Accident Resistance of Molten-Salt Nuclear Reactor

Ignat’ev, V. V.; Субботин, С. А.; Feinberg, O. S.

doi:10.1007/s10512-018-0425-2

Cited by 5 publications

(6 citation statements)

References 3 publications

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“…Lizin et al [1] presented an overview of the nuclear reactor concepts, in which molten salts are supposed to be used. MSRs have a number of advantages [2][3][4][5]: energy efficiency due to higher temperatures; the possibility of fuel salt composition variation during the reactor's operation, including fuel reprocessing and the introduction of transuranium elements for efficient transmutation; and the inherent safety of reactors of this type. MSRs are often considered as reactors with enhanced (natural) safety features.…”

Section: Introductionmentioning

confidence: 99%

Determination of the Oxygen Content in the LiF–NaF–KF Melt

et al. 2023

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The present paper is dedicated to the quantitative determination of oxygen-containing impurities in the LiF–NaF–KF eutectic using electrochemical (cyclic and square-wave voltammetry) and reduction melting methods. The LiF–NaF–KF melt was analyzed before and after purifying electrolysis. The amount of oxygen-containing impurities removed from the salt during purification was determined. It was found that after electrolysis, the concentration of oxygen-containing impurities decreased by 7 times. The results obtained via electrochemical techniques and reduction melting were well-correlated, which made it possible to evaluate the quality of the LiF–NaF–KF F melt. To verify the analysis conditions, mechanical mixtures of LiF–NaF–KF containing Li2O were analyzed using the reduction melting method. The oxygen concentration in the mixtures varied from 0.672 to 2.554 wt. %. Based on the analysis results, the dependence approximated by the straight line was obtained. These data may be used to draw calibration curves and to further develop the procedure of oxygen analysis of fluoride melts.

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Section: Introductionmentioning

confidence: 99%

Determination of the Oxygen Content in the LiF–NaF–KF Melt

et al. 2023

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“…The coolant should be compatible with the construction materials of the heat exchangers and should have good heat exchange and hydrodynamic functions. Such materials are supposed to demonstrate low vapor pressure in a wide range of operating temperatures from 500 to 850 • C and do not interact with the fuel in cases of leakage [3][4][5][6][7]. Special attention should be paid to the corrosion resistance of construction materials in fluoride salts [8][9][10][11].…”

Section: Introductionmentioning

confidence: 99%

Interaction between Iron Fluoride and Molten FLiBe

et al. 2022

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The equilibrium potentials of iron in a LiF-BeF2-FeF2 melt were measured using the EMF method and were dependent upon the temperature and iron fluoride concentrations. The empirical equations for the isotherms and equilibrium polytherms of the iron fluoride concentration were obtained. The cathode polarization of iron fluoride in the molten mixture of lithium and beryllium fluoride was measured using the current switch off method from the stationary state. It was found that in the studied temperature and concentration ranges of iron fluoride in the LiF-BeF2 electrolyte, the valence state of iron in the melt is mainly +2. According to the experimental values of the equilibrium potentials of the iron electrode in the LiF-BeF2-FeF2 melt, the conditional standard potentials of iron were calculated relative to the fluoride reference electrode in the molten mixture of lithium and beryllium fluoride. The conditional standard values of the Gibbs energy change were calculated at the formation of iron difluoride from the element in the form of dilute solutions, as were the thermodynamic values (enthalpy and entropy) when iron difluoride was mixed with LiF-BeF2.

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“…Reprocessing spent nuclear fuel (SNF) is a high-tech process with the purpose of minimizing the radiation hazard of this fuel, ensuring the safe disposal of unused components, and facilitating the release of useful substances (primarily uranium and plutonium). At the same time, to ensure economic efficiency and improve environmental safety, the issue of the minor actinides (MA) arises [ 1 , 2 , 3 , 4 , 5 ]. The MA, which are long-lived radioactive isotopes of americium, curium and neptunium, all transuranic chemical elements, are primary contributors to the high radioactivity of the waste remaining after SNF processing.…”

Section: Introductionmentioning

confidence: 99%

Investigation of the Quasi-Binary Phase Diagram FLiNaK-NdF3

et al. 2021

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The NdF3 solubility in molten eutectic FLiNaK, which is a conceivable medium for a molten salt reactor (MSR), was determined by the quasi-binary phase diagram FLiNaK-NdF3. The eutectic mixture FLiNaK was prepared by direct melting of components LiF, NaF and KF·HF. The acidic anhydrous salt (KF·HF) was used instead of the hygroscopic KF. The NdF3 was sintered by hydrofluorination of Nd2O3. The oxygen impurity in the prepared eutectic FLiNaK, determined by an oxygen analyzer LECO OH836, was 0.036 wt.%, whereas the NdF3 contained 0.04 wt.% of oxygen. A part of the FLiNaK-NdF3 quasi-binary phase diagram was obtained using two thermal analysis techniques: differential thermal analysis (DTA) and differential scanning calorimetry (DSC). The FLiNaK-NdF3 phase diagram in the region of 0–30 mol.% NdF3 contains one eutectic at 2 mol.% NdF3 and 450 °C and two peritectic points: 8 mol.% NdF3 at 500 °C and 22 mol.% NdF3 at 575 °C. The region of the FLiNaK-NdF3 phase diagram below the liquidus line is rather complicated due to the complex structure of the multicomponent system in its molten state, as in its solid state. The NdF3 solubility in FLiNaK is about 5 mol.% at 490 °C and 29 mol.% at 700 °C; this means that the process of the MA transmutation in the MSR can be carried out in molten FLiNaK with a content of actinides as high as 15–20 mol.% in the temperature range of 550–650 °C.

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Accident Resistance of Molten-Salt Nuclear Reactor

Cited by 5 publications

References 3 publications

Determination of the Oxygen Content in the LiF–NaF–KF Melt

Determination of the Oxygen Content in the LiF–NaF–KF Melt

Interaction between Iron Fluoride and Molten FLiBe

Investigation of the Quasi-Binary Phase Diagram FLiNaK-NdF3

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