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TOTMOS: An Integral Transport Code for Calculating Neutron Spectra and Multigroup Cross Sections



2010
Forschungszentrum Jülich GmbH Zentralbibliothek, Verlag Jülich

Jülich : Forschungszentrum Jülich GmbH Zentralbibliothek, Verlag, Berichte des Forschungszentrums Jülich 4325, IV, 79 p. ()

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Report No.: Juel-4325

Abstract: 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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Note: Record converted from JUWEL: 18.07.2013

Contributing Institute(s):
  1. Institut für Energieforschung (IEF)
  2. Sicherheitsforschung und Reaktortechnik (IEF-6)

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 Record created 2013-07-18, last modified 2024-07-12


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