UO2 solubility and chemical interactions in molten LiCl-Li2O-Reference-Cited by-同舟云学术

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UO2 solubility and chemical interactions in molten LiCl-Li2O

Published:2024-10 Issue: Volume:599 Page:155220
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Gonzalez Mario Alberto^ORCID,Leavitt Cameron,Holland Justin M.,Simpson Michael F.^ORCID

Publisher

Elsevier BV

Reference22 articles.

1. Separation and recovery of uranium metal from spent light water reactor fuel via electrolytic reduction and electrorefining;Herrmann;Nucl. Technol.,2010

2. Pyroprocessing technology developments at KAERI;Lee;Nucl. Eng. Technol.,2011

3. Electrochemical processing of spent nuclear fuels: an overview of oxide reduction in pyroprocessing technology;Choi;Prog. Nat. Sci. Mater. Int.,2015

4. A conceptual study of pyroprocessing for recovering actinides from spent oxide fuels;Yoo;Nucl. Eng. Technol.,2008

5. Underpotential deposition of Li in a molten LiCl-Li2O electrolyte for the electrochemical reduction of U from uranium oxides;Hur;Electrochem. Commun.,2010

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