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Embrittlement of neutron-irradiated austenitic steel at high dose ductile fracture modelling based on SEM and TEM microstructural characterization.

Abstract : In the framework of GEN-IV reactor project, post-irradiation examinations of swelling-resistant austenitic steel (15Cr-15Ni-Ti) irradiated at high dose up to 120 dpa in the Phénix fast reactor have been performed in the recent years at CEA. Ring-tensile tests done at room and irradiation temperature have characterized irradiation-induced embrittlement (sharp reduction of uniform and total elongation). Detailed Scanning Electron Microscopy (SEM) examinations of fracture surface combined with Transmission Electron Microscopy (TEM) observations have pointed out several damage mechanisms of grain and grain-boundary [1]. Based on the experimental observations (SEM characterisation of nanodimples on fracture surface and TEM quantitative analysis of void population), numerical simulations of tensile tests are presented using a homogenized ductile fracture model described in [2]. The model features a physical description of growth and coalescence of voids (formed during irradiation) coupled with matrix plasticity. The prediction of model illustrates the correlation between irradiation swelling and embrittlement.
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https://hal-cea.archives-ouvertes.fr/cea-02394063
Contributor : Bibliothèque Cadarache <>
Submitted on : Wednesday, December 4, 2019 - 4:03:08 PM
Last modification on : Tuesday, April 28, 2020 - 11:28:14 AM

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  • HAL Id : cea-02394063, version 1

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CEA | DEN

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A. Courcelle, J. Hure, I. Turque, C. Bisor. Embrittlement of neutron-irradiated austenitic steel at high dose ductile fracture modelling based on SEM and TEM microstructural characterization.. SMINS5 Structural Materials for Innovative Nuclear Systems, Jul 2019, Kyoto, Japan. ⟨cea-02394063⟩

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