NuMat2022: The Nuclear Materials Conference
24–28 October 2022 | Ghent, Belgium
The NuMat organizing committee are delighted to announce that the seventh meeting is now open for abstracts and will be held in Ghent, Belgium, from 24–28 October 2022.
Before travelling to the conference, please familiarise yourself with the Covid-19 requirements for Belgium, which Elsevier will be following. The current country guidelines can be found here. We still request that anyone who has tested positive for Covid-19, or is under any self-quarantine orders does not attend the conference. |
NuMat 2022 has special topics in mind |
Journal of Nuclear Materials to publish selected papers from NUMAT2022 - read more |
The Nuclear Materials Conference (NuMat) was created in 2012 in association with the Journal of Nuclear Materials to serve as an umbrella for international meetings on nuclear materials science related to fission and fusion reactors and the overall nuclear fuel cycle. Following on from NuMat 2020 Online, where over 500 delegates presented their work, NuMat 2022 will focus on broad topics of interest to the nuclear materials community centred around structural components and fuel systems. For the 2022 meeting a session will be dedicated to special topics such as cements and ceramics, polymers, and advanced manufacturing.
There will be plenary speakers, plus an opening plenary from the 2022 recipient of the Robert Cahn award and a presentation from the best paper prize recipient from the Journal of Nuclear Materials. There will be three parallel sessions including workshops and poster sessions which will cover the breadth of research within nuclear materials.
NuMat 2022 will cover the following topics
Track 1 Structural components
Track 1A Metallic alloys for structural components
Track 1B Refractory metallic materials
- Structural and functional materials for fission and fusion reactors
- Modelling and simulation of structural materials
- Radiation damage processes in materials and complex microstructures
- Characterization of irradiated materials
Track 2 Fuel systems
Track 2A Cladding materials including coating
Track 2B Fuel materials, absorbers and fuel cladding interaction
- Thermodynamics and thermal properties of nuclear fuels
- Modelling and simulation of nuclear fuels
- Behavior of materials during normal operation conditions
- Behavior of materials during severe accidents and accident tolerant fuels
- Radiation damage processes in materials and complex microstructures
- Characterization of irradiated fuel systems
- Materials for the nuclear fuel cycle
Track 3 Special Topics
Workshop: Cement and ceramics
- Cementation of RA waste, concrete in NPP’s, swelling behaviour of cement
Workshop: Polymers
- Polymer and polymer waste composites in nuclear application, aging mechanism during LTO, radiation resistivity, microstructural characterization
Workshop: Advanced manufacturing
- Powder metallurgy, spark plasma sintering, additive manufacturing, coating techniques
Supporting publications
Organised in cooperation with the International Atomic Energy Agency
In partnership with Materials Today
Sponsor
Family Support Awards
