FR - 4th International Conference
Materials Challenges for Sustainable Nuclear Fission and Fusion Technologies

Massimo ANGIOLINI, ENEA, Italy

Vladimir BARABASH, ITER Organization, France
V.M. CHERNOV, A.A. Bochvar Res.Inst. for Inorganic Materials, Russia
Xavier DESCHANELS, CEA, France
Gianfranco FEDERICI, EUROfusion, Germany
Takeshi HIRAI, ITER, Japan
Qunying HUANG, Institute of Nuclear Energy Safety Technology, CAS, China
Changheui JANG, KAIST, South Korea
Yutai KATOH, Oak Ridge National Laboratory, USA
Weon-Ju KIM, Korea Atomic Energy Research Institute (KAERI), South Korea
Hua-Tay LIN, Guangdong University of Technology, China
Christian LINSMEIER, Forschungszentrum Juelich GmbH, Germany
Bing LIU, Tsinghua University, China
Tong LIU, China Nuclear Power Technology Research Institute Co., Ltd., China
Igor MAZUL, Efremov Scientific Research Inst.of Electrophysical Apparatus, Russia
Takeo MUROGA, National Institute for Fusion Science, Japan
Yasuyoshi NAGAI, Tohoku University, Japan
Marek RUBEL, Royal Institute of Technology, Sweden
Lance SNEAD, Nuclear Reactor Laboratory, USA
Dmitry TERENTYEV, SCK.CEN, Belgium
Jason TRELEWICZ, Stony Brook University, USA
Thierry WISS, DG Joing Research Centre-JRC, Germany
Yican WU, Institute of Nuclear Energy Safety Technology, CAS, China
Michio YAMAWAKI, University of Fukui, Japan
Mohamed ABDOU, University of California, Los Angeles, USA
Giacomo AIELLO, EUROfusion Consortium, Germany
Vladimir BARABASH, ITER Organization, France
Arun BHATTACHARYA, Oak Ridge National Laboratory, USA
Luca CAPRIOTTI, Idaho National Laboratory, USA
Xiang (Frank) CHEN, Oak Ridge National Laboratory, USA
Jan W. COENEN, Forschungszentrum Jülich, Germany
Daniel DOROW-GERSPACH, Forschungszentrum Jülich, Germany
Sergei DUDAREV, United Kingdom Atomic Energy Authority, UK
Mark GILBERT, Culham Centre for Fusion Energy, UK
Alexander V. MÜLLER, Max-Planck-Institut für Plasmaphysik, Germany
Takuya NAGASAKA, National Institute for Fusion Science, Japan
Hisashi TANIGAWA, National Institutes for Quantum Science and Technology (QST), Japan
Jason TRELEWICZ, Stony Brook University, USA
Rafael VILA, CIEMAT, Spain
Steven ZINKLE, University of Tennessee, Knoxville, USA
Advanced programs are being pursued by several countries on nuclear technologies to assure a safer, reliable, environmentally sustainable, and economical energy. In this context, materials have to be available that embody refined structural, functional and radiation endurance needed to fulfil today technologies requirements and to face future demands that would come from perspective new generation fission and fusion reactors now at the design or at the DEMO stage.
This International Conference, which follows the ones on the same subject held in the frames of CIMTEC 2010, 2014 and 2018, 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.

Contributions are solicited in the following and related areas:
Session Topics

FR-1 Structural components for nuclear fission and fusion applications

  • High-temperature metallic alloys and superalloys
  • Metal-matrix composites
  • Oxide-based and non-oxide-based ceramics
  • Ceramic-matrix composites

FR-2 Low activation structural materials for nuclear fusion systems

  • Ferritic and martensitic alloys
  • Vanadium alloys
  • SiC and SiC matrix composites

FR-3 Materials for first wall components of nuclear fusion systems

  • Plasma facing materials
  • Blanket materials

FR-4 Functional materials

  • Insulators
  • Superconducting magnets
  • Coatings

FR-5 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 conditions

FR-6 Radiation effects

  • Defect production and properties
  • Microstructure evolution
  • Mechanical property changes
  • He and H effects
  • Theoretical modelling

FR-7 Materials modelling and database

  • Modelling of performance
  • System design and modelling
  • Materials and mechanical properties database

FR-8 Crosscutting materials issues, present status, challenges and directions for nuclear fission and fusion science and technology

Focused Session FR-10
Materials Issues in Radioactive Nuclear Waste Treatment and Disposal


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