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20 results for “Molten salts”
Evaporation of materials from the molten salt reactor fuel under elevated temperatures - Dataset
<p>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 fission product mixture was performed in The Gibbs Energy Minimization Software GEMS and the obtained compound vapor pressures were exchanged with the severe accident code MELCOR, where the evaporation from a salt surface located at the bottom of a confinement building was simulated. The fuel salt considered in the simulations was LiF-ThF<sub>4</sub>-UF<sub>4</sub> with fission products Cs and I. The composition of the fuel salt material was obtained from an equilibrium fuel cycle simulation of the salt using the EQL0D routine coupled to the Serpent 2 code. The results were compared to simulations using pure compound vapor pressures in the evaporation simulations. It was observed that by modeling the salt mixing the release of fission products and salt materials was reduced when compared to the pure compound simulations. The mixing effects in the salt, when compared to the pure compound simulation also affected evaporation temperatures and therefore the timing of the release of compounds. In an additional simulation in which the depressurization of the confinement was considered, the total evaporated mass of compounds increased due to increased mass transfer at the salt surface. The simulation process described in this paper can be used for a more comprehensive accident analysis of molten salt reactors once the detailed description of the reactor confinement and accident sequences are available and more fission product elements have been added to the analysis.</p>
Nuclear Data Uncertainty Propagation for the Molten Salt Fast Reactor Design (dataset)
<p>This repository contains the dataset, post-processing script and models needed to reproduce the results presented in the article "Nuclear Data Uncertainty Propagation for the Molten Salt Fast Reactor Design", published in the special issue of Nuclear Science and Engineering dedicated to the 1st Young Molten Salt Reactor Conference (held in Lecco in June 6th and 9th 2022).</p> <p>The dataset includes:</p> <ul> <li>the perturbed nuclear data files (in ACE and ENDF-6 formats) generated with the open-source, python package <a href="https://github.com/luca-fiorito-11/sandy">SANDY</a> and processed with the processing code <a href="https://github.com/njoy">NJOY</a> by using the <a href="https://github.com/nicoloabrate/ndl">NDL</a> code.</li> <li>the <a href="https://serpent.vtt.fi/serpent/">Serpent 2</a> Monte Carlo calculations for two models of the Molten Salt Fast Reactor design, conceived during the <a href="http://samofar.eu/">SAMOFAR</a> EU project</li> </ul> <p>The python scripts include pre- and post-processing tools used to generate the perturbed data and to analyse the Serpent 2 output.</p>
Dataset for: Using the quasi-chemical model beyond the quadruplet approximation: Density and Viscosity Models for Molten Salt Fuel Systems
<p>Contains data plotted in the figures of the manuscript with the same title (submitted, 2021). </p>
Development of an OpenFOAM Multiphysics Solver for Solid Fission Products Transport in the Molten Salt Fast Reactor - Dataset
<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"</p>
Thermal Study of the Emergency Draining Tank of Molten Salt Reactor"
<p>Data set and results associated with the ICAPP 2023 conference paper "Thermal Study of the Emergency Draining Tank of Molten Salt Reactor".</p>
Design and optimization of a Chloride Molten Salt Fast Reactor - dataset
<p>Dataset used for the figures presented in the paper "Design and optimization of a Chloride Molten Salt Fast Reactor" for the ICAPP2023 conference</p>
Multiphysics analysis of an in-core fission product removal system for the Molten Salt Fast Reactor - Dataset
<p>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 Nuclear Energy for New Europe (NENE2022), Portoroz, Slovenia, September 12–15, 2022.</p>
Molten Salt Templated Synthesis of Covalent Isocyanurate Frameworks with Tunable Morphology and High CO2 Uptake Capacity
