FR2426015A1 - Procede et appareil d'elimination et de recuperation du tritium a partir de l'eau legere et de l'eau lourde - Google Patents

Procede et appareil d'elimination et de recuperation du tritium a partir de l'eau legere et de l'eau lourde

Info

Publication number
FR2426015A1
FR2426015A1 FR7910177A FR7910177A FR2426015A1 FR 2426015 A1 FR2426015 A1 FR 2426015A1 FR 7910177 A FR7910177 A FR 7910177A FR 7910177 A FR7910177 A FR 7910177A FR 2426015 A1 FR2426015 A1 FR 2426015A1
Authority
FR
France
Prior art keywords
tritium
water
recovery
elimination
electrolytic
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.)
Granted
Application number
FR7910177A
Other languages
English (en)
Other versions
FR2426015B1 (fr
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.)
Atomic Energy of Canada Ltd AECL
Original Assignee
Atomic Energy of Canada Ltd AECL
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 Atomic Energy of Canada Ltd AECL filed Critical Atomic Energy of Canada Ltd AECL
Publication of FR2426015A1 publication Critical patent/FR2426015A1/fr
Application granted granted Critical
Publication of FR2426015B1 publication Critical patent/FR2426015B1/fr
Granted legal-status Critical Current

Links

Classifications

    • B—PERFORMING OPERATIONS; TRANSPORTING
    • B01—PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL
    • B01D—SEPARATION
    • B01D59/00—Separation of different isotopes of the same chemical element
    • B01D59/50—Separation involving two or more processes covered by different groups selected from groups B01D59/02, B01D59/10, B01D59/20, B01D59/22, B01D59/28, B01D59/34, B01D59/36, B01D59/38, B01D59/44
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01B—NON-METALLIC ELEMENTS; COMPOUNDS THEREOF; METALLOIDS OR COMPOUNDS THEREOF NOT COVERED BY SUBCLASS C01C
    • C01B4/00—Hydrogen isotopes; Inorganic compounds thereof prepared by isotope exchange, e.g. NH3 + D2 → NH2D + HD
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21B—FUSION REACTORS
    • G21B1/00—Thermonuclear fusion reactors
    • G21B1/11—Details
    • G21B1/115—Tritium recovery
    • 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
    • G21F9/02—Treating gases
    • B—PERFORMING OPERATIONS; TRANSPORTING
    • B01—PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL
    • B01D—SEPARATION
    • B01D59/00—Separation of different isotopes of the same chemical element
    • B01D59/28—Separation by chemical exchange
    • B01D59/32—Separation by chemical exchange by exchange between fluids
    • B—PERFORMING OPERATIONS; TRANSPORTING
    • B01—PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL
    • B01D—SEPARATION
    • B01D59/00—Separation of different isotopes of the same chemical element
    • B01D59/38—Separation by electrochemical methods
    • B01D59/40—Separation by electrochemical methods by electrolysis
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/10—Nuclear fusion reactors
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E60/00—Enabling technologies; Technologies with a potential or indirect contribution to GHG emissions mitigation
    • Y02E60/30—Hydrogen technology
    • Y02E60/32—Hydrogen storage

Landscapes

  • Chemical & Material Sciences (AREA)
  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Organic Chemistry (AREA)
  • Health & Medical Sciences (AREA)
  • Inorganic Chemistry (AREA)
  • General Health & Medical Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Plasma & Fusion (AREA)
  • Electrolytic Production Of Non-Metals, Compounds, Apparatuses Therefor (AREA)
  • Drying Of Gases (AREA)
  • Hydrogen, Water And Hydrids (AREA)
  • Oxygen, Ozone, And Oxides In General (AREA)
  • Separation By Low-Temperature Treatments (AREA)

