Fast-spectrum, liquid-fueled reactors

Lizin, A. A.; Tomilin, S. V.; Ponomarev, L. I.; Fedorov, Yu. S.; Hirose, Yasuo

doi:10.1016/b978-0-08-101126-3.00012-9

Cited by 3 publications

(3 citation statements)

References 53 publications

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“…The following salt mixtures are those most often studied as promising fuel salts or coolants for MSRs: LiF-BeF 2 , LiF-NaF-BeF 2 , LiF-NaF-KF, NaF-KF, NaF-NaBF 4 , LiCl-KCl-MgCl 2 , and NaNO 3 -KNO 3 [1,[6][7][8]. Among the other salt systems that have been proposed, the eutectic melt of lithium, sodium, and potassium fluorides (0.465LiF-0.115NaF-0.420KF, i.e., FLiNaK) has several advantages in terms of the physicochemical properties, as well as an increased ability to dissolve actinide and lanthanide fluorides [5,[9][10][11].…”

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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“…Fluoride salt fast reactor and chloride salt fast reactor are two typical molten salt fast reactors that can be used for TRUs transmutation 22 . In a fluoride salt fast reactor, TRUs have a low solubility less than 4 mol% in FLiBe salt, 23 which limits their transmutation ability to some extent.…”

Section: Introductionmentioning

confidence: 99%

Potential of transuranics transmutation in a thorium‐based chloride salt fast reactor

Cui

et al. 2022

Intl J of Energy Research

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A thorium-based chloride salt fast reactor (TCLFR) for transuranics (TRUs) transmutation is proposed to decrease radioactive nuclear waste. The TCLFR core uses two types of fuel: liquid nuclear fuel with TRUs and thorium being dissolved in chloride and solid transmutation rod with only TRUs fuel. The transmutation capability of TCLFR with a core power of 2500 MWth is investigated utilizing three different reactor core configurations, namely ThCore, GdCore, and TcCore, and compared to the standard Molten Chloride Fast Reactor (MCFR) while maintaining most of the geometric parameters. Important burnup parameters such as transmutation rate (TRE) and transmutation ratio (TRO) are extracted and analyzed. Besides, the neutron spectrum shift and the relevant safety parameters, including power peak factor, temperature coefficient of reactivity (TCR) and effective delayed neutron fraction (β eff ) are all explored. The results demonstrate that all the TCLFR cores can transmute TRUs effectively. TRUs have a high online refueling amount of TRUs in TcCore and GdCore due to their low conversion ratio (CR). The TRE in the TcCore and GdCore is 292.77 kg/GWth/year and 258.31 kg/GWth/year, respectively, which is significantly higher than the TRE in the MCFR, which is 171.21 kg/GWth/year. As a result of the production of U-233 compensates for the consumption of TRUs, the refueling amount of TRUs decreases, and the TRE in the ThCore is only 96.29 kg/GWth/year, which is approximately 44% lower than that in the MCFR.

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“…Salt melts based on LiF-BeF 2 and LiF-NaF-KF have been verified as promising media ensuring the operation of liquid-salt reactors with low overpressure. 1,2 Molten alkaline and alkaline Earth metal fluorides [3][4][5][6] and chlorides 7,8 demonstrate excellent hydrodynamic and heat exchange properties, low vapor pressures in a wide operating temperature range (from 500 °C to 850 °C) and do not interact with fuel in case of leakage. However, molten fluorides are aggressive to metallic structural materials.…”

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confidence: 99%

Electrochemical Behavior of Chromium Difluoride in Molten Lithium and Beryllium Fluoride Mixtures

Arkhipov,

Zaikov,

Arkhipov

et al. 2023

J. Electrochem. Soc.

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The interaction between CrF2 and a molten binary LiF-BeF2 mixture has been studied using the electrochemical methods. The polarization of the chromium electrode relative to the dynamic beryllium electrode was measured. The obtained voltammetry data elucidates that under the experimental conditions, chromium is observed exclusively in one valence form. According to the cathode polarization dependences, it is established that the reduction of chromium ions in the metal occurs by a two-electron electrode reaction. The equilibrium concentrations of chromium were experimentally measured at the temperatures of 923, 973, and 1023 K at different chromium fluoride concentrations in the melt. The oxidation degree of chromium, dissolved in the melt, was calculated according to the concentration dependences of the equilibrium potentials. A thermodynamic analysis of the chromium difluoride dissolution in a molten mixture of lithium and beryllium fluorides was performed. The formation of dilute solutions of chromium difluoride is accompanied by slight deviations of the salt system from Raoult's laws.

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Fast-spectrum, liquid-fueled reactors

Cited by 3 publications

References 53 publications

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

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

Potential of transuranics transmutation in a thorium‐based chloride salt fast reactor

Electrochemical Behavior of Chromium Difluoride in Molten Lithium and Beryllium Fluoride Mixtures

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