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Calculation of a Reactivity Initiated Accident with a 3D Cell-by-Cell Method: Application of the SAPHYR System To a Rod Ejection Accident in TMI1


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Calculation of a Reactivity Initiated Accident with a 3D Cell-by-Cell Method: Application of the SAPHYR System to a Rod Ejection Accident in TMI1 S. Aniel-Buchheit1, E. Royer2, P. Ferraresi3 1S. Aniel Buchheit, CEA/DRN/DMT/SERMA, C.E.A Saclay, 91191 Gif sur Yvette, Cedex, France Tel : 33.1.69.08.64.88, Fax : 33.1.69.08.99.35, Email : saniel@cea.fr 2E. Royer, CEA/DRN/DMT/SERMA, , C.E.A Saclay, 91191 Gif sur Yvette, Cedex, France Tel : 33.1.69.08.54.69, Fax : 33.1.69.08.85.68, Email : eric.royer@cea.fr 3P. Ferraresi, IPSN/DRS/SEMAR, , C.E.A Cadarache, 13108 St Paul lez Durance, Cedex, France Tel : 33.1.42.25.76.72, Fax : 33.1.42.25.61.43, Email : patricia.ferraresi@ipsn.fr

Type de document > *Congrès/colloque

Mots clés > code de calcul, neutronique, RIA

Unité de recherche >

Auteurs > [et al.]

Date de publication > 10/04/2000

Résumé

The 3D method for neutronic calculations of a Reactivity-Initiated Accident (RIA) in a Pressurized WaterReactor (PWR) tends now to replace the former 2D-1D evaluations. In the frame of a search of adequate penalties to apply to this new type of transient modeling, sensitivity studies on the geometrical description accuracy, on the type of physical phenomena modeled and on the values of the key physical parameters are currently undertaken by the IPSN and the CEA. 3D core neutronic calculations with a homogeneous and a heterogeneous (cell by cell) assembly modeling were compared. The influence of the axial neutroniccalculation meshing was studied. As far as thermal-hydraulics is concerned, cross flow effects were measured by a comparison of 3D and 1D core FLICA4 models (each assembly being represented by one thermal-hydraulic channel). A more accurate feedback modeling was also studied by adjusting the thermalhydraulic calculation meshes to the neutronic ones (four thermal-hydraulic channels per assembly). All these tests showed first that the power transient can be noticeably affected by the scale of the core physical modeling and by the type of physical phenomena taken into account (moderator feedback effects, core cross flowsÖ). They also have highlighted that, for each studied model parameter, a preliminary search for the "envelope transient" is necessary to be sure to evaluate its maximum impact on power transients.