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Finite element spherical harmonics (P N ) solutions of the three-dimensional Takeda benchmark problems

A set of multi-group eigenvalue ( K eff) benchmark problems in three-dimensional homogenised reactor core configurations have been solved using the deterministic finite element transport theory code EVENT and the Monte Carlo code MCNP4C. The principal aim of this work is to qualify numerical methods...

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Bibliographic Details
Published in:Annals of nuclear energy 2005-06, Vol.32 (9), p.925-948
Main Authors: Ziver, A.K., Shahdatullah, M.S., Eaton, M.D., de Oliveira, C.R.E., Umpleby, A.P., Pain, C.C., Goddard, A.J.H.
Format: Article
Language:English
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Summary:A set of multi-group eigenvalue ( K eff) benchmark problems in three-dimensional homogenised reactor core configurations have been solved using the deterministic finite element transport theory code EVENT and the Monte Carlo code MCNP4C. The principal aim of this work is to qualify numerical methods and algorithms implemented in EVENT. The benchmark problems were compiled and published by the Nuclear Data Agency (OECD/NEACRP) and represent three-dimensional realistic reactor cores which provide a framework in which computer codes employing different numerical methods can be tested. This is an important step that ought to be taken (in our view) before any code system can be confidently applied to sensitive problems in nuclear criticality and reactor core calculations. This paper presents EVENT diffusion theory (P 1) approximation to the neutron transport equation and spherical harmonics transport theory solutions (P 3–P 9) to three benchmark problems with comparison against the widely used and accepted Monte Carlo code MCNP4C. In most cases, discrete ordinates transport theory (S N ) solutions which are already available and published have also been presented. The effective multiplication factors ( K eff) obtained from transport theory EVENT calculations using an adequate spatial mesh and spherical harmonics approximation to represent the angular flux for all benchmark problems have been estimated within 0.1% (100 pcm) of the MCNP4C predictions. All EVENT predictions were within the three standard deviation uncertainty of the MCNP4C predictions. Regionwise and pointwise multi-group neutron scalar fluxes have also been calculated using the EVENT code and compared against MCNP4C predictions with satisfactory agreements. As a result of this study, it is shown that multi-group reactor core/criticality problems can be accurately solved using the three-dimensional deterministic finite element spherical harmonics code EVENT.
ISSN:0306-4549
1873-2100
DOI:10.1016/j.anucene.2005.01.009