GB1540274A - Apparatus for the reprocessing of irradiated nuclear fuels and/or breeder materials - Google Patents

Apparatus for the reprocessing of irradiated nuclear fuels and/or breeder materials

Info

Publication number
GB1540274A
GB1540274A GB1919776A GB1919776A GB1540274A GB 1540274 A GB1540274 A GB 1540274A GB 1919776 A GB1919776 A GB 1919776A GB 1919776 A GB1919776 A GB 1919776A GB 1540274 A GB1540274 A GB 1540274A
Authority
GB
United Kingdom
Prior art keywords
reprocessing
nuclear fuels
irradiated nuclear
breeder materials
breeder
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
GB1919776A
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.)
Forschungszentrum Karlsruhe GmbH
GEA Group AG
Original Assignee
Kernforschungszentrum Karlsruhe GmbH
Metallgesellschaft AG
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 DE2520870A external-priority patent/DE2520870C3/en
Priority claimed from DE2520940A external-priority patent/DE2520940C2/en
Priority claimed from DE2520869A external-priority patent/DE2520869C2/en
Application filed by Kernforschungszentrum Karlsruhe GmbH, Metallgesellschaft AG filed Critical Kernforschungszentrum Karlsruhe GmbH
Publication of GB1540274A publication Critical patent/GB1540274A/en
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
    • C—CHEMISTRY; METALLURGY
    • C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22C—ALLOYS
    • C22C27/00—Alloys based on rhenium or a refractory metal not mentioned in groups C22C14/00 or C22C16/00
    • 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)
  • Chemical & Material Sciences (AREA)
  • Physics & Mathematics (AREA)
  • Materials Engineering (AREA)
  • Mechanical Engineering (AREA)
  • Metallurgy (AREA)
  • Organic Chemistry (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Electrolytic Production Of Metals (AREA)
  • Other Surface Treatments For Metallic Materials (AREA)
GB1919776A 1975-05-10 1976-05-10 Apparatus for the reprocessing of irradiated nuclear fuels and/or breeder materials Expired GB1540274A (en)

Applications Claiming Priority (3)

Application Number Priority Date Filing Date Title
DE2520870A DE2520870C3 (en) 1975-05-10 1975-05-10 Hafnium or hafnium alloys as a material or composite material in devices for the reprocessing of irradiated uranium and plutonium or thorium containing nuclear fuels and / or breeding materials
DE2520940A DE2520940C2 (en) 1975-05-10 1975-05-10 Device for the continuous, extractive separation of connections by means of electrolytic reduction
DE2520869A DE2520869C2 (en) 1975-05-10 1975-05-10 Countercurrent extraction column for liquid-liquid extraction of two mutually insoluble phases with simultaneous electrolysis

Publications (1)

Publication Number Publication Date
GB1540274A true GB1540274A (en) 1979-02-07

Family

ID=27186374

Family Applications (1)

Application Number Title Priority Date Filing Date
GB1919776A Expired GB1540274A (en) 1975-05-10 1976-05-10 Apparatus for the reprocessing of irradiated nuclear fuels and/or breeder materials

Country Status (4)

Country Link
CA (1) CA1070143A (en)
FR (1) FR2311389A1 (en)
GB (1) GB1540274A (en)
SE (1) SE420450B (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP1037214A1 (en) * 1999-03-16 2000-09-20 Hitachi, Ltd. A hafnium alloy having high corrosion resistance, neutron absorber for reactor control rods made of same, reactor control rod, reactor and nuclear power generation plant
WO2008102209A2 (en) * 2006-08-21 2008-08-28 H.C. Starck Ltd Refracrory metal tool for friction stir welding comprising a shoulder made of tungsten, molybdenum, tantalum, niobium or hafnium alloy and a coated or treated surface
CN110729063A (en) * 2019-09-23 2020-01-24 中国核电工程有限公司 Critical safety control method for mixing and clarifying tank in nuclear fuel post-treatment

Families Citing this family (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE2715367A1 (en) * 1977-04-06 1978-10-12 Kernforschungsz Karlsruhe REMOVER FOR RELEASING NUCLEAR FUEL FROM FUEL ELEMENT SECTIONS
GB2007010A (en) * 1977-10-03 1979-05-10 British Nuclear Fuels Ltd Solvent extraction columns
DE2923870C2 (en) * 1979-06-13 1982-10-28 Nukem Gmbh, 6450 Hanau Extraction column for cleaning of fissile and / or breeding material

