Direct LiT Electrolysis in a Metallic Fusion Blanket
- Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)
A process that simplifies the extraction of tritium from molten lithium-based breeding blankets was developed. The process is based on the direct electrolysis of lithium tritide using a ceramic Li ion conductor that replaces the molten salt extraction step. Extraction of tritium in the form of lithium tritide in the blankets/targets of fusion/fission reactors is critical in order to maintain low concentrations. This is needed to decrease the potential tritium permeation to the surroundings and large releases from unforeseen accident scenarios. Extraction is complicated due to required low tritium concentration limits and because of the high affinity of tritium for the blanket. This work identified, developed and tested the use of ceramic lithium ion conductors capable of recovering hydrogen and deuterium through an electrolysis step at high temperatures.
- Research Organization:
- Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)
- Sponsoring Organization:
- USDOE Office of Environmental Management (EM)
- DOE Contract Number:
- AC09-08SR22470
- OSTI ID:
- 1327787
- Report Number(s):
- SRNL-STI-2016-00572; TRN: US1700320
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
TRITIUM
LITHIUM
IONIC CONDUCTIVITY
ELECTROLYSIS
TRITIUM RECOVERY
LITHIUM IONS
LITHIUM TRITIDES
CONCENTRATION RATIO
TEMPERATURE RANGE 0400-1000 K
DEUTERIUM
HYDROGEN
BREEDING BLANKETS
CERAMICS
HYBRID REACTORS
EXTRACTION