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CAST3M modelling of a spent fuel assembly bending during a handling accident Rod failure risk evaluation from the experimental results of spent fuel rod bending test

Published online by Cambridge University Press:  20 June 2014

C. Guerin
Affiliation:
CEA, DEN, DANS, DM2S, SEMT, LM2S, 91191 Gif-sur-Yvette, France
T. Laporte
Affiliation:
CEA, DEN, DANS, DM2S, SEMT, DYN, 91191 Gif-sur-Yvette, France
C. Cappelaere
Affiliation:
CEA, DEN, DMN, SEMI, DIR, 91191 Gif-sur-Yvette, France
C. Vaille
Affiliation:
CEA, DEN, DMN, SEMI, LCMI, 91191 Gif-sur-Yvette, France
P. Mongabure
Affiliation:
CEA, DEN, DANS, DM2S, SEMT, EMSI, 91191 Gif-sur-Yvette, France
A. Miquet
Affiliation:
EDF, SEPTEN, 69628 Villeurbanne, France
P. Bouffioux
Affiliation:
EDF, Renardières, 77818 Moret-sur-Loing, France
Corresponding
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Abstract

The fuel handling operating rules exclude any accidental risk. However in the framework of the PRECCI R&D project, the bending of a spent fuel assembly resulting from its locking during a translation displacement is taken into account. This enabled us to develop an approach based on experiments and calculations that allows us to simulate the behaviour of an assembly under such loading. This study was carried out in CEA laboratories with the funding and the technical support of EDF. A three points bending test on a spent fuel rod segment was performed at the Laboratory for Mechanical Behaviour of Irradiated Materials (LCMI). From the experimental strength-displacement curve, a maximum failure strain, a maximum failure curvature and an equivalent constitutive equation were determined. CAST3M modelling of the fuel rod taking into account the elasto-plastic behaviour of the clad and the cracking of the UO2 fuel pellets was verified by the experimental results. Consequently, the identification of the respective contributions of the clad and of the pellets to the rod global behaviour was made possible. A two dimensional assembly with beam elements was modelled with CAST3M. The properties of the beams modelling the different parts of the assembly (top and bottom nozzle, grids) were chosen and adjusted according to their materials (zirconium alloys, steel) in order to obtain stiffness, tensile and shear behaviour, sliding and holding functions close to the experimental ones. Assembly bending calculations were performed. In order to obtain a rod integrity estimator, their maximum calculated strains and curvatures as a function of the bending angles can be compared to the failure experimental ones.

Type
Research Article
Copyright
© AFM, EDP Sciences 2014

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References

P. Verpeaux, A. Millard, T. Charras, Calcul des structures et intelligence artificielle (1989) 261–271
Dahlblom, O., Ottosen, N., “Smeared Crack Analysis Using Generalized Fictitious Crack Model”, J. Eng. Mech. 116 (1990) 5576 CrossRefGoogle Scholar
L. Karlsson, T. Manngard, “Modelling of PWR Fuel Assembly Deformations During Irradiation”, Transactions of the 15th International Conference on Structural Mechanics in Reactor Technology (SMiRT-15), Seoul, Korea, August 15-20 (1999)
J. Helén, A. Johansson, Nonlinear analyses of the buckling load and the eigenvalues in a 17 × 17 PWR fuel assembly, Trans. of the 12th International Conference on Structural Mechanics in Reactor Technology, Vol. C, pp. 95–100, Stuttgart, August 1993

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CAST3M modelling of a spent fuel assembly bending during a handling accident Rod failure risk evaluation from the experimental results of spent fuel rod bending test
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