Warm PreStress effect on highly irradiated reactor pressure vessel steel

J. Hure (1) , C. Vaille (1) , P. Wident (2) , D. Moinereau (3) , C. Landron (3) , S. Chapuliot (4) , C. Benhamou (4) , B. Tanguy (1)

1 SEMI - Service d'Etudes des Matériaux Irradiés
2 SRMA - Service des Recherches Métallurgiques Appliquées
3 EDF R&D - EDF R&D
4 AREVA NP - Centre Technique (FRANCE)

Domaines: Physique Nucléaire Théorique [nucl-th]; Physique Nucléaire Expérimentale [nucl-ex]

J. Hure, C. Vaille, P. Wident, D. Moinereau, C. Landron, et al.. Warm PreStress effect on highly irradiated reactor pressure vessel steel. Journal of Nuclear Materials, 2015, 464, pp.281-293. ⟨10.1016/j.jnucmat.2015.04.046⟩. ⟨cea-03188719⟩