FR2413762A1 - Procede pour recuperer les actinides des solutions de residus resultant du traitement de recyclage du combustible - Google Patents
Procede pour recuperer les actinides des solutions de residus resultant du traitement de recyclage du combustibleInfo
- Publication number
- FR2413762A1 FR2413762A1 FR7836534A FR7836534A FR2413762A1 FR 2413762 A1 FR2413762 A1 FR 2413762A1 FR 7836534 A FR7836534 A FR 7836534A FR 7836534 A FR7836534 A FR 7836534A FR 2413762 A1 FR2413762 A1 FR 2413762A1
- Authority
- FR
- France
- Prior art keywords
- actinides
- recycling treatment
- solution
- solutions resulting
- separation
- 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.)
- Withdrawn
Links
Classifications
-
- 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
-
- C—CHEMISTRY; METALLURGY
- C01—INORGANIC CHEMISTRY
- C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
- C01G43/00—Compounds of uranium
- C01G43/003—Preparation involving a liquid-liquid extraction, an adsorption or an ion-exchange
-
- C—CHEMISTRY; METALLURGY
- C01—INORGANIC CHEMISTRY
- C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
- C01G56/00—Compounds of transuranic elements
- C01G56/001—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
- C22B3/32—Carboxylic acids
-
- 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
- C22B3/32—Carboxylic acids
- C22B3/322—Oxalic acids
-
- 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
- C22B3/38—Treatment or purification of solutions, e.g. obtained by leaching by liquid-liquid extraction using organic compounds containing phosphorus
- C22B3/384—Pentavalent phosphorus oxyacids, esters thereof
- C22B3/3846—Phosphoric acid, e.g. (O)P(OH)3
-
- 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
- C22B60/00—Obtaining metals of atomic number 87 or higher, i.e. radioactive metals
- C22B60/02—Obtaining thorium, uranium, or other actinides
- C22B60/0204—Obtaining thorium, uranium, or other actinides obtaining uranium
- C22B60/0217—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes
- C22B60/0252—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes treatment or purification of solutions or of liquors or of slurries
- C22B60/026—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes treatment or purification of solutions or of liquors or of slurries liquid-liquid extraction with or without dissolution in organic solvents
-
- 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
-
- 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
Landscapes
- Chemical & Material Sciences (AREA)
- Engineering & Computer Science (AREA)
- Organic Chemistry (AREA)
- Life Sciences & Earth Sciences (AREA)
- General Life Sciences & Earth Sciences (AREA)
- Geology (AREA)
- Mechanical Engineering (AREA)
- Materials Engineering (AREA)
- Environmental & Geological Engineering (AREA)
- Manufacturing & Machinery (AREA)
- Metallurgy (AREA)
- Geochemistry & Mineralogy (AREA)
- Physics & Mathematics (AREA)
- High Energy & Nuclear Physics (AREA)
- General Engineering & Computer Science (AREA)
- Inorganic Chemistry (AREA)
- Plasma & Fusion (AREA)
- Extraction Or Liquid Replacement (AREA)
- Manufacture And Refinement Of Metals (AREA)
- Inorganic Compounds Of Heavy Metals (AREA)
Abstract
LE PROCEDE SELON L'INVENTION CONSISTE A AJOUTER DU NITRATE D'HYDROXYLAMMONIUM ET DE L'HYDRAZINE A LA SOLUTION DE RESIDUS POUR AJUSTER A 4 LA VALENCE DU NEPTUNIUM ET DU PLUTONIUM POUR FORMER UNE SOLUTION D'ALIMENTATION ET A METTRE CETTE SOLUTION EN CONTACT AVEC UN AGENT D'EXTRACTION EN ACIDE DIHEXOXYETHYLPHOSPHORIQUE DANS UN DILUANT ORGANIQUE POUR FAIRE PASSER LES ACTINIDES ET LA PLUS GRANDE PARTIE DES TERRES RARES ET DES PRODUITS DE FISSION DANS L'AGENT D'EXTRACTION. LA SEPARATION EST COMPLETEE PAR CONTACT DE L'AGENT D'EXTRACTION CHARGE AVEC DEUX SOLUTIONS AQUEUSES DE SEPARATION L'UNE A L'ACIDE NITRIQUE POUR L'AMERICIUM, LE CURIUM, LES TERRES RARES, ET L'AUTRE A OXALATE POUR LA SEPARATION SELECTIVE DU NEPTUNIUM, DU PLUTONIUM ET DES PRODUITS DE FISSION.
