Symposium FK
Materials Challenges for Sustainable Nuclear Fission and Fusion Technologies

Hua-Tay LIN, Guangdong University of Technology, China
Vladimir BARABASH, ITER Organization, France
Alfredo CARO, Los Alamos National Laboratory, USA
V.M. CHERNOV, A.A. Bochvar Res.Inst.for Inorganic Materials, Russia
Xavier DESCHANELS, CEA, France
Koji FUKUYA, Institute of Nuclear Safety System, Japan
Alexander GOTTBERG, University of Victoria, Canada
Eric R. HODGSON, Euratom/CIEMAT Fusion Association, Spain
Wolfgang JACOB, Max Planck Institute for Plasma Physics, Germany
Yutai KATOH, Oak Ridge National Laboratory, USA
Weon-Ju KIM, Korea Atomic Energy Research Institute (KAERI), South Korea
Akihiko KIMURA, Kyoto University, Japan
Akira KOHYAMA, Muroran Institute of Technology, Japan
Guang-Hong LU, Beihang University, China
Takeo MUROGA, National Institute for Fusion Science, Japan
Robert ODETTE, University of California, Santa Barbara, USA
Noriyasu OHNO, Nagoya University, Japan
Ji Yeon PARK, KAERI, Korea
Baldev RAJ, PSG Institutions, India
Joachim ROTH, Max-Planck-Inst.für Plasmaphysik, Germany
Marek RUBEL, Royal Institute of Technology, Sweden
Leo SANNEN, SCK / CEN, Belgium
Tatsuo SHIKAMA, Tohoku University, Japan
Marius WIRTZ, Forschungszentrum Jülich, Germany
Thierry WISS, DG Joint Research Center-JRC, Germany
Yican WU, Institute of Nuclear Energy Safety Technology, CAS, China
Chen XU, Chinese Academy of Engineering Physics, China
Michio YAMAWAKI, University of Fukui, Japan
Steffen ANTUSCH, Karlsruhe Institute of Technology, Germany
Sebastijan BREZINSEK, Forschungszentrum Juelich, Germany
Thak Sang BYUN, Pacific Northwest National Laboratory, USA
Viacheslav M. CHERNOV, A.A. Bochvar Res.Inst. for Inorganic Materials, Russia
Engang FU, Peking University, China
Ermile GAGANIDZE, IAM-WBM, Germany
Charles H. HENAGER Jr., Pacific Northwest National Laboratory, USA
Jan HOFFMANN, KIT, Germany
Hefei HUANG, Shanghai Institute of Applied Physics, CAS, China
Yutai KATOH, Oak Ridge National Laboratory, USA
Kenji KONASHI, Tohoku University, Japan
Sosuke KONDO, Kyoto University, Japan
Bernd KUHN, Forschungszentrum Juelich, Germany
Christian LINSMEIER, Forschungszentrum Juelich, Germany
Jaime MARIAN, University of California, Los Angeles, USA
Yoshitaka MATSUKAWA, Tohoku University, Japan
Alexander V. MUELLER, Max-Planck-Institut für Plasmaphysik, Germany
Rudolf NEU, Max-Planck-Institut fuer Plasmaphysik, Germany
Martin OBERKOFLER, Max-Planck-Institut fuer Plasmaphysik, Germany
Iacopo ROVELLI, Imperial College London, UK
Marek RUBEL, Royal Institute of Technology, Sweden
Andrea SAND, University of Helsinki, Finland
Masashi SHIMADA, Idaho National Laboratory, USA
Alexander SPITSYN, NRC Kurchatov Institute, Russia
Gary WAS, University of Michigan, USA
William J. WEBER, University of Tennessee at Knoxville, USA
Kazuhiro YASUDA, Kyushu University, Japan
Jeong-ha YOU, Max-Planck-Institut für Plasmaphysik, Germany
Jijun ZHAO, Dalian University of Technology, China
Nuclear energy, both fission and fusion, will provide a clean, safe, and cost-effective sustainable energy resource, and is expected to grow significantly in order to meet future energy demand globally. This growth should proceed without adverse impacts to global environmental and climate change. To meet this grand challenge several nuclear initiatives were proposed aiming to develop advanced nuclear energy technologies and systems that would meet future needs for safe, sustainable, environmentally responsible, and economical energy. Materials technologies will play a key enabling role to improve economics and long-term reliability of any new advanced nuclear systems. The superior structural material performance will allow higher temperature design and operation for higher thermal efficiency, longer lifetimes, and improved reliability with reduced down time. In addition to the high temperature mechanical properties, resistance to radiation damage is also a key obstacle to improve materials performance and reliability.
The International Symposium on “Materials Challenges for Sustainable Nuclear Fission and Fusion Technologies” will provides an exciting melting pot to foster international collaboration and crosscutting coordination to advance the science and technology of future nuclear fission and fusion energy. The symposium will focus up-to-date advances in materials research and development, nuclear components and systems design, irradiation effect and damage, and theoretical modelling for both advanced nuclear fission and fusion technologies and applications. Advanced materials such as high-temperatures metals, superalloys, ceramics, metal- and ceramic-matrix composites, and functional materials and coatings will be of interest. Basic scientific understanding of radiation effect and damage to the materials microstructure and properties via theoretical modelling and experiments relevant to fission and fusion application environment will also be covered.
Session Topics

FK-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

FK-2 Low activation structural materials for nuclear fusion systems

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

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

  • Plasma facing materials
  • Blanket materials

FK-4 Functional materials

  •  - Insulators
  •  - Superconducting magnets
  •  - Coatings

FK-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

FK-6 Radiation effects

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

FK-7 Materials modelling and database

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

FK-8 Crosscutting materials issues for nuclear fission and fusion systems

FK-9 Systems integration and interface design and components

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


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