CA1269251A - Separation des produits de fission, absorbeurs de neutrons, contenus dans les combustibles a base d'uranium - Google Patents

Separation des produits de fission, absorbeurs de neutrons, contenus dans les combustibles a base d'uranium

Info

Publication number
CA1269251A
CA1269251A CA000492652A CA492652A CA1269251A CA 1269251 A CA1269251 A CA 1269251A CA 000492652 A CA000492652 A CA 000492652A CA 492652 A CA492652 A CA 492652A CA 1269251 A CA1269251 A CA 1269251A
Authority
CA
Canada
Prior art keywords
fuel
uranium
fission products
acid
neutron
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 - Lifetime
Application number
CA000492652A
Other languages
English (en)
Other versions
CA1269251C (fr
Inventor
Bradley J.F. Palmer
Christopher H. Knight
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.)
Canada, Represented By Minister Of Atomic Energy Of Canada AS
Original Assignee
Canada, Represented By Minister Of Atomic Energy Of Canada AS
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 Canada, Represented By Minister Of Atomic Energy Of Canada AS filed Critical Canada, Represented By Minister Of Atomic Energy Of Canada AS
Priority to CA492652A priority Critical patent/CA1269251C/fr
Application granted granted Critical
Publication of CA1269251A publication Critical patent/CA1269251A/fr
Publication of CA1269251C publication Critical patent/CA1269251C/fr
Expired 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
    • 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

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Inorganic Compounds Of Heavy Metals (AREA)
  • Solid Fuels And Fuel-Associated Substances (AREA)
CA492652A 1985-10-09 1985-10-09 Separation des produits de fission, absorbeurs de neutrons, contenus dans les combustibles a base d'uranium Expired CA1269251C (fr)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CA492652A CA1269251C (fr) 1985-10-09 1985-10-09 Separation des produits de fission, absorbeurs de neutrons, contenus dans les combustibles a base d'uranium

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CA492652A CA1269251C (fr) 1985-10-09 1985-10-09 Separation des produits de fission, absorbeurs de neutrons, contenus dans les combustibles a base d'uranium

Publications (2)

Publication Number Publication Date
CA1269251A true CA1269251A (fr) 1990-05-22
CA1269251C CA1269251C (fr) 1990-05-22

Family

ID=4131585

Family Applications (1)

Application Number Title Priority Date Filing Date
CA492652A Expired CA1269251C (fr) 1985-10-09 1985-10-09 Separation des produits de fission, absorbeurs de neutrons, contenus dans les combustibles a base d'uranium

Country Status (1)

Country Link
CA (1) CA1269251C (fr)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN109478436A (zh) * 2016-06-23 2019-03-15 欧安诺循环 用于溶解核燃料的方法

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN109478436A (zh) * 2016-06-23 2019-03-15 欧安诺循环 用于溶解核燃料的方法

Also Published As

Publication number Publication date
CA1269251C (fr) 1990-05-22

Similar Documents

Publication Publication Date Title
Olander Nuclear fuels–present and future
Simnad Nuclear reactor materials and fuels
Ohta et al. Pyroprocessing of light water reactor spent fuels based on an electrochemical reduction technology
JPS6351517B2 (fr)
CA1269251A (fr) Separation des produits de fission, absorbeurs de neutrons, contenus dans les combustibles a base d'uranium
Häkkinen Impurities in LWR fuel and structural materials
Piet et al. HTGR Technology Family Assessment for a Range of Fuel Cycle Missions
Baetslé et al. Status and assessment report on actinide and fission product partitioning and transmutation
MacLean et al. Irradiaton of Metallic and Oxide Fuels for Actinide Transmutation in the ATR
Johnson et al. Light water reactor fuel reprocessing: dissolution studies of voloxidized fuel
Hyland et al. Transmutation of americium and curium in a lanthanide matrix
WO2001033575A2 (fr) Procede de recyclage de combustible irradie
Goode et al. ORNL experiments on behavior of tritium during head-end processing of irradiated reactor fuels
Gué et al. French experience in MOX fuel dissolution
Goode et al. Comparative studies of head-end processing using irradiated, mechanically blended and coprecipitated (U, Pu) O/sub 2/reactor fuels
Rodrigues Reprocessing RERTR fuels
Johnson et al. Light water reactor fuel reprocessing: dissolution studies of voloxidized and nonvoloxidized fuel
Chang Neutronic and burnup characteristics of an actinide-reduced plutonium fuel with tungsten
Asmussen et al. Low-enrichment and denatured (thorium) fuels for the HTGR: a status report
Ferguson et al. FAST REACTOR FUEL PROCESSING.
Wymer Reprocessing of Nuclear Fuel: Overview/critique of Worldwide Experience and Engineering/technology Challenges for Separations
McKay Elimination of waste actinides by reveling them to nuclear reactors
Park et al. Establish objectives for advanced voloxidation with respect to the downstream effects
Biswas et al. Potential utilization of SRS uranium with high {sup 236} U content as commercial LWR fuel
Oversby Spent fuel characteristics & disposal considerations

Legal Events

Date Code Title Description
MKLA Lapsed
MKLA Lapsed

Effective date: 20060523