NOMATEN HYBRID-SEMINAR, May 14th, Irradiation embrittlement investigation and modelling in structural nuclear materials

Date
Place
https://meet.goto.com/NCBJmeetings/nomaten-seminar
In-person: NOMATEN seminar room


NOMATEN HYBRID-SEMINAR

online: https://meet.goto.com/NCBJmeetings/nomaten-seminar
In-person: NOMATEN seminar room

Tuesday, May 14th  2024 13:00 CET

Irradiation embrittlement investigation and modelling in structural nuclear materials

Dr. Christian Robertson
French Alternative Energies and Atomic Energy Commission (CEA), France

 

Abstract:

Structural nuclear materials are subjected to neutron irradiation at elevated temperature, thereby affecting the operational lifetime of various critical reactor components. Dose-dependent material damage directly depends on dislocation-mediated plasticity mechanisms and their interactions with the irradiation defect microstructures, in the form of interstitial and vacancy clusters. Corresponding plastic strain spreading mechanisms have been investigated in details during the past few years, using three dimensional dislocation dynamics simulations. This particular talk focuses on how dislocation-scale data can be worked out and then applied to component-scale damage evaluation. Two applicative case study are presented herein:

  1. Inter-granular crack initiation susceptibility in internal steels
  2. Irradiation embrittlement in reactor Pressure Vessel steel

 

Bio:

Engineering Degree (B. Ing.), Université de Sherbrooke (Canada). Master in Physical Engineering (M. Sc A), École Polytechnique de Montréal (Canada). Doctorate in Materials Physics, Université de Paris-6 (Ph. D.). Dissertation subject: "Déformation plastique induite par l’essai d’indentation sub-micronique dans le cuivre et l’acier 316L". Habilitation à diriger des recherches (HdR) in Materials Physics, Institut National Polytechnique de Grenoble (INPG). Dissertation subject: "Damage accumulation and crystal plasticity mechanisms in metallic materials". Pr. C. Robertson research activities focus on the observation and corresponding physical modelling of plasticity mechanisms in structural nuclear materials, at the grain and sub-grain scale (µm). These developments aim to give support and to improve component design rules and surveillance programmes of metallic materials, in the context of nuclear power reactor operation. The main tools utilized are Transmission Electron Microscopy, Dislocation Dynamics modelling and various mechanical tests including resilience, tensile, creep and fatigue. Various applicative cases have been investigated and presented in several peer-reviewed scientific papers (2004-2024):

  1. Fatigue lifetime prediction under complex loading conditions
  2. Prediction of dose-dependent fracture toughness evolutions (ductile to brittle transition temperature and upper shelve energy) in ferritic materials
  3. Prediction of stress corrosion cracking initiation in post-irradiated austenitic stainless steels
  4. Prediction of thermal and irradiation creep (residual) lifetime in heavily damaged metallic materials

 

 

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This project has received funding from the European Union Horizon 2020 research and innovation
programme under grant agreement No 857470 and from European Regional Development Fund
via Foundation for Polish Science International Research Agenda PLUS programme grant
No MAB PLUS/2018/8.
Poland
The project is co-financed from the state budget within the framework of the undertaking of the Minister of Science and Higher Education "Support for the activities of Centers of Excellence established under Horizon 2020".

Grant: 5 143 237,70 EUR
Total value: 29 971 365,00 EUR
Date of signing the funding agreement: December 2023

The purpose of the undertaking is to support entities of the higher education and science system that have received funding from the European Union budget in the competition H2020-WIDESPREAD-2018-2020/WIDESPREAD-01-2018-2019: Teaming Phase 2. in the preparation, implementation and updating of activities, maintenance of material resources necessary for carrying out activities, acquisition and modernization of scientific and research apparatus, maintenance and development of personnel potential necessary for the implementation of activities, and dissemination of the results of scientific activities.