Bringing nuclear safety to the next level
SAMOSAFER builds on the results of the SAMOFAR project
Bringing nuclear safety to the next level
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PuF3 was synthetized by hydro-fluorination of PuO2 and subsequent reduction of the product by hydrogenation. The obtained PuF3 was analysed by X-Ray Diffraction (XRD) and found phase-pure. High ...
An overview of the ongoing efforts in the area of the thermal hydraulics modeling of a Molten Salt Fast Reactor (MSFR) is presented. The MSFR employs a owing liquid fuel based on a high tempe...
The aim of this paper is the extension of a multiphysics OpenFOAM solver for the analysis of the Molten Salt Fast Reactor (MSFR), developed in previous works (Cervi et al., 2017, 2018). In particular...
The release of fission product and salt compounds from a molten salt reactor fuel under accident conditions was investigated with coupled computer simulations. The thermodynamic modeling of the salt and fiss...
The Molten Salt Fast Reactor is a fast-spectrum molten salt reactor under development in the framework of the European H2020 SAMOFAR Project (http://samofar.eu/). Among the design peculiarities, this...
A selected composition of the initial fuel of the Molten Salt Fast Reactor (MSFR) is assessed by differential scanning calorimetry (DSC) for melting point determination and by Knudsen effusion mass s...
Basic thermodynamic and electrochemical data of pure actinide fluorides and their mixtures are required for the design and safety assessment of any presently studied molten salt reactor concept based...
The Molten Salt Fast Reactor (MSFR) with its liquid circulating fuel and its fast neutron spectrum calls for a new safety approach including technological neutral methodologies and analysis tools ada...
Compressible fluid dynamics is of great practical interest in many industrial applications, ranging from chemistry to aeronautical industry, and to nuclear field as well. At the same time, modelling ...
In order to be able to have a solid understanding of the species, phases and chemical interactions present in the materials of a molten salt reactor, the gap between the neutronic, isotope-based fuel...
The release of fission product and salt compounds from a molten salt reactor fuel under accident conditions was investigated with coupled computer simulations. The thermodynamic modeling of the salt and fiss...
Nukleonika, Vol 60 (4) 907-914