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000136219 041__ $$aEnglish
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000136219 0881_ $$aJuel-4325
000136219 088__ $$2JUEL$$aJuel-4325
000136219 1001_ $$aBrockmann, H.$$b0$$eCorresponding author$$ufzj
000136219 245__ $$aTOTMOS: An Integral Transport Code for Calculating Neutron Spectra and Multigroup Cross Sections
000136219 260__ $$aJülich$$bForschungszentrum Jülich GmbH Zentralbibliothek, Verlag$$c2010
000136219 300__ $$aIV, 79 p.
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000136219 4900_ $$aBerichte des Forschungszentrums Jülich$$v4325
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000136219 520__ $$aThis 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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