K. Katsuyama, T. Nagamine, S. Matsumoto, and S. Sato, High energy X-ray CT study on the central void formations and the fuel pin deformations of FBR fuel assemblies, Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, vol.255, pp.365-372, 2007.

J. Guidez, Phénix : Le retour d'expérience, pp.73-74, 2013.

T. Cadiou and F. Acosta, The impact of the fuel pin bundle deformation on the thermalhydraulics of ASTRID sub-assembly, 12th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-12), 2018.

E. Sosnovsky, E. Baglietto, S. Keijers, K. V. Tichelen, T. C. Souza et al., CFD simulations to determine the effects of deformations on liquid metal cooled wire wrapped fuel assemblies, Proceedings of the 16th International Topical Meeting on Nuclear Reactor Thermalhydraulics (NURETH-16), 2015.

E. R. Gilbert and J. F. Bates, Dependence of irradiation creep on temperature and atom displacements in 20% cold worked type 316 stainless steel, Journal of Nuclear Materials, vol.65, pp.204-209, 1977.

M. P. Surh, J. B. Sturgeon, and W. G. Wolfer, Radiation swelling behavior and its dependence on temperature, dose rate, and dislocation structure evolution, Journal of Nuclear Materials, vol.336, issue.2, pp.217-224, 2005.

T. Uwaba, H. Ohshima, and M. Ito, Analyses of deformation and thermal-hydraulics within a wire-wrapped fuel subassembly in a liquid metal fast reactor by the coupled code system, Nuclear Engineering and Design, vol.317, pp.133-145, 2017.

E. Baglietto, J. Fricano, and E. Sosnovsky, CFD Activities in Support of Thermal-hydraulic Modeling of SFR Fuel Bundles, Proceddings of the 10th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-10), 2014.

, STAR-CCM + v12.02 Users Manual, 2017.

T. Beck, Conceptual design of ASTRID fuel sub-assemblies, Nuclear Engineering and Design, vol.315, pp.51-60, 2017.
URL : https://hal.archives-ouvertes.fr/cea-02380887

, Presentation of Cast3M, 2018.

B. Leturcq, J. B. Minne, and F. D. Paola, Nouvel élément de structure pour les calculs d'interaction dans les faisceaux d'aiguilles combustibles des RNR', 13ème Colloque National en Calcul des Structures, 2017.

B. Leturcq, J. Minne, and F. D. Paola, A new structural behavior to perform efficient nonlinear SFR fuel bundle thermomechanical analysis', presented at the Club Cast3M, 2016.

J. W. Fricano and E. Baglietto, A quantitative CFD benchmark for Sodium Fast Reactor fuel assembly modeling, Annals of Nuclear Energy, vol.64, pp.32-42, 2014.

E. Merzari, Benchmark exercise for fluid flow simulations in a liquid metal fast reactor fuel assembly, Nucl Eng Des, vol.298, pp.218-228, 2016.

T. Cadiou and A. Saxena, Thermal-hydraulic numerical simulation of fuel sub-assembly using a dedicated meshing tool, Nuclear Engineering and Design, vol.295, pp.162-172, 2015.

U. Bieder, V. Barthel, F. Ducros, P. Quéméré, and S. Vandroux, CFD calculations of wire wrapped fuel bundles: modeling and validation strategies, Workshop Proceedings of Computational Fluid Dynamics for Nuclear Reactor Safety Applications (CFD4NRS-3), 2010.

P. Petiot and J. Seiler, Physical properties of sodium : a contribution to the estimation of critical coordinates, High Temperatures -High Pressures, vol.16, issue.3, pp.289-293, 1984.

J. Seran, Behavior under Neutron Irradiation of the 15-15Ti and EM10 Steels Used as Standard Materials of the Phénix Fuel Subassembly, Proceedings of the 15th International Conference on Effects of Radiation on Materials, ASTM-STP, 1125, 1992.