GB2113901B - Apparatus and method for reprocessing and separating spent nuclear fuels - Google Patents

Apparatus and method for reprocessing and separating spent nuclear fuels

Info

Publication number
GB2113901B
GB2113901B GB8236505A GB8236505A GB2113901B GB 2113901 B GB2113901 B GB 2113901B GB 8236505 A GB8236505 A GB 8236505A GB 8236505 A GB8236505 A GB 8236505A GB 2113901 B GB2113901 B GB 2113901B
Authority
GB
United Kingdom
Prior art keywords
reprocessing
spent nuclear
nuclear fuels
separating spent
separating
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
GB8236505A
Other versions
GB2113901A (en
Inventor
Oscar Harold Krikorian
John Zolvah Grens
William Hunter Parrish
Melvin Sterling Coops
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.)
US Department of Energy
Original Assignee
US Department of Energy
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 US06/340,591 external-priority patent/US4399108A/en
Application filed by US Department of Energy filed Critical US Department of Energy
Publication of GB2113901A publication Critical patent/GB2113901A/en
Application granted granted Critical
Publication of GB2113901B publication Critical patent/GB2113901B/en
Expired legal-status Critical Current

Links

Classifications

    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01B—NON-METALLIC ELEMENTS; COMPOUNDS THEREOF; METALLOIDS OR COMPOUNDS THEREOF NOT COVERED BY SUBCLASS C01C
    • C01B21/00—Nitrogen; Compounds thereof
    • C01B21/06—Binary compounds of nitrogen with metals, with silicon, or with boron, or with carbon, i.e. nitrides; Compounds of nitrogen with more than one metal, silicon or boron
    • C01B21/0615—Binary compounds of nitrogen with metals, with silicon, or with boron, or with carbon, i.e. nitrides; Compounds of nitrogen with more than one metal, silicon or boron with transition metals other than titanium, zirconium or hafnium
    • C01B21/063—Binary compounds of nitrogen with metals, with silicon, or with boron, or with carbon, i.e. nitrides; Compounds of nitrogen with more than one metal, silicon or boron with transition metals other than titanium, zirconium or hafnium with one or more actinides, e.g. UN, PuN
    • 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
    • G21C19/48—Non-aqueous processes
    • 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

  • Chemical & Material Sciences (AREA)
  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Organic Chemistry (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Crystallography & Structural Chemistry (AREA)
  • Inorganic Chemistry (AREA)
  • Inorganic Compounds Of Heavy Metals (AREA)
  • Manufacture And Refinement Of Metals (AREA)
GB8236505A 1982-01-19 1982-12-22 Apparatus and method for reprocessing and separating spent nuclear fuels Expired GB2113901B (en)

Applications Claiming Priority (3)

Application Number Priority Date Filing Date Title
US34062282A 1982-01-19 1982-01-19
US34062682A 1982-01-19 1982-01-19
US06/340,591 US4399108A (en) 1982-01-19 1982-01-19 Method for reprocessing and separating spent nuclear fuels

Publications (2)

Publication Number Publication Date
GB2113901A GB2113901A (en) 1983-08-10
GB2113901B true GB2113901B (en) 1986-06-11

Family

ID=27407408

Family Applications (1)

Application Number Title Priority Date Filing Date
GB8236505A Expired GB2113901B (en) 1982-01-19 1982-12-22 Apparatus and method for reprocessing and separating spent nuclear fuels

Country Status (4)

Country Link
CA (1) CA1202787A (en)
DE (1) DE3301641A1 (en)
FR (1) FR2520151B1 (en)
GB (1) GB2113901B (en)

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
RU2726648C1 (en) 2016-03-08 2020-07-15 ТерраПауэр, ЭлЭлСи Fission product getter
CN207038182U (en) * 2017-03-29 2018-02-23 泰拉能源有限责任公司 Caesium collector

Family Cites Families (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
BE758901A (en) * 1969-05-19 1971-04-16 Anderson Robert Neil NUCLEAR FUEL REACTOR INCLUDING A CRITICAL MASS OF ACTINIDE NITRIDE AND PROCEDURE FOR CONDUCTING THIS
DE2064983C3 (en) * 1969-05-19 1979-03-08 Robert N. Palo Alto Anderson Process for removing metallic fission products from spent actinide fuel assemblies
US3843766A (en) * 1969-12-09 1974-10-22 Us Navy Method of reprocessing nuclear fuels
NL7001798A (en) * 1970-02-09 1971-08-11
US3794482A (en) * 1971-02-05 1974-02-26 Parlee Anderson Corp Carbothermic reduction method for converting metal oxides to metal form
US3867510A (en) * 1973-04-23 1975-02-18 Atomic Energy Commission Process for recovering uranium and plutonium from irradiated nuclear fuel oxides

Also Published As

Publication number Publication date
DE3301641A1 (en) 1983-08-18
FR2520151B1 (en) 1987-08-28
CA1202787A (en) 1986-04-08
GB2113901A (en) 1983-08-10
FR2520151A1 (en) 1983-07-22

Similar Documents

Publication Publication Date Title
DE3277013D1 (en) Apparatus for removing and/or positioning fuel assemblies of a nuclear reactor
DE3369587D1 (en) Arrangement and method for storing spent fuel rods
EP0104477A3 (en) Method and device for inspecting image
DE3176385D1 (en) Method and apparatus for inspecting nuclear fuel pellets
DE3374035D1 (en) Toner containment method and apparatus
ZA838515B (en) Apparatus for maintenance of nuclear fuel assembly
DE3469628D1 (en) Method and apparatus for processing spent ion exchange resin
IT1160744B (en) METHOD AND TRAY LOADING APPARATUS FOR NUCLEAR FUEL TABLETS
DE3367691D1 (en) Method and apparatus for dismantling and disposing of fuel assemblies
DE3469087D1 (en) Hold-down apparatus for a nuclear reactor
JPS571034A (en) Method and device for automatically removing defective empty can
JPS5739395A (en) Method and device for operating safely nuclear reactor
GB2138129B (en) Method and apparatus for measuring uranium isotope enrichment
DE3380670D1 (en) Process for selectively separating plutonium from uranium and other metals
EP0218854A3 (en) Process and apparatus for regenerating spent reprocessing extraction solvent
DE3273860D1 (en) Method and apparatus for induced nuclear beta decay
DE3361505D1 (en) Method and device for modifying the concentration of a soluble poison in the coolant of the primary system of a nuclear reactor
GB2113901B (en) Apparatus and method for reprocessing and separating spent nuclear fuels
JPS5717898A (en) Method and device for removing tritium from mixture
EP0259747A3 (en) Continuous dissolution method and apparatus for spent nucontinuous dissolution method and apparatus for spent nuclear fuel clear fuel
DE3271902D1 (en) Method for treating nuclear fuel scrap
GB2038868B (en) Method and apparatus for reprocessing waste oils
JPS57128893A (en) Method of reprocessing spent nuclear fuel
GB2145650B (en) Device and method for storing radioactive wastes
JPS5791500A (en) Method of and apparatus for reducing capacity of radioactive waste

Legal Events

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