Direct LiT Electrolysis in a Metallic Fusion Blanket

Olson, Luke

doi:10.2172/1327787

Title: Direct LiT Electrolysis in a Metallic Fusion Blanket

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Abstract

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.

Authors:

Olson, Luke ^[1]

Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

Publication Date:: Fri Sep 30 00:00:00 EDT 2016

Research Org.:: Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

Sponsoring Org.:: USDOE Office of Environmental Management (EM)

OSTI Identifier:: 1327787

Report Number(s):: SRNL-STI-2016-00572
TRN: US1700320

DOE Contract Number:: AC09-08SR22470

Resource Type:: Technical Report

Country of Publication:: United States

Language:: English

Subject:: 37 INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CHEMISTRY; 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

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                    Olson, Luke. Direct LiT Electrolysis in a Metallic Fusion Blanket.  United States: N. p., 2016. 
        Web.  doi:10.2172/1327787.

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                    Olson, Luke. Direct LiT Electrolysis in a Metallic Fusion Blanket.  United States.  https://doi.org/10.2172/1327787

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                    Olson, Luke. 2016.  
        "Direct LiT Electrolysis in a Metallic Fusion Blanket".  United States.  https://doi.org/10.2172/1327787.  https://www.osti.gov/servlets/purl/1327787.

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@article{osti_1327787,

  title        = {Direct LiT Electrolysis in a Metallic Fusion Blanket},

  author       = {Olson, Luke},

  abstractNote = {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.},

  doi          = {10.2172/1327787},

  url          = {https://www.osti.gov/biblio/1327787},
  journal      = {},
number       = ,

  volume       = ,

  place        = {United States},

  year         = {Fri Sep 30 00:00:00 EDT 2016},

  month        = {Fri Sep 30 00:00:00 EDT 2016}

}

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