LiF–NaF–KF Eutectic Based Fast Molten-Salt Reactor as Np, Am, Cm Transmuter

Ponomarev, L. I.; Belonogov, M. N.; Волков, И. А.; Симоненко, В. А.; Sheremet’eva, U. F.

doi:10.1007/s10512-019-00528-y

Cited by 8 publications

(4 citation statements)

References 7 publications

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“…Properties of molten fluoride salts enable their usage in molten salt reactors (MSRs) as solvents [1][2][3]. However, the successful usage of molten alkali fluorides [4][5][6][7] requires the development of functional materials having high corrosion resistance in the melt of composition characteristics for molten salts reactors. To date, this essential problem has not been solved [8][9][10].…”

Section: Introductionmentioning

confidence: 99%

Corrosion Behavior of Candidate Functional Materials for Molten Salts Reactors in LiF–NaF–KF Containing Actinide Fluoride Imitators

et al. 2022

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Molten fluorides of alkali metals are considered a technological medium for molten salt reactors (MSRs). However, these media are known to be extremely corrosive. The successful implementation of high-temperature technological devices using molten alkali metal fluorides requires the selection of such structural materials that have high corrosion resistance in melts with compositional characteristic of MSRs. In this research, the corrosion behavior of 12Cr18Ni10Ti steel, the alloy Ni60Cr20Mo15, and the alloy Monel 404 (Ni50Cu50) was investigated in the LiF–NaF–KF eutectic melt, containing additions of CeF3 and NdF3 from 0 to 5 wt.% as imitator fluorides of actinides in an inert argon atmosphere at 550 °C for 100 h. Gravimetry, energy-dispersive X-ray (EDX) microanalysis of surfaces and cross-section of samples, and ICP-MS were used to establish the corrosion behavior of the investigated alloys. Corrosion resistance of the studied materials was found to decrease in a row from Monel 404 > Hastelloy C2000 > 12Cr18Ni10Ti. The addition of cerium fluoride into the melt resulted in the additional etching of the alloy surface. The addition of neodymium fluoride resulted in the formation of the point/inter-crystalline corrosion damages in the sample bulk. The samples of steel 12Cr18Ni10Ti were subjected to local cracking corrosion. The austenitic nickel-based alloys suffered specific local corrosion with formation of subsurface voids. Excellent corrosion resistance of the Monel alloy under the test conditions was found.

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Section: Introductionmentioning

confidence: 99%

Corrosion Behavior of Candidate Functional Materials for Molten Salts Reactors in LiF–NaF–KF Containing Actinide Fluoride Imitators

et al. 2022

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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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“…Another area of using molten salts is associated with the development of molten salt reactors for burning long-lived americium, curium, and neptunium. The most elaborated approaches for this purpose are based on the use of LiF-NaF-KF [4,5] and LiF-BeF 2 [6][7][8] eutectics with melting temperatures of about 450°С.…”

Section: Introductionmentioning

confidence: 99%

“…The eutectic LiF-NaF-KF mixture is considered as one of the possible components of the fuel salt for molten salt reactors [4,5]; it can also be a convenient model for the LiF-ThF 4 eutectic as a molten salt blanket of a fusion-fi ssion thermonuclear reactor [1,2]. In the latter case, the LiF-NaF-KF eutectic is a convenient object to study the sorption of thorium fl uoride and its eff ect on other elements.…”

Section: Introductionmentioning

confidence: 99%

Sorption of NdF3 and ThF4 from the LiF–NaF–KF Melt

et al. 2021

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The sorption of neodymium and thorium fluorides by AG-3 activated carbon from molten alkali metal fluorides LiF–NaF–KF has been studied. The sorption isotherm of neodymium fluoride at 650°C has a pronounced convex and is adequately described by the Langmuir equation. The sorption of thorium fluoride under the same conditions is much weaker than that of neodymium fluoride, which is determined by the size of the neodymium and thorium fluoride complexes. The kinetic dependence of the sorption of neodymium fluoride at a temperature of 650°С is adequately described by a first-order equation for a reversible reaction. The temperature dependence of sorption capacity in the range 550–750°С passes a maximum within 600–650°С.

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LiF–NaF–KF Eutectic Based Fast Molten-Salt Reactor as Np, Am, Cm Transmuter

Cited by 8 publications

References 7 publications

Corrosion Behavior of Candidate Functional Materials for Molten Salts Reactors in LiF–NaF–KF Containing Actinide Fluoride Imitators

Corrosion Behavior of Candidate Functional Materials for Molten Salts Reactors in LiF–NaF–KF Containing Actinide Fluoride Imitators

Investigation of the Quasi-Binary Phase Diagram FLiNaK-NdF3

Sorption of NdF3 and ThF4 from the LiF–NaF–KF Melt

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