DE3061377D1 - Process for the recovery of ruthenium present in an aqueous nitric solution and application of this process to a nitric solution obtained by dissolution of irradiated nuclear fuel elements - Google Patents

Process for the recovery of ruthenium present in an aqueous nitric solution and application of this process to a nitric solution obtained by dissolution of irradiated nuclear fuel elements

Info

Publication number
DE3061377D1
DE3061377D1 DE8080400126T DE3061377T DE3061377D1 DE 3061377 D1 DE3061377 D1 DE 3061377D1 DE 8080400126 T DE8080400126 T DE 8080400126T DE 3061377 T DE3061377 T DE 3061377T DE 3061377 D1 DE3061377 D1 DE 3061377D1
Authority
DE
Germany
Prior art keywords
nitric solution
dissolution
recovery
application
nuclear fuel
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.)
Expired
Application number
DE8080400126T
Other languages
English (en)
Inventor
Richard Fitoussi
Sylvie Lours
Claude Musikas
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.)
Commissariat a lEnergie Atomique et aux Energies Alternatives CEA
Original Assignee
Commissariat a lEnergie Atomique CEA
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 Commissariat a lEnergie Atomique CEA filed Critical Commissariat a lEnergie Atomique CEA
Application granted granted Critical
Publication of DE3061377D1 publication Critical patent/DE3061377D1/de
Expired legal-status Critical Current

Links

Classifications

    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
    • C01G55/00—Compounds of ruthenium, rhodium, palladium, osmium, iridium, or platinum
    • C01G55/001—Preparation involving a liquid-liquid extraction, an adsorption or an ion-exchange
    • C—CHEMISTRY; METALLURGY
    • C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22B—PRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
    • C22B3/00—Extraction of metal compounds from ores or concentrates by wet processes
    • C22B3/20—Treatment or purification of solutions, e.g. obtained by leaching
    • C22B3/26—Treatment or purification of solutions, e.g. obtained by leaching by liquid-liquid extraction using organic compounds
    • C22B3/40—Mixtures
    • C22B3/409—Mixtures at least one compound being an organo-metallic compound
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/42—Reprocessing of irradiated fuel
    • G21C19/44—Reprocessing of irradiated fuel of irradiated solid fuel
    • G21C19/46—Aqueous processes, e.g. by using organic extraction means, including the regeneration of these means
    • 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
    • G21F9/007—Recovery of isotopes from radioactive waste, e.g. fission products
    • 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
    • Y02E30/30—Nuclear fission 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
    • Y02P—CLIMATE CHANGE MITIGATION TECHNOLOGIES IN THE PRODUCTION OR PROCESSING OF GOODS
    • Y02P10/00—Technologies related to metal processing
    • Y02P10/20—Recycling
    • 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
    • Y02W—CLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATER TREATMENT OR WASTE MANAGEMENT
    • Y02W30/00—Technologies for solid waste management
    • Y02W30/50—Reuse, recycling or recovery technologies
    • 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
    • Y10—TECHNICAL SUBJECTS COVERED BY FORMER USPC
    • Y10S—TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y10S423/00—Chemistry of inorganic compounds
    • Y10S423/09—Reaction techniques
    • Y10S423/14—Ion exchange; chelation or liquid/liquid ion extraction

Landscapes

  • Engineering & Computer Science (AREA)
  • Chemical & Material Sciences (AREA)
  • Physics & Mathematics (AREA)
  • Organic Chemistry (AREA)
  • High Energy & Nuclear Physics (AREA)
  • General Engineering & Computer Science (AREA)
  • Metallurgy (AREA)
  • General Life Sciences & Earth Sciences (AREA)
  • Materials Engineering (AREA)
  • Mechanical Engineering (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Geology (AREA)
  • Geochemistry & Mineralogy (AREA)
  • Manufacturing & Machinery (AREA)
  • Environmental & Geological Engineering (AREA)
  • Plasma & Fusion (AREA)
  • Inorganic Chemistry (AREA)
  • Extraction Or Liquid Replacement (AREA)
  • Manufacture And Refinement Of Metals (AREA)
  • Inorganic Compounds Of Heavy Metals (AREA)
DE8080400126T 1979-02-08 1980-01-25 Process for the recovery of ruthenium present in an aqueous nitric solution and application of this process to a nitric solution obtained by dissolution of irradiated nuclear fuel elements Expired DE3061377D1 (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR7903241A FR2448506A1 (fr) 1979-02-08 1979-02-08 Procede de recuperation du ruthenium present dans une solution aqueuse acide

