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Conference proceedings: 10th Europen Review Meeting on Severe Accident Research, ERMSAR 2022
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 ...
Presentation, done during the FISA 2022 / EUREDWASTE 22 conference in the embedded SNETP forum meeting, related to the selected waste issues of Molten Salt Reactors mainly from neutronics perspective. &...
Molten Salt Reactors (MSRs) are nuclear power systems conceived to be working with a circulating salt-mixture, acting simultaneously as fuel and as coolant, providing safety and sustainability enhanceme...
This is the numerical data set belonging to the journal paper entitled: 'Numerical Modelling of Solid-Liquid Phase Change with a Conservative Linearised Enthalpy Approach and the Discontinuous...
Dataset associated to the 2022 ANS Annual meeting conference paper "Numerical methodology for design and evaluation of natural circulation systems for MSR applications".
Presentation in Cooperative Severe Accident Research Program (CSARP) video meeting. 7-11 June, 2021.
Molten salt reactors are being explored as an option for the future of nuclear energy and were selected as one of the advanced designs by the Generation IV International Forum. While research is being done i...
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...
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 analysis of innovative reactor concepts such as the Molten Salt Fast Reactor (MSFR) requires the development of new modeling and simulation tools. In the case of the MSFR, the strong intrinsic coupling b...
Within the H2020-Euratom project SAMOSAFER, research is currently ongoing into the Molten Salt Fast Reactor (MSFR) concept in which nuclear fuel is dissolved in a liquid salt. A major challenge in the MSFR i...
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. ...
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 Molten Salt Fast Reactor, currently under development in the framework of the SAMOSAFER H2020-Euratom project, foresees an in-core helium bubbling system for the removal of gaseous and metallic fission p...
Dataset associated with the PHYSOR 2022 conference paper "Development of an OpenFOAM Multiphysics Solver for Solid Fission Products Transport in the Molten Salt Fast Reactor"
The Molten Salt Fast Reactor (MSFR) is a nuclear reactor concept under development in the framework of the H2020-Euratom project SAMOSAFER. Given its peculiar characteristics as a circulating-fuel react...
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...
Nukleonika, Vol 60 (4) 907-914
This repository features a fortran program (Stevan_DG.f90) for solving the 1D Stefan problem with the linearised enthalpy approach and a discontinuous Galerkin framework, published under the GNU general publ...
This paper proposes a concept of molten salt fast reactor (MSFR) using chloride salts and U/Pu cycle as solution to close the fuel cycle. It is making use of the available materials currently unused or even ...
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 reference MSFR (Molten Salt Fast Reactor) is a 3000 MWth molten salt reactor. In most molten salt reactors, such as the MSFR, the fissile and fertile materials are dissolved in a circulating salt tha...
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...
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 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".
Dataset associated to the conference paper "A New Reactivity Control Approach for Circulating Fuel Reactors", Proceedings of the International Conference Nuclear Energy for New Europe (NENE202...
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...
Dataset associated to the Nuclear Engineering and Design paper "Multiphysics Modelling of Gaseous Fission Products in the Molten Salt Fast Reactor".
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...
Dataset associated to the conference paper "Multiphysics analysis of an in-core fission product removal system for the Molten Salt Fast Reactor", Proceedings of the International Conference Nu...
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 ...
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...
Data set and results associated with the ICAPP 2023 conference paper "Thermal Study of the Emergency Draining Tank of Molten Salt Reactor".
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...
Phase equilibria in the system ThF4-PuF3 were measured by DSC. Samples were encapsulated to prevent leak during the measurements and to protect the internal parts of the device from the...
This work focuses on the development of a comprehensive numerical methodology for the study of natural circulation systems using molten salts as working fluid, in particular for its application in the design...
This data set corresponds to the paper This data set corresponds to the paper Transient Freezing of Water in a Square Duct: An Experimental Benchmark. Please cite this paper when using this data (for instanc...
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...
Contains data plotted in the figures of the manuscript with the same title (submitted, 2021).
This research was undertaken, in part, thanks to funding from the Canada Research Chairs program and the Discovery Grant Program of the Natural Sciences and Engineering Research Council of Canada. This study...
This is the numerical data-set belonging to 'Transient Freezing of Water in a Square duct'. The simulation outputs can be opened using the opensource application GMSH.
Solid-liquid phase-change phenomena play a key role in the thermal hydraulics of Molten Salt Reactors (MSR’s). Amongst key areas of interest are the design of the freeze plug and the analysis of accide...