Bringing nuclear safety to the next level
SAMOSAFER builds on the results of the SAMOFAR project
Bringing nuclear safety to the next level
Are you interested in our research results?
Open Zenodo and you will be redirected to the SAMOSAFER community.
Dataset associated to the NURETH-19 conference paper "Modelling and Simulation of the Gaseous Fission Product Removal in the Molten Salt Fast Reactor".
Dataset associated to the NURETH-19 conference paper "Modelling and Simulation of the Gaseous Fission Product Removal in the Molten Salt Fast Reactor".
Presentation in Cooperative Severe Accident Research Program (CSARP) video meeting. 7-11 June, 2021.
Nuclear reactor modeling has been shifting, over the last decades, towards full-core multiphysics analysis due to the ever-increasing safety requirements and complexity of the designs of innovative systems. ...
Conference proceedings: 10th Europen Review Meeting on Severe Accident Research, ERMSAR 2022
Contains data plotted in the figures of the manuscript with the same title (submitted, 2021).
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...
Dataset associated to the journal paper "An Eulerian Single-Phase Transport Model for Solid Fission Products in the Molten Salt Fast Reactor: Development of an Analytical Solution for Verification Purpo...
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 ...
Nukleonika, Vol 60 (4) 907-914
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...
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 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...
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...
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 ...
This repository features a fortran program (Stevan_fvm.f90) solving the 1D Stefan problem with the linearised enthalpy approach and a finite volume framework, published under the GNU general public lice...
The release of fission products and fuel materials from a molten salt fast reactor fuel in hypothetical accident conditions was investigated. The molten salt fast reactor in this investigation features a fas...
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...
Dataset associated to the Annals of Nuclear Energy paper "Multiphysics Modelling of Gaseous Fission Products in the Molten Salt Fast Reactor".
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...