Report

FZJ-2016-06004

http://join2-wiki.gsi.de/foswiki/pub/Main/Artwork/join2_logo100x88.png V.S.O.P.(97) Computer Code System for Reactor Physics and Fuel Cycle Simulation : Input Manual and Comments

Rütten, H. J.FZJ* ; Haas, K. A.FZJ* ; Brockmann, H.FZJ* ; Ohlig, U.FZJ* ; Scherer, W.FZJ*

1998
Forschungszentrum Jülich GmbH Zentralbibliothek, Verlag Jülich

Please use a persistent id in citations: http://hdl.handle.net/2128/12755

Report No.: Juel-3522

Abstract: V.S.O.P. (97) is a computer code system for the comprehensive numerical simulation ofthe physics of thermal reactors. It implies processing ofcross sections, the setup ofthe reactor and ofthe fuel element, repeated 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 EM and to two spatial dimensions. V.S.O.P (97) can simulate the reactor operation from the initial core towards the equilibrium core. V.S.O.P. 97 - on the basis of V.S.O.P. 94 - has been improved with regard to a more detailed treatment of the build-up and the depletion of the heavy metal isotopes. Their chains now include theminor actinides. Resonance cross sections of the lumped resonance absorbers are evaluated burnup-dependent. Beyond this, the code has been reviewed in many details, aiming at an improved precision in the computer simulation ofthe features ofthe reactors and oftheir fuel cycle. The code consists of about 65400 FORTRAN statements. A memory of 32 MB should be available for its use.

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Contributing Institute(s):

1. Publikationen vor 2000 (PRE-2000)

Research Program(s):

1. 899 - ohne Topic (POF3-899) (POF3-899)

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Database coverage:

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