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
US05/865,346 US4162230A (en) | 1977-12-28 | 1977-12-28 | Method for the recovery of actinide elements from nuclear reactor waste |
Publications (1)
Publication Number | Publication Date |
---|---|
FR2413762A1 true FR2413762A1 (fr) | 1979-07-27 |
Family
ID=25345302
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
FR7836534A Withdrawn FR2413762A1 (fr) | 1977-12-28 | 1978-12-27 | Procede pour recuperer les actinides des solutions de residus resultant du traitement de recyclage du combustible |
Country Status (8)
Country | Link |
---|---|
US (1) | US4162230A (fr) |
JP (1) | JPS5496411A (fr) |
BE (1) | BE872881A (fr) |
CA (1) | CA1097925A (fr) |
DE (1) | DE2856489A1 (fr) |
FR (1) | FR2413762A1 (fr) |
GB (1) | GB2011697B (fr) |
IT (1) | IT1101597B (fr) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR2434785A1 (fr) * | 1978-07-25 | 1980-03-28 | Us Energy | Procede pour recuperer des actinides contenus dans des solutions residuaires de carbonate |
Families Citing this family (33)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4332776A (en) * | 1979-11-08 | 1982-06-01 | Wyoming Mineral Corporation | Extractant solvent restoration in the process for recovery of uranium from phosphoric acid |
US4358426A (en) * | 1980-12-17 | 1982-11-09 | The United States Of America As Represented By The United States Department Of Energy | Method for cleaning solution used in nuclear fuel reprocessing |
US4490336A (en) * | 1981-05-27 | 1984-12-25 | Prodeco, Inc. | Process for stripping uranium from an alkyl pyrophosphoric acid |
FR2509282A1 (fr) * | 1981-07-09 | 1983-01-14 | Commissariat Energie Atomique | Procede de separation des actinides et des lanthanides presents a l'etat trivalent, dans une solution aqueuse acide |
LU84016A1 (de) * | 1982-03-15 | 1982-07-08 | Euratom | Verfahren zur rueckgewinnung von plutonium aus salpetersauren waessrigen loesungen |
DE3243841C2 (de) * | 1982-11-26 | 1986-02-06 | Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe | Verfahren zur Denitrierung von salpetersauren, Aktiniden enthaltenden Abfall-Lösungen unter gleichzeitiger Abtrennung der Aktiniden |
DE3332954A1 (de) * | 1983-09-13 | 1985-03-28 | Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe | Verfahren zur abtrennung von neptunium aus einer organischen phase bei der wiederaufarbeitung bestrahlter kernbrenn- und/oder brutstoffe |
GB8403724D0 (en) * | 1984-02-13 | 1984-03-14 | British Nuclear Fuels Plc | Treating nuclear fuel |
US4528165A (en) * | 1984-06-13 | 1985-07-09 | The United States Of America As Represented By The United States Department Of Energy | Separation of uranium from technetium in recovery of spent nuclear fuel |
JPS6130799A (ja) * | 1984-07-24 | 1986-02-13 | 日本原子力研究所 | ネプツニウムの分離方法 |
FR2583989B1 (fr) * | 1985-06-26 | 1987-07-31 | Commissariat Energie Atomique | Procede pour eviter l'extraction du technetium et/ou du rhenium notamment lors de l'extraction de l'uranium et/ou du plutonium, par un solvant organique |
