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WO2013166505A3 - LITHIUM TRITIDE (LiT) ELECTROLYSIS CELL FOR REMOVING TRITIUM FROM LITHIUM METAL - Google Patents

LITHIUM TRITIDE (LiT) ELECTROLYSIS CELL FOR REMOVING TRITIUM FROM LITHIUM METAL Download PDF

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Publication number
WO2013166505A3
WO2013166505A3 PCT/US2013/039750 US2013039750W WO2013166505A3 WO 2013166505 A3 WO2013166505 A3 WO 2013166505A3 US 2013039750 W US2013039750 W US 2013039750W WO 2013166505 A3 WO2013166505 A3 WO 2013166505A3
Authority
WO
WIPO (PCT)
Prior art keywords
lithium
lit
tritide
electrolysis cell
lithium metal
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Ceased
Application number
PCT/US2013/039750
Other languages
French (fr)
Other versions
WO2013166505A2 (en
Inventor
Joseph C. Farmer
Michael Dunne
Bassem S. EL-DASHER
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Lawrence Livermore National Security LLC
Original Assignee
Lawrence Livermore National Security LLC
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Lawrence Livermore National Security LLC filed Critical Lawrence Livermore National Security LLC
Publication of WO2013166505A2 publication Critical patent/WO2013166505A2/en
Publication of WO2013166505A3 publication Critical patent/WO2013166505A3/en
Anticipated expiration legal-status Critical
Ceased legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21G—CONVERSION OF CHEMICAL ELEMENTS; RADIOACTIVE SOURCES
    • G21G1/00—Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes
    • G21G1/001—Recovery of specific isotopes from irradiated targets
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/28—Treating solids
    • G21F9/30—Processing
    • G21F9/308—Processing by melting the waste
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21G—CONVERSION OF CHEMICAL ELEMENTS; RADIOACTIVE SOURCES
    • G21G1/00—Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes
    • G21G1/001—Recovery of specific isotopes from irradiated targets
    • G21G2001/0094—Other isotopes not provided for in the groups listed above

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • General Chemical & Material Sciences (AREA)
  • Extraction Or Liquid Replacement (AREA)
  • Electrolytic Production Of Metals (AREA)

Abstract

Lithium hydroxide (LiOH) can be used as solvent for extracting lithium tritide from molten lithium metal, such as that found in a lithium blanket of a nuclear fusion reactor. Use of LiOH avoids the problems of generation of acids, particularly of HF, by the prior art process. Electrochemical cells for electrolyzing LiT are provided with suitably high anode and cathode areas or suitably long flow paths, which have been found to be required for superior operation.
PCT/US2013/039750 2012-05-04 2013-05-06 LITHIUM TRITIDE (LiT) ELECTROLYSIS CELL FOR REMOVING TRITIUM FROM LITHIUM METAL Ceased WO2013166505A2 (en)

Applications Claiming Priority (4)

Application Number Priority Date Filing Date Title
US201261643066P 2012-05-04 2012-05-04
US201261643119P 2012-05-04 2012-05-04
US61/643,119 2012-05-04
US61/643,066 2012-05-04

Publications (2)

Publication Number Publication Date
WO2013166505A2 WO2013166505A2 (en) 2013-11-07
WO2013166505A3 true WO2013166505A3 (en) 2013-12-27

Family

ID=49515055

Family Applications (2)

Application Number Title Priority Date Filing Date
PCT/US2013/039750 Ceased WO2013166505A2 (en) 2012-05-04 2013-05-06 LITHIUM TRITIDE (LiT) ELECTROLYSIS CELL FOR REMOVING TRITIUM FROM LITHIUM METAL
PCT/US2013/039751 Ceased WO2013166506A2 (en) 2012-05-04 2013-05-06 Non-centrifugal contactor for molten-salt tritium-extraction process

Family Applications After (1)

Application Number Title Priority Date Filing Date
PCT/US2013/039751 Ceased WO2013166506A2 (en) 2012-05-04 2013-05-06 Non-centrifugal contactor for molten-salt tritium-extraction process

Country Status (1)

Country Link
WO (2) WO2013166505A2 (en)

Families Citing this family (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP3215657B1 (en) 2014-11-04 2020-02-26 Savannah River Nuclear Solutions, LLC Recovery of tritium from molten lithium blanket
US10844501B2 (en) * 2018-03-08 2020-11-24 Uchicago Argonne, Llc Carbon supported single atom carbon dioxide reduction electro catalysts
US12417852B1 (en) * 2020-01-14 2025-09-16 Beam Alpha, Inc. Ion transport
US11554363B2 (en) 2020-09-01 2023-01-17 Uchicago Argonne, Llc Method of preparing electrocatalysts for converting carbon dioxide to chemicals
CN112117020B (en) * 2020-09-09 2022-11-22 中国工程物理研究院核物理与化学研究所 Method for treating tritium water by photo-thermal concerted catalysis
EP4257227A1 (en) 2022-04-04 2023-10-11 Renaissance Fusion Device and method for extraction of lithium hydrides

Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3957597A (en) * 1974-05-28 1976-05-18 The United States Of America As Represented By The United States Energy Research And Development Administration Process for recovering tritium from molten lithium metal
US5154878A (en) * 1990-04-30 1992-10-13 Anthony Busigin Process and apparatus for tritium recovery
US20030058980A1 (en) * 2000-10-31 2003-03-27 El-Sharaway El-Badawy A. Method and apparatus for the transmutation of nuclear waste with tandem production of tritium
US20040007466A1 (en) * 2002-03-28 2004-01-15 Seo Chung Seok Method of reducing spent oxide nuclear fuel into nuclear-fuel metal using LiCl-Li2O salt, cathode electrode assembly used in the method, and reduction device including the assembly
JP2011158374A (en) * 2010-02-02 2011-08-18 Toyama Univ Method and system for decontaminating tritium contaminant

Family Cites Families (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US8741150B2 (en) * 2008-09-29 2014-06-03 Korea Institute Of Geosciences And Mineral Resources Lithium recovery device using separator reservoir, lithium recovery method and lithium adsorption/desorption system using the same
IT1400531B1 (en) * 2010-06-22 2013-06-11 Commissariat Energie Atomique PROCESS FOR THE DETRIFICATION OF SOFT HOUSEKEEPING WASTE AND RELATIVE PLANT

Patent Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3957597A (en) * 1974-05-28 1976-05-18 The United States Of America As Represented By The United States Energy Research And Development Administration Process for recovering tritium from molten lithium metal
US5154878A (en) * 1990-04-30 1992-10-13 Anthony Busigin Process and apparatus for tritium recovery
US20030058980A1 (en) * 2000-10-31 2003-03-27 El-Sharaway El-Badawy A. Method and apparatus for the transmutation of nuclear waste with tandem production of tritium
US20040007466A1 (en) * 2002-03-28 2004-01-15 Seo Chung Seok Method of reducing spent oxide nuclear fuel into nuclear-fuel metal using LiCl-Li2O salt, cathode electrode assembly used in the method, and reduction device including the assembly
JP2011158374A (en) * 2010-02-02 2011-08-18 Toyama Univ Method and system for decontaminating tritium contaminant

Also Published As

Publication number Publication date
WO2013166505A2 (en) 2013-11-07
WO2013166506A3 (en) 2013-12-27
WO2013166506A2 (en) 2013-11-07

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