Publications (1)

Publication Number Publication Date
DE3061377D1 true DE3061377D1 (en) 1983-01-27

Family

ID=9221748

Family Applications (1)

Application Number Title Priority Date Filing Date
DE8080400126T Expired DE3061377D1 (en) 1979-02-08 1980-01-25 Process for the recovery of ruthenium present in an aqueous nitric solution and application of this process to a nitric solution obtained by dissolution of irradiated nuclear fuel elements

Country Status (5)

Country Link
US (1) US4282112A (de)
EP (1) EP0014629B1 (de)
JP (1) JPS55107744A (de)
DE (1) DE3061377D1 (de)
FR (1) FR2448506A1 (de)

Families Citing this family (11)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5988692A (ja) * 1982-11-15 1984-05-22 動力炉・核燃料開発事業団 硝酸蒸発処理におけるルテニウムの除染効率改良法
JPS59231493A (ja) * 1983-06-15 1984-12-26 住友金属鉱山株式会社 低レベル放射性廃液の処理方法
JPS60161598A (ja) * 1983-12-15 1985-08-23 日本原子力研究所 放射性ルテニウムを含む放射性廃液の処理方法
JPH0631840B2 (ja) * 1986-10-09 1994-04-27 健次 本島 放射性ルテニウムの除去方法
FR2607021B1 (fr) * 1986-11-21 1990-11-16 Commissariat Energie Atomique Procede d'extraction selective de metaux de transition a partir de solutions acides par des systemes de ligands azotes polydentes et d'echangeurs cationiques
FR2672582B1 (fr) * 1991-02-08 1993-04-23 Comurhex Procede d'elimination du ruthenium contenu dans des solutions uraniferes.
JPH06180392A (ja) * 1992-12-15 1994-06-28 Power Reactor & Nuclear Fuel Dev Corp 高レベル放射性廃液からルテニウムを分離回収する方法
US20040127584A1 (en) * 2002-12-31 2004-07-01 Phillips Petroleum Company Chemical vapor deposition synthesis of polymerization catalyst composition
WO2009086023A2 (en) * 2007-12-19 2009-07-09 Applied Materials, Inc. Methods for cleaning process kits and chambers, and for ruthenium recovery
JP6030579B2 (ja) * 2012-11-16 2016-11-24 田中貴金属工業株式会社 使用済み色素溶液からのＲｕ錯体色素の回収方法
RU2542897C2 (ru) * 2013-07-18 2015-02-27 Федеральное государственное автономное образовательное учреждение высшего образования "Новосибирский национальный исследовательский государственный университет" (Новосибирский государственный университет, НГУ) Способ извлечения рутения из комплексных соединений рутения