FR2596383B1 (fr) * | 1986-03-28 | 1990-10-26 | Cogema | Procede de separation du fer a partir d'une solution organique contenant de l'uranium |
EP0251399A1 (fr) * | 1986-06-23 | 1988-01-07 | "Centre d'Etude de l'Energie Nucléaire", "C.E.N." | Procédé de séparation ou de récupération de plutonium et plutonium ainsi obtenu |
JPS6360108A (ja) * | 1986-08-29 | 1988-03-16 | Sumitomo Metal Mining Co Ltd | ガドリニウムの分離回収方法 |
US4835107A (en) * | 1986-10-21 | 1989-05-30 | Arch Development Corp. | Method for the concentration and separation of actinides from biological and environmental samples |
DE3809042A1 (de) * | 1988-03-18 | 1989-09-28 | Wiederaufarbeitung Von Kernbre | Verfahren und vorrichtung zum abtrennen von uran, plutonium sowie spaltprodukten |
US5135728A (en) * | 1992-01-03 | 1992-08-04 | Karraker David G | Method for dissolving delta-phase plutonium |
US5435942A (en) * | 1994-02-28 | 1995-07-25 | United States Department Of Energy | Process for treating alkaline wastes for vitrification |
FR2720853B1 (fr) * | 1994-06-03 | 1996-07-05 | Commissariat Energie Atomique | Procédé de régénération d'un solvant organique dégradé, utilisé pour le retraitement de combustibles nucléaires usés. |
FR2739216B1 (fr) * | 1995-09-22 | 1997-10-24 | Commissariat Energie Atomique | Procede de traitement de combustibles et/ou de cibles nucleaires a base d'aluminium metallique par des solutions d'hydroxyde de tetramethylammonium |
US6312654B1 (en) * | 1997-07-29 | 2001-11-06 | Forschungszentrum Julich Gmbh | Method of separating a trivalent actinide from a trivalent lanthanide and/or yttrium in aqueous solution |
FR2779974B1 (fr) | 1998-06-19 | 2000-07-13 | Commissariat Energie Atomique | Procede de dissolution du plutonium ou d'un alliage de plutonium |
US6973154B2 (en) * | 1998-09-29 | 2005-12-06 | Hitachi, Ltd. | Method of chemical decontamination and system therefor |
FR2822287B1 (fr) * | 2001-03-13 | 2003-12-12 | Commissariat Energie Atomique | Procede de decontamination de filtres solides a iode |
JP5193687B2 (ja) * | 2008-05-30 | 2013-05-08 | 株式会社東芝 | 使用済み燃料再処理方法 |
US7854907B2 (en) * | 2008-11-19 | 2010-12-21 | The Board of Regents of the Nevada System of Higher Education of the University of Nevada, Las Vegas | Process for the extraction of technetium from uranium |
US9283418B2 (en) | 2010-10-15 | 2016-03-15 | Avantech, Inc. | Concentrate treatment system |
US8753518B2 (en) * | 2010-10-15 | 2014-06-17 | Diversified Technologies Services, Inc. | Concentrate treatment system |
US10580542B2 (en) | 2010-10-15 | 2020-03-03 | Avantech, Inc. | Concentrate treatment system |
KR101386704B1 (ko) | 2013-02-04 | 2014-04-18 | 한국과학기술연구원 | 용매추출공정을 이용한 지르코늄과 하프늄의 분리방법 |
US10297355B1 (en) * | 2016-12-14 | 2019-05-21 | U.S. Department Of Energy | Reduction-oxidation of actinides extraction process (ROANEX) for used nuclear fuel recycling |
CN111876598B (zh) * | 2019-12-10 | 2022-03-22 | 核工业北京化工冶金研究院 | 一种共萃取分离铀铌的方法 |
CN112853128B (zh) * | 2020-12-30 | 2022-07-01 | 中国原子能科学研究院 | 连续调节Purex流程1CU料液中镎价态和酸度的方法和装置 |
Citations (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR1404016A (fr) * | 1964-07-08 | 1965-06-25 | Atomic Energy Authority Uk | Perfectionnements au traitement des combustibles nucléaires irradiés |
