Symposium FF
Materials Challenges for Future Nuclear Fission
and Fusion Technologies
Advisory Board
Invited Lectures


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 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 Future Nuclear Fission and Fusion Technologies” will provides an exciting melting pot to foster the 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.

Contributions are invited in the following and related areas:

FF-1 Structural Components for Nuclear Fission and Fusion Applications

  • High-temperature metallic alloys and superalloys
  • Metal-matrix composites
  • Ceramics
  • Ceramic-matrix composites

FF-2 Low Activation Structural Materials for Nuclear Fusion Systems

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

FF-3 Materials for First Wall Components of Nuclear Fusion Systems

  • Plasma facing materials
  • Blanket materials

FF-4 Functional Materials

  • Insulators
  • Superconducting magnets
  • Coatings

FF-5 Nuclear Fuel Materials

  • Processing, microstructure, and properties relationship
  • Oxide-base nuclear fuels
  • Metal-base nuclear fuels
  • Thermomechanical modelling
  • Recycle of nuclear fuels
  • Fuel cladding materials

FF-6 Radiation effects

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

FF-7 Materials Modelling and Database

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

FF-8 Crosscutting Materials Issues for Nuclear Fission and Fusion Systems

FF-9 Systems Integration and Interface Design and Components

Focussed Session FF-10 Materials Technology for Nuclear Waste Treatment and Disposal



SUBMIT AN ABSTRACT