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Jérôme Crepin

Research Director

Center · CMAT

Discipline(s)
Solid Mechanics
Topic(s)
Nuclear, Superalloy

Team

MEM - Mécanique Expérimentale et Matériaux

Biography

Jérôme Crépin is a researcher specializing in the fields of materials mechanics, stress corrosion, and microstructural behavior under extreme stresses. His work focuses primarily on the study of metal alloys, particularly zirconium alloys, austenitic stainless steels, and nickel-based alloys, which are used in demanding industrial environments such as nuclear reactors. His research addresses issues related to plastic deformation, stress corrosion cracking (SCC), and the impact of irradiation and hydrogen defects on the mechanical properties of materials. Jérôme Crépin has contributed to the development of innovative experimental methods, such as the use of digital image correlation (DIC) to analyze local strain fields, and the application of in situ techniques to characterize deformation mechanisms at the microstructural scale. His studies have led to a better understanding of the relationships between microstructure, loading conditions, and fracture strength, particularly in contexts involving multiaxial loading or ductile-to-brittle transitions.

Publication(s)

Teaching

Materials for New Challenges (Research Quarter)

Lecturer

PhD supervision

  • 2026 The effect of mechanical loading and strain path on the stress corrosion cracking of an austenitic stainless steel in the primary environment of PWRs GRAND Johanne
  • 2024 The effect of mechanical loading and strain path on the stress corrosion cracking of an austenitic stainless steel in PWR primary environment WANG Alain
  • 2023 Stress Corrosion Cracking of Cold-Worked Stainless Steel: Influence of Oxygen in Primary Circuit of PWRs FAYOLLE Charles
  • 2020 Oxidation and stress corrosion cracking of cold-worked stainless steel in the primary circuit of PWRs: effect of oxygen transients DE PAULA Thalita
  • 2016 Non-isothermal behavior and failure of fuel cladding in zirconium alloys. Application to the Reactivity Insertion Accident (RIA) scenario. CHAIEB Ahmed
  • 2016 Oxygen transients effect on oxidation and stress corrosion cracking of cold-worked 316L stainless steel in primary water of pressurized water reactors. MAISONNEUVE Marc
  • 2016 Experimental and numerical analysis of stress corrosion cracking initiation in pre-strained stainless steels HUANG Qi
  • 2016 Intergranular corrosion of austenitic stainless steels in oxidizing nitric acid environments EMERY Adrien
  • 2016 The behavior of zirconium alloy claddings under thermo-mechanical conditions representative of a RIA accident ZOUARI Ahmed
  • 2015 Study of fatigue behavior and associated mechanisms in a very high-strength steel for aeronautical applications ABDESSELAM Hayat
  • 2015 Microstructure-property relationships at high temperature in aluminum alloys for aeronautical applications BRIEZ Louise
  • 2015 Study of hydrogen trapping in austenitic stainless steel in the context of irradiation-assisted stress corrosion cracking BACH Anne-Cécile
  • 2015 Effects of oxygen and hydrogen on the microstructure and mechanical behavior of zirconium alloys after high-temperature excursion LE HONG Thai