FAST: Generation-IV nuclear reactors with a fast neutron spectrumWe launched the project in 2002 and our current goals are:
- to study neutronics and nucleonics, thermal hydraulics and fuel behaviour of advanced fast-spectrum nuclear reactors using modern computational tools: TRACE/PARCS/FRED, Eranos/EQL3D, Serpent 2, OpenFOAM;
- to evaluate safety of fast reactors considered for construction in Europe, in particular, ASTRID Sodium-cooled Fast Reactor;
- to analyse innovative design solutions for Generation-IV Molten Salt Reactor;
- to represent Switzerland internationally at GIF, IAEA, OECD, EURATOM;
- to educate young researchers and students, in particular, via the ETHZ/EPFL Master of Science in Nuclear Engineering and EPFL PhD programs.
November 13, 2016In November 2015 Switzerland joined the GIF MSR activities and the upcoming 23rd GIF MSR pSSC meeting will be hosted by Paul Scherrer Institute, the Swiss implementing agent. At this occasion an MSR workshop dedicated to the national projects of the GIF MSR partners will be held. It will include the country programs of China, EU, France, Russia, USA, and the motivation and foreseen project of Australia and Switzerland.
Molten Salt Reactor Workshop at PSI :: PSI Auditorium :: 24. January 2017 :: afternoon
Download the flyer.
Register for the workshop.
October 9, 2016On October 4, 2016, the proposal for the project called "European Sodium Fast Reactor Safety Measures Assessment and Research Tools (ESFR-SMART)" was submitted in response to NFRP2 "Research on safety of fast neutron Generation-IV reactors" of Euratom Work Program 2016-2017. The consortium of the proposed project includes 19 partners from 8 countries. The project is coordinated by Dr. K. Mikityuk (PSI). The first three pages of the proposal (list of participants, table of content and abstract): download.
October 7, 2016On September 16 Eirik Pettersen from Université Paris-Saclay successfully passed the MS exam. The topic of his MS study which he did at the FAST group was "Coupled multi-physics simulations of the Molten Salt Fast Reactor using coarse-mesh thermal-hydraulics and spatial neutronics". A coupled tool consisting of the 2D/3D coarse-mesh, thermal-hydraulics system code TRACE and the 3D neutron diffusion solver PARCS was used to compute dynamic behaviour of the MSFR, featuring large open volume through which the molten salt circulates. The coarse-mesh TRACE solution was compared to the CFD solution and the conclusion was made on the TRACE applicability to the MSFR analysis.
September 20, 2016On September 14, 2016 the NES colloquium "Molten Salt Reactor: sustainable and safe reactor for the future?" was given by Dr. Jiri Krepel. The colloquium offered a brief history of the Molten Salt Reactor, addressed its advantages, disadvantages and open issues, and presented the related international research and activities at PSI. Specific attention was brought to the inter-laboratory effort initiated within the Nuclear Energy and Safety Division during the past two years. The slides are available for download (4MB).
September 3, 2016On August 30 Jiadong Bao successfully passed the MS exam. The topic of his MS study was "Development of the model for the multiphysics analysis of Molten Salt Reactor Experiment using GeN-Foam code". The experiment, completed 50 years ago, was partly re-analyzed with the open source multi-physics code to improve our understanding of the liquid-fuel reactor physics and to validate the computational tools to be used in design and safety demonstration of the future MSRs.
August 4, 2016The 2016 October issue of Annals of Nuclear Energy publishes a paper "Development and verification of the neutron diffusion solver for the GeN-Foam multi-physics platform" by C. Fiorina, N. Kerkar, K. Mikityuk, P. Rubiolo and A. Pautz. We contributed to the part devoted to the European Sodium Fast Reactor calculations. http://dx.doi.org/10.1016/j.anucene.2016.05.023
July 2, 2016The August issue of Nuclear Engineering and Design publishes a paper "Analysis of effects of pellet-cladding bonding on trapping of the released fission gases in high burnup KKL BWR fuels" by V. Brankov, G. Khvostov, K. Mikityuk, A. Pautz, R. Restani, S. Abolhassani, G. Ledergerber, W. Wiesenack, to which we contributed in frame of the cooperation with the Fuel Modeling Group of our lab. http://dx.doi.org/10.1016/j.nucengdes.2016.06.021
June 26, 2016The just-published Generation IV International Forum Annual Report highlights the main achievements of the Forum in 2015. In particular, FAST contributed to the Task Force on Education and Training. https://www.gen-4.org/gif/jcms/c_82870/gif-2015-annual-report-final-e-book
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