WO2013166506A3 - Non-centrifugal contactor for molten-salt tritium-extraction process - Google Patents

Non-centrifugal contactor for molten-salt tritium-extraction process Download PDF

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Publication number
WO2013166506A3
WO2013166506A3 PCT/US2013/039751 US2013039751W WO2013166506A3 WO 2013166506 A3 WO2013166506 A3 WO 2013166506A3 US 2013039751 W US2013039751 W US 2013039751W WO 2013166506 A3 WO2013166506 A3 WO 2013166506A3
Authority
WO
WIPO (PCT)
Prior art keywords
molten
lithium
tritium
salt
centrifugal contactor
Prior art date
Application number
PCT/US2013/039751
Other languages
French (fr)
Other versions
WO2013166506A2 (en
Inventor
Joseph C. Farmer
Michael Dunne
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 WO2013166506A2 publication Critical patent/WO2013166506A2/en
Publication of WO2013166506A3 publication Critical patent/WO2013166506A3/en

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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

Abstract

A method for removing lithium tritide (LiT) from a lithium blanket involves transferring molten lithium containing LiT from the lithium blanket to a non-centrifugal contactor and carrying out further extraction and the separation steps to recover the tritium. A fraction of LiT from the molten lithium is extracted into a solvent phase containing a molten lithium salt. The phases are separated after extraction in a cyclonic or hydrocyclonic phase separator that is fluidically connected to the extraction column of the non-centrifugal contactor.
PCT/US2013/039751 2012-05-04 2013-05-06 Non-centrifugal contactor for molten-salt tritium-extraction process WO2013166506A2 (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
WO2013166506A2 WO2013166506A2 (en) 2013-11-07
WO2013166506A3 true WO2013166506A3 (en) 2013-12-27

Family

ID=49515055

Family Applications (2)

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

Family Applications Before (1)

Application Number Title Priority Date Filing Date
PCT/US2013/039750 WO2013166505A2 (en) 2012-05-04 2013-05-06 LITHIUM TRITIDE (LiT) ELECTROLYSIS CELL FOR REMOVING TRITIUM FROM LITHIUM METAL

Country Status (1)

Country Link
WO (2) WO2013166505A2 (en)

Families Citing this family (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US10450660B2 (en) 2014-11-04 2019-10-22 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
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
WO2010035956A2 (en) * 2008-09-29 2010-04-01 한국지질자원연구원 Lithium recovery device using separator reservoir, lithium recovery method and lithium adsorption/desorption system using the same
WO2011161709A1 (en) * 2010-06-22 2011-12-29 Enea Agenzia Nazionale Per Le Nuove Tecnologie Process for the detritiation of soft housekeeping waste and plant thereof

Family Cites Families (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
KR100593790B1 (en) * 2003-03-28 2006-07-03 한국원자력연구소 Method for electrolytic reduction of oxide spent fuel in LiCl-Li2O, cathode electrode assembly for applying the method, and device having the cathode electrode
JP5717348B2 (en) * 2010-02-02 2015-05-13 国立大学法人富山大学 Tritium contaminant decontamination method and system

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
WO2010035956A2 (en) * 2008-09-29 2010-04-01 한국지질자원연구원 Lithium recovery device using separator reservoir, lithium recovery method and lithium adsorption/desorption system using the same
WO2011161709A1 (en) * 2010-06-22 2011-12-29 Enea Agenzia Nazionale Per Le Nuove Tecnologie Process for the detritiation of soft housekeeping waste and plant thereof

Also Published As

Publication number Publication date
WO2013166505A2 (en) 2013-11-07
WO2013166505A3 (en) 2013-12-27
WO2013166506A2 (en) 2013-11-07

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