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Recovery of tritium from molten lithium blanket

Patent ·
OSTI ID:1600195

Electrochemical cells and methods are described that can be utilized for the recovery of tritium directly from a molten lithium metal solution without the need for a separation or concentration step prior to the electrolytic recovery process. The methods and systems utilize an ion conducting electrolyte that conducts either lithium ion or tritide ion across the electrochemical cell.

Research Organization:
Savannah River Site (SRS), Aiken, SC (United States)
Sponsoring Organization:
USDOE
DOE Contract Number:
AC09-08SR22470
Assignee:
Savannah River Nuclear Solutions, LLC (Aiken, SC)
Patent Number(s):
10,450,660
Application Number:
14/931,018
OSTI ID:
1600195
Country of Publication:
United States
Language:
English

References (7)

Molten salts in fusion nuclear technology journal September 1998
Electrolysis of Lithium Hydride journal November 1958
Lithium Fast-Ionic Conduction in Complex Hydrides: Review and Prospects journal January 2011
The Use of Zirconium-Palladium Windows for the Separation of Tritium from the Liquid Metal Breeder-Blanket of a Fusion Reactor journal September 1983
Electrochemical Extraction of Hydrogen from Molten LiF-LiCI-LiBr and Its Application to Liquid-Lithium Fusion Reactor Blanket Processing journal June 1978
Novel Fast Lithium Ion Conduction in Garnet-Type Li 5 La 3 M 2 O 12 (M = Nb, Ta) journal March 2003
Über eine Bestätigung des Faradayschen Gesetzes an Lithiumhydrid journal November 1923

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