Rütten, H. J.FZJ* ; Haas, K. A.FZJ* ; Pohl, C.FZJ*

2012
Forschungszentrum Jülich GmbH Zentralbibliothek, Verlag Jülich

Report No.: Juel-4348

Abstract: V.S.O.P. is a computer code system for the comprehensive numerical simulation of the physics of thermal reactors. The application of the code implies processing of cross sections, the set-up of the reactor and of the fuel element, neutron spectrum evaluation, neutron diffusion calculation, fuel burnup, fuel shuffling, reactor control, and thermal hydraulics of steady states and transients. The neutronics calculations can be performed in up to three dimensions. Thermal hydraulics is restricted to gas-cooled reactors in two spatial dimensions. Evaluation of fuel cycle costs over the reactor life time is made using the present worth method. A broad description of the features of the code has been published in Ref. /1/.

1. Nukleare Entsorgung und Reaktorsicherheit (IEK-6)