<p>The use of reactive molten salts, i.e., ZnCl2, as a soft template and a catalyst has been actively investigated in the preparation of covalent triazine frameworks (CTFs). Although the soft templating effect of the salt melt is more prominent at low<br> temperatures, close to the melting point of ZnCl2, leading to the formation of abundant micropores, a significant mesopore<br> formation is observed that is due to the partial carbonization and other side reactions at higher temperatures (>400 °C).<br> Evidently, high-temperature synthesis of CTFs in various eutectic salt mixtures of ZnCl2 with alkali metal chloride salts also leads to mesopore formation. We reasoned that using the isocyanate moieties instead of cyano groups in the monomer, 1,4-phenylene isocyanate, could enable efficient interactions between carbonyl moieties and alkali metal ions to realize efficient salt templating to form covalent isocyanurate frameworks (CICFs). In this direction, the trimerization of 1,4-phenylene diisocyanate was carried out under ionothermal conditions at different reaction temperatures using ZnCl2 (CICF) and the eutectic salt mixture of KCl/NaCl/ZnCl2 (CICF-KCl/NaCl) as the reactive solvents. We observed notable differences in the morphologies of the two polymers, whereas CICF showed irregular-shaped micrometer-sized particles, the CICF-KCl/NaCl exhibited a filmlike morphology. Moreover, favorable ion-dipole interactions between alkali metal cations and oxygen atoms of the monomer facilitated two-dimensional growth and the formation of a purely microporous framework in the case of CICF-KCl/NaCl along with a near theoretical retention of the nitrogen content at 500 °C. The CICF-KCl/NaCl showed a BET surface area of 590 m2 g−1 along with a CO2 uptake capacity of 5.9 mmol g−1 at 273 K and 1.1 bar because of its high microporosity and nitrogen content. On the contrary, in the absence of alkali metal ions, CICF showed high mesopore content and a moderate CO2 uptake capacity. This study underscores the importance of the strength of the interactions between the salts and the monomer in the ionothermal synthesis to control the morphology,<br> porosity, and gas uptake properties of the porous organic polymers</p>
Dataset for CFD4NRS-9 conference paper "Simulation of noble metal particle growth and removal in the molten salt fast reactor"
<p>Dataset used for the results presented in the CFD4NRS-9 conference paper "Simulation of noble metal particle growth and removal in the molten salt fast reactor". Also the code used to generate results is included (it is also publicly available at https://github.com/edofrederix/flotationFoam), and contains a README with instructions. The plots can be generated with their respective Python files.</p>
Data Sets For: Heterogeneous Structure, Mechanisms of Counterion Exchange, and the Spacer Salt Effect in Complex Molten Salt Mixtures Including LaCl3
<p>Data Sets For: Heterogeneous Structure, Mechanisms of Counterion Exchange, and the Spacer Salt Effect in Complex Molten Salt Mixtures Including LaCl3</p>
Decoding the Pair Distribution Function of Uranium in Molten Fluoride Salts from X-ray Absorption Spectroscopy Data by Machine Learning
<p>The repo contains all codes and data related to the JPCC publication entitled "Decoding the Pair Distribution Function of Uranium in Molten Fluoride Salts from X-ray Absorption Spectroscopy Data by Machine Learning"</p>
data for "Molten Salt-Assisted synthesis of Titanium Nitride"
<p>data supporting the main text figures:</p> <p>Figure 1. A) XRD patterns of solid state metatheses at 1000, 600, or at 600 °C with the addition of two equivalents Mg. B) XRD patterns of synthesesin different molten salts (1.25 mmol of TiO2 in 544 mg of salt, yielding a titanium molality of 2.3 mol kg –1 ) with additional Mg. References of TiN (ICSD26947), TiO 2 (ICSD 9161), and silicon are indicated in blue, red, and green, respectively. The diffraction patterns were normalized to the internal siliconreference.</p> <p>Figure 2. XRD patterns for 12 or 3 h reactions of TiO 2 with A) Mg3 N2 or B) Ca 3 N2 at various temperatures in ZnCl 2 –LiCl molten salt (3 equivalentssalt). Two equivalents of magnesium were added in each case, except for the solid-state metathesis reactions at 1000 °C. References of TiN, TiO 2 , andsilicon are indicated in blue, red, and green, respectively. The diffraction patterns were normalized to an internal silicon reference for the reactions withCa 3 N2 </p> <p>Figure 3. A) UV–vis absorption spectra of the TiN particles dispersed in various solvents. Inset: the top of the LSPR band in function of the refractiveindex of each solvent and B) TEM image for TiN synthesized at 350 °C through a standard 12 h molten salts-assisted reaction.</p>
