF)29 |2 PUB:(DE-HGF) |a Report |m report |
| 336 | 7 | _ | |2 DataCite |a Output Types/Report |
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| 336 | 7 | _ | |2 DRIVER |a report |
| 490 | 0 | _ | |a Berichte des Forschungszentrums Jülich |v 4325 |
| 500 | _ | _ | |a Record converted from JUWEL: 18.07.2013 |
| 520 | _ | _ | |a This report describes the TOTMOS code, which calculates the scalar neutron spectrum in a reactor cell as a function of the position by the collision probability method. One-dimensional cylindrical or spherical geometries can be treated. The neutron spectrum is used to compute cell-weighted cross sections, which can be used in gross reactor calculations. Furthermore, "equivalent" cross sections are calculated, which are employed to study the efficiency of absorber rods in a reactor on the basis of the diffusion theory. |
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