Chemical behavior of grey phases in LiCl molten salt for oxide reduction in pyroprocessing

2018 ◽  
Vol 318 (3) ◽  
pp. 1923-1930 ◽  
Author(s):  
Sung-Wook Kim ◽  
Min Ku Jeon ◽  
Wooshin Park ◽  
Dong Hyun Heo ◽  
Sang-Kwon Lee ◽  
...  
Keyword(s):  
Molten Salt ◽  
Oxide Reduction ◽  
Chemical Behavior

Chemical behavior of Li2BeF4 molten salt as a liquid tritium breeder

2001 ◽  
Vol 58-59 ◽  
pp. 667-672 ◽  
Author(s):  
H Nishimura ◽  
A Suzuki ◽  
T Terai ◽  
M Yamawaki ◽  
S Tanaka ◽  
...  
Keyword(s):  
Molten Salt ◽  
Chemical Behavior ◽  
Tritium Breeder

scholarly journals Electrochemical Behavior of CsI in LiCl Molten Salt

2020 ◽  
Vol 2020 ◽  
pp. 1-6
Author(s):  
Sung-Wook Kim ◽  
Sang-Kwon Lee ◽  
Min Ku Jeon ◽  
Eun-Young Choi
Keyword(s):  
Molten Salt ◽  
Electrochemical Behavior ◽  
Spent Nuclear Fuel ◽  
Electrochemical Reaction ◽  
Oxide Phase ◽  
Oxide Reduction ◽  
Cathode Reaction ◽  
Anode Reaction ◽  
Long Lifetime ◽  
Cs Ions

The electrochemical behavior of CsI in LiCl molten salt was investigated to identify its impact on the electrolytic oxide reduction of oxide-phase spent nuclear fuels by combined electrolysis and cyclic voltammetry experiments of LiCl-CsI in comparison with LiCl, LiCl-CsCl, and LiCl-LiI. It was found that Cs+ ions were hardly involved in the cathode reaction, and reduction of Li+ ions occurred dominantly in the cathode. In contrast, incorporation of I− ions induced low-potential anode reaction compared with the I− ion-free cases. Such additional electrochemical reaction resulted in the generation of I2 and/or ICl gases, which would increase a process burden for treating 129I with exceptionally long lifetime. In this respect, separating CsI from spent nuclear fuel before the electrolytic oxide reduction is recommended for the purpose of efficient waste management.

HEAT PUMPS FOR MOLTEN SALT ENERGY STORAGE

2017 ◽  
Author(s):  
M. Ramos Gonzalez ◽  
William Culbreth
Keyword(s):  
Energy Storage ◽  
Molten Salt ◽  
Heat Pumps
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