Process for recovering tritium from molten lithium metal
Abstract
Lithium tritide (LiT) is extracted from molten lithium metal that has been exposed to neutron irradiation for breeding tritium within a thermonuclear or fission reactor. The extraction is performed by intimately contacting the molten lithium metal with a molten lithium salt, for instance, lithium chloride - potassium chloride eutectic to distribute LiT between the salt and metal phases. The extracted tritium is recovered in gaseous form from the molten salt phase by a subsequent electrolytic or oxidation step.
- Inventors:
-
- Naperville, IL
- Issue Date:
- Research Org.:
- Argonne National Laboratory (ANL), Argonne, IL (United States)
- OSTI Identifier:
- 862544
- Patent Number(s):
- 3957597
- Assignee:
- United States of America as represented by United States Energy (Washington, DC)
- Patent Classifications (CPCs):
-
C - CHEMISTRY C01 - INORGANIC CHEMISTRY C01B - NON-METALLIC ELEMENTS
C - CHEMISTRY C25 - ELECTROLYTIC OR ELECTROPHORETIC PROCESSES C25B - ELECTROLYTIC OR ELECTROPHORETIC PROCESSES FOR THE PRODUCTION OF COMPOUNDS OR NON-METALS
- DOE Contract Number:
- W-31109-ENG-38
- Resource Type:
- Patent
- Country of Publication:
- United States
- Language:
- English
- Subject:
- process; recovering; tritium; molten; lithium; metal; tritide; extracted; exposed; neutron; irradiation; breeding; thermonuclear; fission; reactor; extraction; performed; intimately; contacting; salt; instance; chloride; potassium; eutectic; distribute; phases; recovered; gaseous; form; phase; subsequent; electrolytic; oxidation; step; lithium chloride; metal phases; fission reactor; neutron irradiation; molten lithium; molten salt; lithium metal; potassium chloride; lithium salt; recovering tritium; oxidation step; metal phase; gaseous form; /205/376/423/976/
Citation Formats
Maroni, Victor A. Process for recovering tritium from molten lithium metal. United States: N. p., 1976.
Web.
Maroni, Victor A. Process for recovering tritium from molten lithium metal. United States.
Maroni, Victor A. Thu .
"Process for recovering tritium from molten lithium metal". United States. https://www.osti.gov/servlets/purl/862544.
@article{osti_862544,
title = {Process for recovering tritium from molten lithium metal},
author = {Maroni, Victor A},
abstractNote = {Lithium tritide (LiT) is extracted from molten lithium metal that has been exposed to neutron irradiation for breeding tritium within a thermonuclear or fission reactor. The extraction is performed by intimately contacting the molten lithium metal with a molten lithium salt, for instance, lithium chloride - potassium chloride eutectic to distribute LiT between the salt and metal phases. The extracted tritium is recovered in gaseous form from the molten salt phase by a subsequent electrolytic or oxidation step.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Thu Jan 01 00:00:00 EST 1976},
month = {Thu Jan 01 00:00:00 EST 1976}
}
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