%0 Report
%A Brockmann, H.
%T TOTMOS: An Integral Transport Code for Calculating Neutron Spectra and Multigroup Cross Sections
%V 4325
%N Juel-4325
%C Jülich
%I Forschungszentrum Jülich GmbH Zentralbibliothek, Verlag
%M PreJuSER-136219
%M Juel-4325
%B Berichte des Forschungszentrums Jülich
%P IV, 79 p.
%D 2010
%Z Record converted from JUWEL: 18.07.2013
%X 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.
%F PUB:(DE-HGF)29
%9 Report
%U https://juser.fz-juelich.de/record/136219