Sixth International Workshop on Structural Materials for Innovative Nuclear Systems (SMINS-6)

Co-organized by the OECD Nuclear Energy Agency (NEA) and Idaho National Laboratory
When: Monday 12-09-2022 00:00 – Thursday 15-09-2022 00:00
Where: Idaho Falls (ID, US)

The workshop will cover fundamental studies, modelling and experiments on innovative structural materials including cladding materials for advanced nuclear systems such as thermal/fast systems, sub-critical systems, as well as fusion systems.

Five main topics are suggested and a panel discussion will be organised:

  1. Fundamental studies
  2. Metal alloys
  3. Ceramic and ceramic composites
  4. Advanced/novel materials
  5. Evolution of material properties
  6. Panel discussion on complex concentrated alloys for nuclear applications

Fundamental studies: identification of mechanisms driving the response of materials under the conditions expected in innovative nuclear systems. These mechanisms may be described at the atomic or at higher scale. Multiscale approaches, together with related problems of scale bridging are of special interest along with advanced simulation techniques and data driven modelling/learning. Ion and neutron irradiation experiments, and subsequent characterization of materials microstructure are included. 

Metal alloys and ceramic and ceramic composites: in- and out-of-core applications with the scope of data availability and gaps; experimental and modelling needs for specific components; link between R&D, standardisation and experimental protocols; mechanical properties. Discussions on code development and implementation plans are also of interest.

Advanced/novel materials: complex concentrated alloys, functionally gradient materials, nano-grained materials, grain boundary engineered materials, nano-precipitation-strengthened materials and micro-laminates. Design, processing and joining will focus on novel and advanced methods (including numerical approaches) for the production and optimisation of materials and components: for instance, high-performance coating, additive manufacturing, laser sintering, and innovative joining techniques for similar and dissimilar materials.

Evolution of material properties: experimental and modelling studies of degradation modes; time-dependent properties, mechanical properties, thermal properties, radiation tolerance, environmental resistance.

Please note that fuel-cladding interactions and zirconium alloys for fuel cladding will not be covered in this edition of the workshop.  Other novel materials for accident tolerant fuel cladding in LWR systems are within the scope of the meeting.