Extraction of thorium from LiCl–KCl molten salts by forming Al–Th alloys: a new pyrochemical method for the reprocessing of thorium-based spent fuels-Reference-Cited by-同舟云学术

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Extraction of thorium from LiCl–KCl molten salts by forming Al–Th alloys: a new pyrochemical method for the reprocessing of thorium-based spent fuels

Published:2013 Issue:45 Volume:3 Page:23539
ISSN:2046-2069
Container-title:RSC Advances
language:en
Short-container-title:RSC Adv.

Author:

Liu Ya-Lan,Yan Yong-De,Han Wei,Zhang Mi-Lin,Yuan Li-Yong,Liu Kui,Ye Guo-An,He Hui,Chai Zhi-Fang,Shi Wei-Qun

Publisher

Royal Society of Chemistry (RSC)

Subject

General Chemical Engineering,General Chemistry

Link

http://pubs.rsc.org/en/content/articlepdf/2013/RA/C3RA43292K

Reference41 articles.

1. Modeling and simulation of nuclear fuel materials

2. Nuclear fuel in generation II and III reactors: research issues related to high burn-up

3. Electrochemical behaviour of thorium(IV) in molten LiF–CaF2 medium on inert and reactive electrodes

4. Separation of actinides from rare earth elements by means of molten salt electrorefining with anodic dissolution of U–Pu–Zr alloy fuel

5. Electrochemical reduction behavior of U3O8 powder in a LiCl molten salt

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1. Concentration effects on dynamic fluctuations in structure and thermodynamic properties of LiCl–AlCl3 molten Salt: Insights from ab initio molecular dynamics;Journal of Molecular Liquids;2024-05

2. Electrochemical recovery of lithium-ion battery materials from molten salts by microstructural characterization using X-ray imaging;Cell Reports Physical Science;2023-04

3. Electrochemical properties and extraction of Dy on liquid Sn electrode in LiCl–KCl molten salt;Journal of Solid State Electrochemistry;2023-01-22

4. Electrochemical behavior and separation of dysprosium from molten NaCl-KCl eutectic by co-reduction with aluminum;Separation and Purification Technology;2022-11

5. Electrochemical extraction of uranium from U3O8 by preparing flower-shaped Al-U intermetallics in LiCl-KCl-AlCl3 melts;Journal of Nuclear Materials;2022-07

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