Abstract

Procédé et appareil pour éliminer le tritium de l'eau lourde et de l'eau légère. Ce procédé consiste à mettre en contact de l'eau d'alimentation tritiée dans une colonne catalytique 10 selon un écoulement à contre-courant avec de l'hydrogène gazeux provenant d'une cuve d'électrolyse 11, de manière à enrichir l'eau d'alimentation avec le tritium provenant de l'hydrogène gazeux électrolytique et à renvoyer l'eau enrichie en tritium dans la cuve d'électrolyse 11 où l'hydrogène électrolytique est produit et envoyé ensuite à travers la colonne catalytique Il en direction ascendante. La teneur en tritium de l'hydrogène gazeux qui quitte le haut de la colonne d'enrichissement 10 par catalyse est encore diminuée dans un épurateur 14 lequel contient un catalyseur qui transfère le tritium dans l'eau liquide qui s'écoule à contre-courant Récupération du tritium.
FR7910177A 1978-05-18 1979-04-23 Procede et appareil d'elimination et de recuperation du tritium a partir de l'eau legere et de l'eau lourde Granted FR2426015A1 (fr)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US05/907,105 US4190515A (en) 1978-05-18 1978-05-18 Apparatus for removal and recovery of tritium from light and heavy water

Publications (2)

Publication Number Publication Date
FR2426015A1 true FR2426015A1 (fr) 1979-12-14
FR2426015B1 FR2426015B1 (fr) 1984-06-22

Family

ID=25423528

Family Applications (1)

Application Number Title Priority Date Filing Date
FR7910177A Granted FR2426015A1 (fr) 1978-05-18 1979-04-23 Procede et appareil d'elimination et de recuperation du tritium a partir de l'eau legere et de l'eau lourde

Country Status (10)

Country Link
US (1) US4190515A (fr)
JP (1) JPS5843717B2 (fr)
BE (1) BE874046A (fr)
CA (1) CA1093500A (fr)
CH (1) CH639048A5 (fr)
DE (1) DE2900912A1 (fr)
FR (1) FR2426015A1 (fr)
GB (1) GB2021536B (fr)
IL (1) IL56289A (fr)
SE (1) SE434260B (fr)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2426643A1 (fr) * 1978-05-22 1979-12-21 Ca Atomic Energy Ltd Procede et appareil d'enrichissement et d'augmentation de la concentration de l'eau lourde

Families Citing this family (26)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB2040899B (en) * 1979-01-22 1982-11-24 Euratom Spent plasma reprocessing system
DE3123860C2 (de) * 1981-06-16 1984-08-09 Kernforschungsanlage Jülich GmbH, 5170 Jülich Verfahren und Vorrichtung zur stufenweisen Anreicherung von Deuterium und/oder Tritium durch Isotopenaustausch
US4532102A (en) * 1983-06-01 1985-07-30 The United States Of America As Represented By The United States Department Of Energy Producing tritium in a homogenous reactor
JPS60228996A (ja) * 1984-04-26 1985-11-14 昭和電工株式会社 トリチウム含有水の処理方法
US5154878A (en) * 1990-04-30 1992-10-13 Anthony Busigin Process and apparatus for tritium recovery
JP3048612B2 (ja) * 1990-09-06 2000-06-05 ペルメレック電極株式会社 電解オゾン発生装置
US5468462A (en) * 1993-12-06 1995-11-21 Atomic Energy Of Canada Limited Geographically distributed tritium extraction plant and process for producing detritiated heavy water using combined electrolysis and catalytic exchange processes
US5451322A (en) * 1994-06-03 1995-09-19 Battelle Memorial Institute Method and apparatus for tritiated water separation
US5591319A (en) * 1995-05-10 1997-01-07 Atomic Energy Of Canada Limited/Energie Atomique Du Canada Limitee Electrolytic pre-enrichment method and apparatus for the combined electrolysis and catalytic exchange process
US6348153B1 (en) 1998-03-25 2002-02-19 James A. Patterson Method for separating heavy isotopes of hydrogen oxide from water
US6190531B1 (en) 1999-07-27 2001-02-20 University Of North Carolina Concentration and removal of tritium and/or deuterium from water contaminated with tritium and/or deuterium
US6984327B1 (en) 2004-11-23 2006-01-10 Patterson James A System and method for separating heavy isotopes of hydrogen oxide from water
GB0512883D0 (en) * 2005-06-24 2005-08-03 Atomic Energy Authority Uk Concentrating tritiated water
US7470350B2 (en) * 2006-04-25 2008-12-30 Ge Healthcare Uk Limited Process for tritium removal from light water
US20100178237A1 (en) * 2007-06-15 2010-07-15 Ge Healthcare Uk Limited Process for recovery of water isotopologues
US10940437B2 (en) 2010-04-02 2021-03-09 Veolia Nuclear Solutions, Inc. Advanced tritium system and advanced permeation system for separation of tritium from radioactive wastes
US20130336870A1 (en) * 2010-04-02 2013-12-19 Kurion, Inc. Advanced Tritium System for Separation of Tritium from Radioactive Wastes and Reactor Water in Light Water Systems
US9981868B2 (en) 2010-04-02 2018-05-29 Kurion, Inc. Mobile processing system for hazardous and radioactive isotope removal
US8597471B2 (en) 2010-08-19 2013-12-03 Industrial Idea Partners, Inc. Heat driven concentrator with alternate condensers
EP2831889B1 (fr) 2012-03-26 2018-11-21 Kurion, Inc. Régénération sélective de résines de milieux spécifiques à un isotope dans des systèmes pour séparation d'isotopes radioactifs de matières de déchets liquides
CA2893114A1 (fr) * 2013-01-30 2014-08-07 Sofia Invest & Engineering Procede et dispositif pour la purification d'air par separation du tritium gazeux et pour la concentration de tritium dans un volume constant d'eau
EP3068518B1 (fr) 2013-11-13 2020-12-16 Savannah River Nuclear Solutions, LLC Décontamination d'eau tritiée
EP3988181A1 (fr) 2014-06-24 2022-04-27 Veolia Nuclear Solutions, Inc. Système mobile de traitement pour élimination d'isotopes dangereux et radioactifs
US9738739B2 (en) 2014-08-20 2017-08-22 George A. Digenis Method of fixing radioactive tritiated water in a stable tritiated polystyrene product
US11058994B2 (en) 2019-01-18 2021-07-13 Savannah River National Solutions, LLC Tritium cleanup system and method
CA3188265C (fr) * 2021-08-09 2023-10-17 Paul Kwon Methode et systeme pour separer un flux d'eau lourde tritie dans un flux d'eau lourde pauvre en tritium et un flux d'eau lourde enrichi de tritium

Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2137906A1 (fr) * 1971-05-17 1972-12-29 Siemens Ag
FR2269493A1 (fr) * 1974-05-03 1975-11-28 Ca Atomic Energy Ltd
US4173620A (en) * 1976-12-27 1979-11-06 Doryokuro Kakunenryo Kaihatsu Jigyodan Extraction method of tritium

Family Cites Families (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE1147203B (de) * 1956-06-16 1963-04-18 Uhde Gmbh Friedrich Verfahren zur Herstellung von mit Deuterium angereichertem Wasser oder Wasserstoff
FR1207117A (fr) * 1958-08-01 1960-02-15 Norsk Hydro Elektrisk Procédé et installation pour la fabrication d'oxyde de deutérium
FR1526867A (fr) * 1966-08-09 1968-05-31 Commissariat Energie Atomique Perfectionnements apportés aux moyens pour retirer le protonium et le tritium de l'eau lourde
FR1593961A (fr) * 1968-12-03 1970-06-01
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
US4217332A (en) * 1976-06-17 1980-08-12 Engelhard Minerals & Chemicals Corporation Process for exchanging hydrogen isotopes between gaseous hydrogen and water

Patent Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2137906A1 (fr) * 1971-05-17 1972-12-29 Siemens Ag
FR2269493A1 (fr) * 1974-05-03 1975-11-28 Ca Atomic Energy Ltd
US4173620A (en) * 1976-12-27 1979-11-06 Doryokuro Kakunenryo Kaihatsu Jigyodan Extraction method of tritium

Non-Patent Citations (1)

* Cited by examiner, † Cited by third party
Title
EXBK/78 *

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2426643A1 (fr) * 1978-05-22 1979-12-21 Ca Atomic Energy Ltd Procede et appareil d'enrichissement et d'augmentation de la concentration de l'eau lourde

Also Published As

Publication number Publication date
CA1093500A (fr) 1981-01-13
IL56289A (en) 1982-01-31
JPS54150599A (en) 1979-11-26
BE874046A (fr) 1979-05-29
US4190515A (en) 1980-02-26
SE434260B (sv) 1984-07-16
JPS5843717B2 (ja) 1983-09-28
SE7813056L (sv) 1979-11-19
DE2900912A1 (de) 1979-11-22
GB2021536B (en) 1982-09-02
FR2426015B1 (fr) 1984-06-22
CH639048A5 (fr) 1983-10-31
GB2021536A (en) 1979-12-05

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Legal Events

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