Study on the mechanism of deoxidization and purification for Li2BeF4 molten salt via graphite nanoparticles-Reference-Cited by-同舟云学术

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Study on the mechanism of deoxidization and purification for Li2BeF4 molten salt via graphite nanoparticles

Published:2017-04 Issue: Volume:487 Page:317-322
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Xie Meng-ya,Li Li,Ding Ya-ping,Zhang Guo-xin

Funder

Strategic Priority Research Program of the Chinese Academy of Sciences

National Science Foundation of China

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference26 articles.

1. Steam reforming of methane using double-walled reformer tubes containing high-temperature thermal storage Na2CO3/MgO composites for solar fuel production;Gokon;Energy,2014

2. Assessment of Candidate Molten Salt Coolants for the Advanced High Temperature Reactor (AHTR);Williams,2006

3. Corrosion study of a highly durable electrolyzer based on cold crucible technique for pyrochemical reprocessing of spent nuclear oxide fuel;Takeuchi;J. Nucl. Mater.,2013

4. Corrosion of 316 stainless steel in high temperature molten Li2BeF4 (FLiBe) salt;Zheng;J. Nucl. Mater.,2015

5. The Development Status of Molten-salt Breeder Reactors;Rosenthal,1972

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1. Effect of oxide impurities on the dissolution behavior of Th⁴⁺, Be²⁺ and U⁴⁺ in fluoride salts;RSC Advances;2024

2. Thermodynamic Substantiation and Experimental Studies of the Carbothermic Reduction of the FLiBe–BeO System;Russian Metallurgy (Metally);2023-02

3. Review of the solubility, monitoring, and purification of impurities in molten salts for energy storage in concentrated solar power plants;Renewable and Sustainable Energy Reviews;2020-10

4. Carburization of metals by a chemical mechanism of carbon transport through molten fluoride salts;Journal of Nuclear Materials;2020-10

5. Chemical compatibility of silicon carbide in molten fluoride salts for the fluoride salt-cooled high temperature reactor;Journal of Nuclear Materials;2019-10

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