This title appears in the Scientific Report : 2010 

V.S.O.P. (99/09) Computer Code System for Reactor Physics and Fuel Cycle Simulation; Version 2009
Rütten, H.-J.
Haas, K.A. / Brockmann, H. / Ohlig, U. / Pohl, C. / Scherer, W.
Nukleare Entsorgung und Reaktorsicherheit; IEK-6
Jülich Forschungszentrum Jülich GmbH Zentralbibliothek, Verlag 2010
VIII, 154 p.
Internal Report
Nukleare Sicherheitsforschung
Berichte des Forschungszentrums Jülich 4326
OpenAccess
OpenAccess
Please use the identifier: http://hdl.handle.net/2128/12831 in citations.
V.S.O.P.(99/ 09) represents the further development of V.S.O.P.(99/ 05). Compared to its precursor, the code system has been improved again in many details. The main motivation for this new code version was to update the basic nuclear libraries used by the code system. Thus, all cross section libraries involved in the code have now been based on ENDF/B-VII. V.S.O.P. is a computer code system for the comprehensive numerical simulation of the physics of thermal reactors. It implies the setup of the reactor and of the fuel element, processing of cross sections, neutron spectrum evaluation, neutron diffusion calculation in two or three dimensions, fuel burnup, fuel shuffling, reactor control, thermal hydraulics and fuel cycle costs. The thermal hydraulics part (steady state and time-dependent) is restricted to gas-cooled reactors and to two spatial dimensions. The code can simulate the reactor operation from the initial core towards the equilibrium core.