Liquidus temperature study of LiF–NaF–KF-based melts simulating the fuel salt of a molten-salt reactor for Np, Am, Cm transmutation

IF 0.4 4区 工程技术 Q4 NUCLEAR SCIENCE & TECHNOLOGY Atomic Energy Pub Date : 2024-12-05 DOI:10.1007/s10512-024-01147-y
M. N. Belonogov, I. A. Volkov, N. D. Dyrda, G. N. Rykovanov, I. V. Sannikov, P. A. Sannikova, R. R. Fazylov, D. V. Khmelnitsky, V. A. Shelan
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引用次数: 0

Abstract

Experiments were carried out to determine the liquidus temperature of 46.5LiF–11.5NaF–42KF-based melts simulating the fuel salt of a molten-salt burner operating in a Np, Am, Cm transmutation mode without the consumption of plutonium. The liquidus temperature was determined by differential scanning calorimetry; the melt composition was monitored by atomic emission, alpha, and gamma spectrometry. Melts containing PuF3 and UF4, as well as NdF3 and NiF2 simulating the products of fission and corrosion of structural materials were studied. For the actinide fluoride mole fraction of 5–15 mol% in the LiF–NaF–KF-based fuel salt in the presence of fission and corrosion products, the liquidus temperature of the melts was equal to 485–580 °C.

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来源期刊
Atomic Energy
Atomic Energy 工程技术-核科学技术
CiteScore
1.00
自引率
20.00%
发文量
100
审稿时长
4-8 weeks
期刊介绍: Atomic Energy publishes papers and review articles dealing with the latest developments in the peaceful uses of atomic energy. Topics include nuclear chemistry and physics, plasma physics, accelerator characteristics, reactor economics and engineering, applications of isotopes, and radiation monitoring and safety.
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Liquidus temperature study of LiF–NaF–KF-based melts simulating the fuel salt of a molten-salt reactor for Np, Am, Cm transmutation An analysis of machine learning for the safety justification of VVER reactors Development of a neural-network methodology for the safety justification of VVER reactors in manoeuvring modes Formation of intermetallics during the metallization of model nuclear fuel based on uranium dioxide containing oxides of rare earth metals and palladium Self-protection of fast lead-cooled reactors against the partial blockage of the core flow area
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