Family Cites Families (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR1497313A (en) * 1965-10-21 1967-10-06 Westinghouse Electric Corp Hafnium alloy
GB1095925A (en) * 1965-12-02 1967-12-20 Imp Metal Ind Kynoch Ltd Hafnium alloys
GB1095807A (en) * 1965-12-02 1967-12-20 Imp Metal Ind Kynoch Ltd Hafnium alloys
US3622309A (en) * 1968-10-21 1971-11-23 Iit Res Inst Hafnium base alloy (boron)
US3622308A (en) * 1968-10-21 1971-11-23 Iit Res Inst Hafnium base alloy (iridium)
FR2074709A1 (en) * 1970-01-20 1971-10-08 Ugine Kuhlmann Hafnium alloy - of good high temp oxidn resistance

Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP1037214A1 (en) * 1999-03-16 2000-09-20 Hitachi, Ltd. A hafnium alloy having high corrosion resistance, neutron absorber for reactor control rods made of same, reactor control rod, reactor and nuclear power generation plant
WO2008102209A2 (en) * 2006-08-21 2008-08-28 H.C. Starck Ltd Refracrory metal tool for friction stir welding comprising a shoulder made of tungsten, molybdenum, tantalum, niobium or hafnium alloy and a coated or treated surface
WO2008102209A3 (en) * 2006-08-21 2009-07-30 H C Starck Ltd Refracrory metal tool for friction stir welding comprising a shoulder made of tungsten, molybdenum, tantalum, niobium or hafnium alloy and a coated or treated surface
CN110729063A (en) * 2019-09-23 2020-01-24 中国核电工程有限公司 Critical safety control method for mixing and clarifying tank in nuclear fuel post-treatment
CN110729063B (en) * 2019-09-23 2022-11-15 中国核电工程有限公司 Critical safety control method for mixing and clarifying tank in nuclear fuel post-treatment

Also Published As

Publication number Publication date
FR2311389A1 (en) 1976-12-10
SE7605234L (en) 1976-11-11
SE420450B (en) 1981-10-05
CA1070143A (en) 1980-01-22
FR2311389B1 (en) 1980-04-25

Similar Documents

Publication Publication Date Title
ZA7621B (en) Apparatus and installation for examining the fuel rods of a nuclear reactor
JPS51114594A (en) Method and device for inspecting extension of nuclear reactor
JPS51130093A (en) Injector radiation shielding device and radioactive serum inspecting method
CA928434A (en) Method and apparatus for the non-destructive assay of bulk nuclear reactor fuel using 1 kev to 1 mev range neutrons
IT1083984B (en) APPARATUS FOR INGLOBING RADIOACTIVE AND TOXIC WASTE
IL49396A0 (en) Nuclear reactor fuel element and fitting
JPS5261700A (en) Irradiated nuclear fuel storage shield and method of producing same
GB1546863A (en) Apparatus for measuring the nuclear radiation of a sequence of radioactive samples and magazine for use therein
GB1554576A (en) Nuclear reactor
IT7827570A0 (en) APPARATUS AND PROCEDURE FOR STORAGE OF NUCLEAR FUEL.
DE3061029D1 (en) Method and apparatus for the control of fuel rods used in nuclear reactor assemblies
GB2025686B (en) Waste disposalprocess and apparatus for nuclear fission product solutions
JPS51140100A (en) Method of solidifyinf liquid radioactive waste
JPS5246298A (en) Method and device for purifying reactor facility adhered with radioactive sodium
GB1554191A (en) Nuclear reactors
IT1128436B (en) PROCEDURE FOR THE DISSOLUTION OF NUCLEAR FUELS CONTAINING PLUTONIUM
GB2045511B (en) Electrochemical reprocessing of nuclear fuels
GB1540274A (en) Apparatus for the reprocessing of irradiated nuclear fuels and/or breeder materials
JPS51121692A (en) Method of introducing decay heat of radioactive nuclear fission products
GB1554898A (en) Nuclear reactor
JPS5338896A (en) Irradited nuclear fuel dry reprocessing method and device
ES488292A0 (en) APPARATUS FOR DETERMINING THE APPARENT DENSITY OF RADIOACTIVE NUCLEAR FUEL PARTICLES
GB2010572B (en) Method and apparatus for storing radioactive materials
JPS56128477A (en) Method of and apparatus for measuring radioactive radiation
GB1550978A (en) And others methods and apparatus for refuelling nuclear reactors

Legal Events

Date Code Title Description
PS Patent sealed
PCNP Patent ceased through non-payment of renewal fee