The accuracy and precision of the present technique were suitable for applications in harsh field processes. Based on our previous methodology, herein, we established a field-applicable wireless measurement system to simultaneously monitor the liquid level and density of corrosive molten salts at high temperatures. We have developed a liquid level measurement system using the dynamic bubbler technique. 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. 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 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. 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 results were compared to simulations using pure compound vapor pressures in the evaporation simulations. 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 fuel salt considered in the simulations was LiF-ThF4-UF4 with fission products Cs and I.
#Melting point measure software
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 release of fission product and salt compounds from a molten salt reactor fuel under accident conditions was investigated with coupled computer simulations. The excess properties (mixing enthalpies, entropies and Gibbs energies) calculated in this work are consistent with the expected behaviour of decreasing enthalpy and Gibbs energy of mixing with the increasing ionic radius of the alkali cations. The agreement between these assessments and the phase equilibrium data available in the literature is generally good. In this work, the modified quasi-chemical model in the quadruplet approximation was used to develop new thermodynamic modelling assessments of the binary solutions, which are highly relevant in assessing the corrosion process in molten salt reactors. This work focused on the thermodynamic assessment of the CrF2−CrF3 system and the binary systems of chromium trifluoride CrF3 with alkali fluorides (LiF, NaF, KF) using the CALPHAD (computer coupling of phase diagrams and thermochemistry) method. Understanding the corrosion mechanisms and the effect of corrosion products on the basic properties of the salt (e.g., melting point, heat capacity) is fundamental for the safety assessment and durability of molten salt reactor technology. The activities of LiF, ThF4 and UF4 over the molten F1+3zLi1-zTh xUy (z = x + y, 1 ≤ x ≤ 0, 0 ≤ y ≤ 1) salts mixture have been computed using FTsalt-FACT salt phase diagrams database. The dynamic and kinematic viscosities, density and thermodynamic function as a function of temperature of molten fuel carrier salts F1.675Li0.775Th 0.1995U0.0255 mixture have been determined. The solidus, liquidus temperature and enthalpy of fusion values were determined for molten F1.675Li0.775Th 0. mixture to be 825 ± 3 K, 838 ± 4 K and (15.9 ± 4) kJ mol⁻¹, respectively.
The thermo-physical and thermodynamic properties of this fuel salts mixture were measured using thermal analysis, Archimedes and Rheometric techniques. Based on this pseudo-binary phase diagram and reactor criticality data, the composition of fuel carrier salts has been calculated as: F1.675Li0.775Th 0.1995U0.0255. LiF–ThF4 system has been established to be the most appropriate solvent for the fissile isotope ²³³U.
The comprehensive information on LiF-ThF4-UF4 system is necessary for the development of new design molten salt reactors.
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