Family Cites Families (11)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2967209A (en) * 1948-06-18 1961-01-03 William E Grummitt Recovery of ruthenium values
US2894816A (en) * 1950-09-27 1959-07-14 Herbert H Hyman Solvent extraction of ruthenium
US2982601A (en) * 1954-03-03 1961-05-02 Archie S Wilson Separation of uranyl and ruthenium values by the tributyl phosphate extraction process
US2796424A (en) * 1954-03-04 1957-06-18 Wallace W Schulz Separation process by adsorption
US3208819A (en) * 1963-06-19 1965-09-28 Richard M Wallace Method for decontaminating nuclear fuels containing ruthenium complexes
GB1047232A (de) * 1963-07-12
BE650266A (de) * 1964-07-08 1900-01-01
FR1515048A (fr) * 1966-11-03 1968-03-01 Commissariat Energie Atomique Perfectionnements apportés aux procédés de décontamination de milieux contenant des produits de fission contaminés notamment avec du ruthénium et aux procédés deséparation du ruthénium
US4011297A (en) * 1972-06-02 1977-03-08 Outokumpu Oy In-situ ph measurement of organic-continuous solvent extraction processes
US4012481A (en) * 1975-11-07 1977-03-15 Pgp Industries, Inc. Process for the separation of platinum group metals
ZA763680B (en) * 1976-06-21 1978-02-22 Nat Inst Metallurg The separation and purification of ruthenium

Also Published As

Publication number Publication date
EP0014629A1 (de) 1980-08-20
JPS55107744A (en) 1980-08-19
JPS6260449B2 (de) 1987-12-16
FR2448506A1 (fr) 1980-09-05
FR2448506B1 (de) 1982-05-21
US4282112A (en) 1981-08-04
EP0014629B1 (de) 1982-12-22

Similar Documents

Publication Publication Date Title
DE2861037D1 (en) Process and reactor for producing a treating aqueous solution containing at least hydrogenoperoxide ions and hydroxyl ions according to predetermined concentrations and use of the reactor
GB2011697B (en) Method for the recovery of actinide elements from nuclear reactor waste
DE3061377D1 (en) Process for the recovery of ruthenium present in an aqueous nitric solution and application of this process to a nitric solution obtained by dissolution of irradiated nuclear fuel elements
GB2011696A (en) Method for recovering palladium and technetium values from nuclear fuel reprocessing wast solutions
FR2322100A1 (fr) Procede d'extraction liquide-liquide pour la recuperation et la repartition des actinides a partir de solutions aqueuses acides d'origine nucleaire
IT1073822B (it) Perfezionamento nelle disposizioni di assorbimento di forze assiali su elementi di combustibile in reattori nucleari
JPS5453798A (en) Method of producing nuclear fuel of puo2 and uo2
GB2021303B (en) Nuclear reactor fuel assemblies
IT1077451B (it) Procedimento per il trattamento di rifiuti solidi in modo da produrre un combustibile
ZA761910B (en) An improvement in or relating to process for dissolving radioactive corrosion products from internal surfaces of a nuclear reactor
GB2013643B (en) Process for the recovery of uranium contained in phosphate solutions
JPS53139087A (en) Method of checking fuel assembly in nuclear reactor
DE2965965D1 (en) Method of treating alkaline solutions containing radioactive iodine during the reprocessing of nuclear fuels
JPS53113998A (en) Method of holding radioactive volatile substance produced in regenerating nuclear fuel
DE2860908D1 (en) Process for preparing hydroxylammonium salts in reactors made of stainless steel
BR7802892A (pt) Processo para impedir a dispersao,no ambiente,de material radioativo em hastes de combustivel nuclear servido
GB2118759B (en) Process for the recovery of plutonium from aqueous nitric solutions
JPS53139097A (en) Method of recovering nuclear fuel substance
GB1193596A (en) Ion Exchange Process for Recovering Americium and Curium.
GB2065955B (en) Production of tritium in a nuclear reactor
GB1549641A (en) Method of measuring the position of regulating rods in a nuclear reactor
GB2238116B (en) Method of measuring the concentration of radioactive iodine in aqueous, nitrate solutions of nuclear fuels and/or fission products
JPS53147200A (en) Treating method of radioactive waste liquid
GB838324A (en) Process for enclosing a body containing fissionable material in a jacket
AU496042B2 (en) Improvements in or relating to process for dissolving radioactive corrosion products from internal surfaces ofa nuclear reactor

Legal Events

Date Code Title Description
8339 Ceased/non-payment of the annual fee