IC-5 - 5th International Conference
Materials Challenges for Sustainable Nuclear Fission and Fusion Technologies
Convener:
Lance SNEAD, Massachusetts Institute of Technology, USA
Members:
Jan-Willem COENEN, Forschungzentrum Juelich, Germany
Jean-Paul CROCOMBETTE, CEA Saclay, DEN/SRMP, France
Flyura DJURABEKOVA, University of Helsinki, Finland
Sergei DUDAREV, UKAEA, UK
En-Hou HAN, Institute of Corrosion Science and Technology, China
Tatsuya HINOKI, Kyoto University, Japan
Xunxiang HU, Sichuan University, China
Yutai KATOH, Oak Ridge National Laboratory, USA
Christian LINSMEIER, Forschungszentrum Juelich GmbH, Germany
Jaime MARIAN, University of California at Los Angeles, USA
Takeo MUROGA, National Institute for Fusion Science, Japan
Shuhei NOGAMI, A.L.M.T. Corp., Japan
Marek RUBEL, KTH Royal Institute of Technology, Sweden
David SPROUSTER, Stony Brook University, USA
Jason TRELEWICZ, Stony Brook University, USA
Thierry WISS, DG Joing Research Centre-JRC, Germany
Yican WU, Institute of Nuclear Energy Safety Technology, CAS, China
Ping XIAO, University of Manchester, UK
Steven ZINKLE, University of Tennessee, USA
Lance SNEAD, Massachusetts Institute of Technology, USA
Members:
Jan-Willem COENEN, Forschungzentrum Juelich, Germany
Jean-Paul CROCOMBETTE, CEA Saclay, DEN/SRMP, France
Flyura DJURABEKOVA, University of Helsinki, Finland
Sergei DUDAREV, UKAEA, UK
En-Hou HAN, Institute of Corrosion Science and Technology, China
Tatsuya HINOKI, Kyoto University, Japan
Xunxiang HU, Sichuan University, China
Yutai KATOH, Oak Ridge National Laboratory, USA
Christian LINSMEIER, Forschungszentrum Juelich GmbH, Germany
Jaime MARIAN, University of California at Los Angeles, USA
Takeo MUROGA, National Institute for Fusion Science, Japan
Shuhei NOGAMI, A.L.M.T. Corp., Japan
Marek RUBEL, KTH Royal Institute of Technology, Sweden
David SPROUSTER, Stony Brook University, USA
Jason TRELEWICZ, Stony Brook University, USA
Thierry WISS, DG Joing Research Centre-JRC, Germany
Yican WU, Institute of Nuclear Energy Safety Technology, CAS, China
Ping XIAO, University of Manchester, UK
Steven ZINKLE, University of Tennessee, USA
The list of Invited Speakers will be available at the end of July 2025
Nuclear power, whether sourced from fusion or fission, is undergoing a resurgence in both academic and industrial interest driven primarily by the understood and pressing need to address combined global energy and environmental needs. As nuclear is now perceived as the most rational low-carbon baseload power option significant research into advanced systems, and investment in current available systems, is underway through both the private and government investment. To support this resurgence in activity the critical area of nuclear materials: structural materials, fuels, irradiation damage, etc. has also received increased attention.
This International Conference, which follows the ones on the same subject held in the frames of CIMTEC 2010, 2014, 2018 and 2022, will cover: i- processing, properties, modelling and simulation of nuclear fuels and of structural and functional materials for fission and fusion reactors; ii- radiation damage processes and characterization of irradiated materials; and iii- behaviour of materials during severe accident. Materials related aspects in component design, crosscutting materials issues and medium and long-term targets for nuclear fission and fusion systems will be relevant to the debate as well as the crucial problem of radioactive nuclear waste management that will be object of a parallel Focused Session.
This International Conference, which follows the ones on the same subject held in the frames of CIMTEC 2010, 2014, 2018 and 2022, will cover: i- processing, properties, modelling and simulation of nuclear fuels and of structural and functional materials for fission and fusion reactors; ii- radiation damage processes and characterization of irradiated materials; and iii- behaviour of materials during severe accident. Materials related aspects in component design, crosscutting materials issues and medium and long-term targets for nuclear fission and fusion systems will be relevant to the debate as well as the crucial problem of radioactive nuclear waste management that will be object of a parallel Focused Session.
Session Topics
IC-5.A Structural materials for nuclear fission and fusion applications
- Fusion Structural Alloys
- Fission Structural Alloys
- Fibrous and Particulate High Temperature Composites
- UHTC Ceramics and Composites
IC-5.B Materials for first wall components of nuclear fusion systems
- High Heat Flux Materials and Structures
- Plasma Interactive Materials
- Blanket Materials and Tritium Studies
IC-5.C Functional materials
- Insulators
- Superconducting magnets
- Coatings
IC-5.D Nuclear fuel materials
- Processing, microstructure, and properties relationship
- Oxide-based nuclear fuels
- Non-oxide-based nuclear fuels
- Metal-based nuclear fuels
- Thermomechanical modelling
- Recycle of nuclear fuels
- Advanced fuel cladding materials and coatings
- Materials behaviour in accidental condition
IC-5.E Modeling fundamental radiation effects
- Defect production fundamentals
- Microstructure evolution
- Mechanical property changes
- Helium, Hydrogen and Transmutation Science (Fusion Materials and Fuels)
IC-5.F Materials modelling and database
- Modelling of performance
- System design and modelling including high-temperature design methodology
- Materials and mechanical properties database
- Small-specimen test technology
IC-5.G Crosscutting materials issues, present status, challenges and directions for nuclear fission and fusion science and technology
Focused Session IC-5.H
Materials Issues in Radioactive Nuclear Waste Treatment and Disposal