FAST: Generation-IV nuclear reactors with a fast neutron spectrumWe launched the project in 2002 and our current goals are:
- to study neutronics, 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 SFR);
- to analyse innovative design solutions for Generation-IV Molten Salt Reactor;
- to represent Switzerland internationally (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).
October 7, 2015The December issue of Nuclear Engineering and Design publishes a paper "GeN-Foam: a novel OpenFOAM(R) based multi-physics solver for 2D/3D transient analysis of nuclear reactors" by C. Fiorina, I. Clifford, M. Aufiero, K. Mikityuk, which summarizes our 2-year efforts on launching a new open-source computational engine for nuclear reactor analysis. http://dx.doi.org/10.1016/j.nucengdes.2015.05.035
October 6, 2015SAMOFAR – Safety Assessment of the Molten Salt Fast Reactor – is a 5M€ 4-year project of the European Union research program Horizon 2020. The project consortium consists of 11 partners (CNRS, JRC, CIRTEN, IRSN, CINVESTAV, AREVA, CEA, EDF, PSI, KIT and TU Delft). The grand objective of SAMOFAR is to prove the innovative safety concepts of the Molten Salt Fast Reactor (MSFR) by advanced experimental and numerical techniques, to deliver a breakthrough in nuclear safety and optimal waste management, and to create a consortium of stakeholders to demonstrate the MSFR beyond SAMOFAR. At the end of August 2015 the kick-off meeting of the SAMOFAR project took place at Delft University of Technology with over 35 enthusiastic participants.
September 4, 2015On 27 August 2015, Switzerland signed the Framework Agreement for International Collaboration on Research and Development of Generation IV Nuclear Energy Systems, which was extended in February 2015 for ten years, paving the way for continued collaboration among participating countries in this important area of Gen IV R&D. A signing ceremony was held at the OECD in the presence of Mr Mauro Dell'Ambrogio, Swiss State Secretary for Education, Research and Innovation, and Mr William D. Magwood, IV, NEA Director General. http://www.oecd-nea.org/general/mnb/2015/august-september.html
September 2, 2015The November issue of Annals of Nuclear Energy publishes a paper "On the use of the SPH method in nodal diffusion analyses of SFR cores" by E. Nikitin, E. Fridman, and K. Mikityuk, to which we contributed with PARCS calculations. http://dx.doi.org/10.1016/j.anucene.2015.06.007
August 26, 2015Hyemin Kim successfully passed the MS exam. The topic of her MS study was "Static and transient analysis of Molten Salt Reactor Experiment using SERPENT-2/TRACE/PARCS codes". The experiment, completed 50 years ago, was partly re-analyzed with the modern codes 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 26, 2015Jongsoo Choe successfully passed the MS exam. The topic of his MS study was "Empirical Decay Heat Correlations and Fission Products Behavior in MSRs". Molten Salt Reactors were simulated using Serpent and EQL0D to correlate decay heat power not only with reactor operation time and time after reactor shut-down, but also with efficiency of the on-line fission gas removal system. The results were compared with MSBR simulations from ORNL reports.
August 26, 2015Benoit Soubelet successfully passed the MS exam. The topic of his MS study was "Time efficient fluid dynamics analysis of sodium fast reactor wire wrapped rod bundles". OpenFOAM, an open-source 3D CFD code, was applied for modeling of single and two-phase (air-water) flow in a hexagonal wire-wrapped bundle. The obtained results were benchmarked with respect to TRACE, a state-of-the-art 1D thermal-hydraulics code.
August 20, 2015The November issue of Progress in Nuclear Energy publishes the first part of the paper on "The effectiveness of full actinide recycle as a nuclear waste management strategy when implemented over a limited timeframe -- Part I: Uranium fuel cycle" by B. A. Lindley (University of Cambridge), C. Fiorina (PSI), R. Gregg (NNL), F. Franceschini (Westinghouse), G. T. Parks (University of Cambridge), to which we contributed with the SFR analysis. http://dx.doi.org/10.1016/j.pnucene.2015.07.020
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