PROGRESS IN COUPLING COMPUTATIONAL THERMODYNAMICS AND COMPUTATIONAL FLUID DYNAMICS TO SUPPORT MOLTEN SALT REACTOR APPLICATIONS (Revised)
<p>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 is in direct support of the SAMOSAFER project.</p> <p> </p>
Deciphering the structural dynamics in molten salt-promoted MgO-based CO2 sorbents and their role in the CO2 uptake. Open data access
<p><strong>Open data for publication "Deciphering the structural dynamics in molten salt-promoted MgO-based CO<sub>2</sub> sorbents and their role in the CO<sub>2</sub> uptake" </strong></p>
Data Sets for: Are High-Temperature Molten Salts Reactive With Excess Electrons? The Case of ZnCl2
<p>Data Sets for: Are High-Temperature Molten Salts Reactive With Excess Electrons? The Case of ZnCl2 <a href="https://doi.org/10.1021/acs.jpcb.3c04210">https://doi.org/10.1021/acs.jpcb.3c04210 </a></p><p> </p>
Data from: Facile synthesis of porous Mo2C/C composites by using luffa sponge-derived carbon template in molten salt media
Herein, we report the synthesis of a new type of porous Mo2C/C composite by using luffa sponge-derived carbon template, and ammonium molybdate ((NH4)6Mo7O24•4H2O) in the molten NaCl-KCl salts media. The product exhibits a higher specific surface area and three-dimensional porous structure, including macrochannels, micropores, and mesopores. The desirable porous structure is resulted from the carbon template structure and formed Mo2C coating.
Transcription of Physical Properties Data Compilations Relevant to Energy Storage: I. Molten Salts: Eutectic Data
<p>Transcription of Physical Properties Data Compilations Relevant to Energy Storage: I. Molten Salts: Eutectic Data. This is a large dataset of eutectic mixtures originally compiled and published in 1978. There was not previously a machine-readable version of this dataset. We have transcribed the 2-component mixtures into csv format. We have also included 6 basic features that are widely available on Pubchem for the individual components in the mixtures, and a list of components that were not available via Pubchem.</p>
Multiphysics Modelling of Gaseous Fission Products in the Molten Salt Fast Reactor - Dataset
<p>Dataset associated to the Nuclear Engineering and Design paper "Multiphysics Modelling of Gaseous Fission Products in the Molten Salt Fast Reactor".</p>
Data from: Facile synthesis of porous Mo2C/C composites by using luffa sponge-derived carbon template in molten salt media
Open the record for dataset details and reuse information.
Data related to the article "Molecular dynamics simulations for the prediction of thermophysical properties of plutonium-based molten salts"
<p>Contains input files and data used to generate the figures of the article:</p> <p>Molecular dynamics simulations for the prediction of thermophysical properties of plutonium-based molten salts<br>(Giovanni Pireddu*, Mirella Simoes Santos*, David Lambertin, Timothée Kooyman)<br><br>*:Equal contribution</p> <p>Journal of Nuclear Materials<br>DOI: https://doi.org/10.1016/j.jnucmat.2024.155124</p> <p>The folder EXAMPLE_INPUT_FILES contains typical MetalWalls(https://doi.org/10.21105/joss.02373) (repository(https://gitlab.com/ampere2/metalwalls)) input files used to perform the molecular simulations.</p> <p>The folder DATA_FIGURES contains the processed data used to plot the figures of the paper (see below).</p> <p><br>Figure 2:<br>- 'Fig2_Density.dat' : density as a function of temperature (binary system, calculated from MD simulations)</p> <p>Figure 3:<br>- 'Fig3_HCap.dat' : heat capacity as a function of temperature (binary system, calculated from MD simulations)</p> <p>Figure 4:<br>- 'Fig4_Density.dat' : density as a function of temperature (ternary system, calculated from MD simulations)</p>
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