Symposium_V_Program 644.75 Kb
Nuclear materials are studied for under demanding temperature, pressure and irradiation environments. These materials act as barriers and their structural properties are investigated with emphasis on mechanical performances, durability, plasticity and stability. Symposium N includes sessions dealing with materials ranging from structural components of fusion systems, advanced spallation or fission units, structural parts of thermal reactors, fuels and waste forms. Macro-properties such as thermodynamic, thermophysical and mechanical as well as microstructural analysis of these materials are discussed for example comparing properties prior and after irradiation.
Hot topics to be covered by the symposium:
- Component materials for advanced fusion systems are considered in the first session. Temperature as well as the energy and flux of particles are very high. This session is connected with research activities on structural materials for other systems.
- Component materials for advanced fission reactors are considered in the third session. Temperatures as well as the energy and flux of particles are also very high. This session concerns research activities and R&D for high temperature gas reactors.
- Structural materials of thermal reactors such as cladding, assembly components, reactor internals and vessel or piping are treated in a specific session.
- Fuel materials include advanced oxides, nitrides, carbides or metals in homogeneous form or as composites such as cercer, cermet or metmet that can be used either as fuel or as target for transmutation.
- Waste form materials must be durable and have a low solubility or leaching rate in environmental conditions over geological time scales.
In all cases, irradiations with accelerators guide the investigator in choosing the optimal components prior to irradiation in the reactor. The challenge in this century will be to work with reliable or inert material that makes their use safer with respect to economic and ecological goals, making their utilisation more sustainable for nuclear systems.
Tentative list of invited speakers:
- Jiang Li, ASIPP Hefei, China: Fusion systems and transmutation
- Bruno Thomauske, RWTH, Germany: Materials in ADS gas-cooled reactors
- Lars Hallstadius, Westinghouse, Sweden: Claddings for high performance fuels
- Rosaura Ham-Su, AECL, Canada: Fuel production and analysis
- Stephane Gin, CEA Marcoule, France: Waste form challenges
List of scientific committee members:
- Harald Bolt, FZJ, Juelich, Germany
- Gary Dyck, IAEA, Vienna, Austria
- Thomas Fanghänel, ITU, CEC
- Dolores Gomez Briceño, CIEMAT, Madrid, Spain
- Wolfgang Hoffelner, PSI, Villigen, Switzerland
- Jaap van der Laan, NRG, Petten, The Netherlands
- Clément Lemaignan, CEA, Grenoble, France
- Margaret Mcgrath, NEA/HRP, Halden, Norway
- Bruno Riccardi, ENEA, Frascati, Italy
- Eric Simoni, Université Paris Sud, France
The proceedings will be published in Progress in Nuclear Energy (Elsevier Ltd).
PSI Paul Scherrer Institute
Tel: + 41 56 3104176
The University of Michigan
2534 C.C. Little Building
1100 N. University Ave.
Ann Arbor, MI 48109-1005
Tel.:+1 734 763 9295
Claude Guet (Proceedings Editor)
Tel: +33 6 82 67 81 45
Alan J. Hurd
Lujan Neutron Center LANL
Los Alamos, NM
Tel.: +1 505 667 1344
School of Materials Science and Engineering
Department of Nuclear Engineering
Tokyo Institute of Technology
2-12-1-N1-1, O-okayama, Meguro
Tel.: +81 3 5734 3060