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WO2001033575A3 - Procede de recyclage de combustible irradie - Google Patents

Procede de recyclage de combustible irradie Download PDF

Info

Publication number
WO2001033575A3
WO2001033575A3 PCT/CA2000/001263 CA0001263W WO0133575A3 WO 2001033575 A3 WO2001033575 A3 WO 2001033575A3 CA 0001263 W CA0001263 W CA 0001263W WO 0133575 A3 WO0133575 A3 WO 0133575A3
Authority
WO
WIPO (PCT)
Prior art keywords
fuel
fertile
fissile
fission products
irradiated 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.)
Ceased
Application number
PCT/CA2000/001263
Other languages
English (en)
Other versions
WO2001033575A2 (fr
Inventor
James D Sullivan
Holly B Hamilton
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
Priority to AU11215/01A priority Critical patent/AU1121501A/en
Publication of WO2001033575A2 publication Critical patent/WO2001033575A2/fr
Publication of WO2001033575A3 publication Critical patent/WO2001033575A3/fr
Anticipated expiration legal-status Critical
Ceased legal-status Critical Current

Links

Classifications

    • 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
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/42—Selection of substances for use as reactor fuel
    • G21C3/58—Solid reactor fuel Pellets made of fissile material
    • G21C3/62—Ceramic fuel
    • G21C3/623—Oxide fuels
    • 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

Landscapes

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Chemical & Material Sciences (AREA)
  • Ceramic Engineering (AREA)
  • Physical Or Chemical Processes And Apparatus (AREA)
  • Manufacture And Refinement Of Metals (AREA)

Abstract

La présente invention concerne un procédé simple destiné à recycler du combustible irradié et permettant d'en empêcher la prolifération. La matrice complète de combustible irradié est dissoute dans un acide fort et les éléments fissiles et fertiles recherchés ainsi qu'une partie des produits de fission hautement radioactifs sont précipités par élévation du pH. En choisissant convenablement la valeur du pH, les éléments de terres rares qui absorbent les neutrons restent en solution et ne précipitent pas avec les éléments fissiles/fertiles et les produits de fission hautement radioactifs. La présence d'une partie importante des produits de fission dans le mélange fertile/fissile le rend très radioactif et donc inaccessible sans l'utilisation d'écrans de protection ou d'équipement spécialisé de manutention. Le combustible irradié à partir duquel le combustible anti-prolifération de la présente invention peut être recyclé est, de préférence, issu d'un réacteur à eau légère (LWR) ou d'un réacteur utilisant du thorium comme combustible fertile. Le combustible recyclé anti-prolifération selon la présente invention est de préférence repris pour être utilisé dans un réacteur de type CANDU®.
PCT/CA2000/001263 1999-10-29 2000-10-26 Procede de recyclage de combustible irradie Ceased WO2001033575A2 (fr)

Priority Applications (1)

Application Number Priority Date Filing Date Title
AU11215/01A AU1121501A (en) 1999-10-29 2000-10-26 Process for recycling irradiated fuel

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
US42992499A 1999-10-29 1999-10-29
US09/429,924 1999-10-29

Publications (2)

Publication Number Publication Date
WO2001033575A2 WO2001033575A2 (fr) 2001-05-10
WO2001033575A3 true WO2001033575A3 (fr) 2001-11-29

Family

ID=23705289

Family Applications (1)

Application Number Title Priority Date Filing Date
PCT/CA2000/001263 Ceased WO2001033575A2 (fr) 1999-10-29 2000-10-26 Procede de recyclage de combustible irradie

Country Status (2)

Country Link
AU (1) AU1121501A (fr)
WO (1) WO2001033575A2 (fr)

Families Citing this family (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
RU2371791C2 (ru) * 2007-11-30 2009-10-27 Российская Федерация в лице Федерального агентства по атомной энергии Способ растворения ядерного топлива в виде измельченных тепловыделяющих сборок атомных реакторов и устройство для его осуществления
FR3053151B1 (fr) * 2016-06-23 2018-08-10 Commissariat A L'energie Atomique Et Aux Energies Alternatives Procede de dissolution d'un combustible nucleaire
RU2691621C1 (ru) * 2017-11-27 2019-06-17 Акционерное общество "Радиевый институт имени В.Г. Хлопина" Топливная композиция для водоохлаждаемых реакторов АЭС на тепловых нейтронах
CN111024800B (zh) * 2019-12-20 2022-06-28 核工业北京地质研究院 一种确认pH值与流体中铀溶解能力关系的方法

Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2074812A1 (en) * 1970-01-30 1971-10-08 Commissariat Energie Atomique Nuclear fuel recovery - fixing fluorine ions during evaporation to avoid corrosion
EP0031067A1 (fr) * 1979-12-20 1981-07-01 Alkem Gmbh Procédé pour dissoudre des combustibles nucléaires difficilement solubles
EP0599509A1 (fr) * 1992-11-16 1994-06-01 Westinghouse Electric Corporation Procédé pour l'extraction du carbonate d'uranium
JPH06294893A (ja) * 1993-04-09 1994-10-21 Ishikawajima Harima Heavy Ind Co Ltd 使用済核燃料の再処理における不溶解残渣の回収方法
JPH0986936A (ja) * 1995-09-28 1997-03-31 Sumitomo Metal Mining Co Ltd テクネチウムの回収方法
WO1999022379A1 (fr) * 1997-10-25 1999-05-06 British Nuclear Fuels Plc Retraitement de combustible nucleaire

Patent Citations (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2074812A1 (en) * 1970-01-30 1971-10-08 Commissariat Energie Atomique Nuclear fuel recovery - fixing fluorine ions during evaporation to avoid corrosion
EP0031067A1 (fr) * 1979-12-20 1981-07-01 Alkem Gmbh Procédé pour dissoudre des combustibles nucléaires difficilement solubles
US4434137A (en) * 1979-12-20 1984-02-28 Alkem Gmbh Method for dissolving hard-to dissolve nuclear fuels
EP0599509A1 (fr) * 1992-11-16 1994-06-01 Westinghouse Electric Corporation Procédé pour l'extraction du carbonate d'uranium
JPH06294893A (ja) * 1993-04-09 1994-10-21 Ishikawajima Harima Heavy Ind Co Ltd 使用済核燃料の再処理における不溶解残渣の回収方法
JPH0986936A (ja) * 1995-09-28 1997-03-31 Sumitomo Metal Mining Co Ltd テクネチウムの回収方法
WO1999022379A1 (fr) * 1997-10-25 1999-05-06 British Nuclear Fuels Plc Retraitement de combustible nucleaire

Non-Patent Citations (2)

* Cited by examiner, † Cited by third party
Title
PATENT ABSTRACTS OF JAPAN vol. 1995, no. 01 28 February 1995 (1995-02-28) *
PATENT ABSTRACTS OF JAPAN vol. 1997, no. 07 31 July 1997 (1997-07-31) *

Also Published As

Publication number Publication date
AU1121501A (en) 2001-05-14
WO2001033575A2 (fr) 2001-05-10

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