P. Bouffioux

A model to describe the anisotropic viscoplastic behaviour of Zircaloy-4 tubes

P. Delobelle, P. Robinet, P. Geyer et al. · Journal of Nuclear Materials · 1996 · 51 citations

Materials Science, Viscoplastic Fluid, Engineering +9

Synthesis on the spent fuel long term evolution

C. Ferry, Christophe Poinssot, Patrick Lovera et al. · 2005 · 19 citations

Fuel Cycle, Chemical Engineering, Engineering +15

Hydride reorientation and its impact on ambient temperature mechanical properties of high burn-up irradiated and unirradiated recrystallized Zircaloy-2 nuclear fuel cladding with an inner liner

Q. Auzoux, P. Bouffioux, Albert J. Machiels et al. · Journal of Nuclear Materials · 2017 · 19 citations

Materials Science, Nuclear Ceramic, High Temperature Materials +8

Thermomechanical Behavior and Modeling Between 350°C and 400°C of Zircaloy-4 Cladding Tubes From an Unirradiated State to High Fluence (0 to 85s˙1024 nm−2,E>1 MeV)

I. Scha ̈ffler, P. Geyer, P. Bouffioux et al. · Journal of Engineering Materials and Technology · 1999 · 13 citations

Engineering, Mechanical Engineering, Fusion Materials +22

REFLET Experiment in OSIRIS: Relaxation under Flux as a Method for Determining Creep Behavior of Zircaloy Assembly Components

S. Carassou, Christelle Duguay, Pascal Yvon et al. · Journal of ASTM International · 2010 · 10 citations

Engineering, Severe Plastic Deformation, Mechanical Engineering +17