FR2405541A2 - Procede d'extraction de produits de fission contenus dans des elements combustibles nucleaires irradies - Google Patents

Procede d'extraction de produits de fission contenus dans des elements combustibles nucleaires irradies

Info

Publication number
FR2405541A2
FR2405541A2 FR7730371A FR7730371A FR2405541A2 FR 2405541 A2 FR2405541 A2 FR 2405541A2 FR 7730371 A FR7730371 A FR 7730371A FR 7730371 A FR7730371 A FR 7730371A FR 2405541 A2 FR2405541 A2 FR 2405541A2
Authority
FR
France
Prior art keywords
fission products
nuclear fuel
irradied
fuel elements
products contained
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
FR7730371A
Other languages
English (en)
Other versions
FR2405541B2 (fr
Inventor
Maurice Anav
Andre Chesne
Andre Leseur
Pierre Miquel
Roger Pascard
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
Priority claimed from FR7639569A external-priority patent/FR2376499A1/fr
Application filed by Commissariat a lEnergie Atomique CEA filed Critical Commissariat a lEnergie Atomique CEA
Priority to FR7730371A priority Critical patent/FR2405541A2/fr
Priority to GB5189077A priority patent/GB1552205A/en
Priority to US05/860,452 priority patent/US4180476A/en
Priority to JP16093977A priority patent/JPS5390598A/ja
Priority to DE19772758408 priority patent/DE2758408A1/de
Publication of FR2405541A2 publication Critical patent/FR2405541A2/fr
Application granted granted Critical
Publication of FR2405541B2 publication Critical patent/FR2405541B2/fr
Granted legal-status Critical Current

Links

Classifications

    • 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
    • C22B26/00—Obtaining alkali, alkaline earth metals or magnesium
    • C22B26/10—Obtaining alkali metals
    • 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
    • G21F9/04—Treating liquids
    • G21F9/06—Processing
    • G21F9/08—Processing by evaporation; by distillation
    • 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
    • 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
    • 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

Abstract

L'invention a pour objet un procédé d'extraction de produits de fission contenus dans des éléments combustibles nucléaires irradiés avant dissolution par voie humide du combustible. Ce procédé consiste à mettre en contact lesdits éléments avec de l'eau après les avoir traités mécaniquement pour les dégainer et/ou les tronçonner, à séparer ensuite lesdits éléments traités de la solution aqueuse obtenue et à récupérer au moins l'un desdits produits de fission à partir de ladite solution, et il se caractérise en ce qu'on récupère certains desdits produits de fission à partir de ladite solution aqueuse en concentrant ladite solution aqueuse par distillation pour obtenir un concentrat contenant lesdits produits de fission et en ce qu'on traite ledit concentrat afin d'assurer un stockage à long terme desdits produits de fission. Application à la récupération de l'iode, du césium et du rubidium.
FR7730371A 1976-12-30 1977-10-10 Procede d'extraction de produits de fission contenus dans des elements combustibles nucleaires irradies Granted FR2405541A2 (fr)

Priority Applications (5)

Application Number Priority Date Filing Date Title
FR7730371A FR2405541A2 (fr) 1976-12-30 1977-10-10 Procede d'extraction de produits de fission contenus dans des elements combustibles nucleaires irradies
GB5189077A GB1552205A (en) 1976-12-30 1977-12-13 Extraction of fission products
US05/860,452 US4180476A (en) 1976-12-30 1977-12-14 Process for the extraction of fission products
JP16093977A JPS5390598A (en) 1976-12-30 1977-12-28 Method of extracting nuclear fission product
DE19772758408 DE2758408A1 (de) 1976-12-30 1977-12-28 Verfahren zur abtrennung von spaltprodukten

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
FR7639569A FR2376499A1 (fr) 1976-12-30 1976-12-30 Procede d'extraction de produits de fission contenus dans des elements combustibles nucleaires irradies
FR7730371A FR2405541A2 (fr) 1976-12-30 1977-10-10 Procede d'extraction de produits de fission contenus dans des elements combustibles nucleaires irradies

Publications (2)

Publication Number Publication Date
FR2405541A2 true FR2405541A2 (fr) 1979-05-04
FR2405541B2 FR2405541B2 (fr) 1981-06-26

Family

ID=26219774

Family Applications (1)

Application Number Title Priority Date Filing Date
FR7730371A Granted FR2405541A2 (fr) 1976-12-30 1977-10-10 Procede d'extraction de produits de fission contenus dans des elements combustibles nucleaires irradies

Country Status (5)

Country Link
US (1) US4180476A (fr)
JP (1) JPS5390598A (fr)
DE (1) DE2758408A1 (fr)
FR (1) FR2405541A2 (fr)
GB (1) GB1552205A (fr)

Families Citing this family (10)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2277415A1 (fr) * 1974-07-03 1976-01-30 Commissariat Energie Atomique Procede d'extraction, de piegeage et de stockage de l'iode radioactif contenu dans les combustibles nucleaires irradies
US4582637A (en) * 1980-03-28 1986-04-15 British Nuclear Fuels Ltd. Reprocessing of irradiated nuclear fuel
DE3103900C2 (de) * 1981-02-05 1984-02-02 Kernforschungsanlage Jülich GmbH, 5170 Jülich Anlage zum Aufbereiten graphitischer Brennelemente von Hochtemperatur-Kernreaktoren
US4673547A (en) * 1982-05-24 1987-06-16 Kernforschungsanlage Julich Gesellschaft Mit Beschrankter Haftung Process for separation of hydrogen and/or deuterium and tritium from an inert gas flow and apparatus for effectuation of process in the cooling gas circuit of a gas-cooled nuclear reactor
US4595529A (en) * 1984-03-13 1986-06-17 The United States Of America As Represented By The Department Of Energy Solvent wash solution
FR2681139B1 (fr) * 1991-09-10 1993-11-05 Matieres Nucleaires Cie Gle Installation pour effectuer plusieurs reactions chimiques successives dans un meme recipient.
ATE557400T1 (de) * 2008-02-05 2012-05-15 Univ Missouri Herstellung von radioisotopen und behandlung einer zielmateriallösung
WO2014071966A1 (fr) 2012-11-12 2014-05-15 Christian-Albrechts-Universität Zu Kiel Titanates stratifiés d'amines insaturées
KR101558920B1 (ko) * 2013-09-13 2015-10-08 한국원자력연구원 요오드 핵종을 함유하는 방사성 폐수의 생물학적 정화 장치
KR101490355B1 (ko) * 2014-01-09 2015-02-05 한국원자력연구원 방사성 폐수 내 고농도 요오드의 무기광물화 제거방법 및 제거장치

Family Cites Families (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3282655A (en) * 1966-11-01 Production of
GB987014A (en) * 1962-07-04 1965-03-24 Yarrow & Company Ltd Improvements in and relating to nuclear reactor installations
US3365578A (en) * 1962-08-10 1968-01-23 Atomic Energy Authority Uk Glass composition comprising radioactive waste oxide material contained within a steel vessel
US3298961A (en) * 1965-08-26 1967-01-17 George D Davis Concentration and containment of radioactivity from radioactive waste solutions in asphalt
UST939005I4 (en) 1974-03-20 1975-10-07 Forced circulation

Also Published As

Publication number Publication date
US4180476A (en) 1979-12-25
JPS5390598A (en) 1978-08-09
DE2758408A1 (de) 1978-07-06
FR2405541B2 (fr) 1981-06-26
GB1552205A (en) 1979-09-12

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