US3326811A (en) * | 1963-07-12 | 1967-06-20 | Atomic Energy Authority Uk | Processing of irradiated nuclear fuels |
US3463619A (en) * | 1968-07-12 | 1969-08-26 | Atomic Energy Commission | Solvent extraction process for purifying americium and curium |
US3595629A (en) * | 1969-08-14 | 1971-07-27 | Atomic Energy Commission | Plutonium and neptunium extraction process |
US3745205A (en) * | 1972-02-17 | 1973-07-10 | Atomic Energy Commission | Extraction of uranium from an aqueous solution |
Family Cites Families (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CA576900A (fr) * | 1959-06-02 | M. Aikin Archibald | Extraction de solvant de solutions de nitrate d'uranium irradie de neutrons | |
FR1568325A (fr) * | 1968-03-29 | 1969-05-23 | ||
FR2212610B1 (fr) * | 1972-12-28 | 1977-08-05 | Commissariat Energie Atomique | |
US4011296A (en) * | 1975-05-27 | 1977-03-08 | General Electric Company | Irradiated fuel reprocessing |
-
1977
- 1977-12-28 US US05/865,346 patent/US4162230A/en not_active Expired - Lifetime
-
1978
- 1978-11-17 GB GB7845139A patent/GB2011697B/en not_active Expired
- 1978-12-19 BE BE192411A patent/BE872881A/fr unknown
- 1978-12-21 CA CA318,798A patent/CA1097925A/fr not_active Expired
- 1978-12-26 JP JP16451778A patent/JPS5496411A/ja active Pending
- 1978-12-27 IT IT3134078A patent/IT1101597B/it active
- 1978-12-27 FR FR7836534A patent/FR2413762A1/fr not_active Withdrawn
- 1978-12-28 DE DE19782856489 patent/DE2856489A1/de not_active Withdrawn
Patent Citations (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3326811A (en) * | 1963-07-12 | 1967-06-20 | Atomic Energy Authority Uk | Processing of irradiated nuclear fuels |
FR1404016A (fr) * | 1964-07-08 | 1965-06-25 | Atomic Energy Authority Uk | Perfectionnements au traitement des combustibles nucléaires irradiés |
US3463619A (en) * | 1968-07-12 | 1969-08-26 | Atomic Energy Commission | Solvent extraction process for purifying americium and curium |
US3595629A (en) * | 1969-08-14 | 1971-07-27 | Atomic Energy Commission | Plutonium and neptunium extraction process |
US3745205A (en) * | 1972-02-17 | 1973-07-10 | Atomic Energy Commission | Extraction of uranium from an aqueous solution |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR2434785A1 (fr) * | 1978-07-25 | 1980-03-28 | Us Energy | Procede pour recuperer des actinides contenus dans des solutions residuaires de carbonate |
Also Published As
Publication number | Publication date |
---|---|
IT1101597B (it) | 1985-10-07 |
BE872881A (fr) | 1979-04-17 |
US4162230A (en) | 1979-07-24 |
IT7831340A0 (it) | 1978-12-27 |
GB2011697B (en) | 1982-05-06 |
JPS5496411A (en) | 1979-07-30 |
GB2011697A (en) | 1979-07-11 |
CA1097925A (fr) | 1981-03-24 |
DE2856489A1 (de) | 1979-07-05 |
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Legal Events
Date | Code | Title | Description |
---|---|---|---|
ST | Notification of lapse | ||
RC | Opposition against decision of lapse | ||
DA | Annulment of decision of lapse | ||
ST | Notification of lapse |