Extension of the GeN-Foam neutronic solver to SP3 analysis and application to the CROCUS experimental reactor

Abstract The Laboratory for Reactor Physics and Systems Behaviour at the PSI and at the EPFL has been developing since 2013 a multi-physics platform for coupled reactor analysis named GeN-Foam. The developed tool includes a solver for the eigenvalue and transient solution of multi-group neutron diffusion equations. Although frequently used in reactor analysis, the diffusion theory shows some limitations for core configurations involving strong anisotropies, which is the case for the CROCUS research reactor at the EPFL. The use of an SP 3 approximation to neutron transport can often lead to visible improvements in a code predictive capabilities, especially for one-directional anisotropies, with acceptable added computational cost vs diffusion. Following some modelling issues for the CROCUS reactor, and in order to improve the GeN-Foam modelling capabilities, the GeN-Foam diffusion solver has been extended to allow for SP 3 analyses. The present paper describes such extension and a preliminary verification using a mini-core PWR benchmark. The newly developed solver is then applied to the analysis of the CROCUS experimental reactor and results are compared to Monte Carlo calculations, as well as to the results of the diffusion solver.

[1]  C. Demazière,et al.  Fine-mesh deterministic modeling of PWR fuel assemblies: Proof-of-principle of coupled neutronic/thermal–hydraulic calculations , 2014 .

[2]  Konstantin Mikityuk,et al.  GeN-Foam: a novel OpenFOAM® based multi-physics solver for 2D/3D transient analysis of nuclear reactors , 2015 .

[3]  J. Leppänen.  Development of a New Monte Carlo reactor physics code , 2007 .

[4]  K. Ivanov,et al.  A multi-scale homogenization and reconstruction approach for solid material temperature calculations in prismatic high temperature reactor cores , 2013 .

[5]  Hrvoje Jasak,et al.  A tensorial approach to computational continuum mechanics using object-oriented techniques , 1998 .

[6]  T. Downar,et al.  Multi-group SP3 approximation for simulation of a three-dimensional PWR rod ejection accident , 2015 .

[7]  W. Stacey.  Nuclear Reactor Physics , 2001 .

[8]  Paolo Vinai,et al.  Coupled fine-mesh neutronics and thermal-hydraulics - modeling and implementation for PWR fuel assemblies , 2015 .

[9]  Soeren Kliem,et al.  The reactor dynamics code DYN3D – models, validation and applications , 2016 .

[10]  O. Geoffroy,et al.  Development of an OpenFOAM model for the Molten Salt Fast Reactor transient analysis , 2014 .

[11]  Mathieu Hursin,et al.  Methods and Models for the Coupled Neutronics and Thermal-Hydraulics Analysis of the CROCUS Reactor at EFPL , 2015 .

[12]  Konstantin Mikityuk,et al.  Development and verification of the neutron diffusion solver for the GeN-Foam multi-physics platform , 2016 .

[13]  Derek Gaston,et al.  MOOSE: A parallel computational framework for coupled systems of nonlinear equations , 2009 .

[14]  Ivor David Clifford,et al.  A hybrid coarse and fine mesh solution method for prismatic high temperature gas-cooled reactor thermal-fluid analysis , 2013 .

[15]  Edward W. Larsen,et al.  The Simplified P3 Approximation , 2000 .

[16]  K. Mikityuk,et al.  Application of the new GeN-Foam multi-physics solver to the European Sodium Fast Reactor and verification against available codes , 2015 .

[17]  M. Aufiero.  DEVELOPMENT OF ADVANCED SIMULATION TOOLS FOR CIRCULATING-FUEL NUCLEAR REACTORS , 2014 .

[18]  Enrico Sartori,et al.  Nuclear Computational Science: A Century in Review , 2010 .

[19]  J. Kloosterman,et al.  Modelling and analysis of the MSFR transient behaviour , 2014 .

[20]  Javier Jimenez Escalante,et al.  Coupling of dynamic Monte Carlo with thermal-hydraulic feedback , 2015 .

[21]  Tomasz Kozlowski,et al.  Analysis of results for the OECD/NEA and U.S. NRC PWR MOX/UO 2 core transient benchmark , 2003 .

[22]  M. A. Kalugin,et al.  A benchmark on the calculation of kinetic parameters based on reactivity effect experiments in the CROCUS reactor , 2006 .