CH505443A - Process for recovering the constituents of irradiated nuclear fuel and device for carrying out the process - Google Patents

Process for recovering the constituents of irradiated nuclear fuel and device for carrying out the process

Info

Publication number
CH505443A
CH505443A CH1601768A CH1601768A CH505443A CH 505443 A CH505443 A CH 505443A CH 1601768 A CH1601768 A CH 1601768A CH 1601768 A CH1601768 A CH 1601768A CH 505443 A CH505443 A CH 505443A
Authority
CH
Switzerland
Prior art keywords
constituents
recovering
carrying
nuclear fuel
irradiated nuclear
Prior art date
Application number
CH1601768A
Other languages
French (fr)
Inventor
Manevy Georges
Matcheret Georges
Original Assignee
Commissariat Energie Atomique
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 Commissariat Energie Atomique filed Critical Commissariat Energie Atomique
Publication of CH505443A publication Critical patent/CH505443A/en

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
    • G21C19/48—Non-aqueous processes
    • 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
    • G21C19/34—Apparatus or processes for dismantling nuclear fuel, e.g. before reprocessing ; Apparatus or processes for dismantling strings of spent fuel elements
    • 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)
CH1601768A 1967-11-21 1968-10-25 Process for recovering the constituents of irradiated nuclear fuel and device for carrying out the process CH505443A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR129085 1967-11-21

Publications (1)

Publication Number Publication Date
CH505443A true CH505443A (en) 1971-03-31

Family

ID=8642040

Family Applications (1)

Application Number Title Priority Date Filing Date
CH1601768A CH505443A (en) 1967-11-21 1968-10-25 Process for recovering the constituents of irradiated nuclear fuel and device for carrying out the process

Country Status (10)

Country Link
BE (1) BE722979A (en)
CH (1) CH505443A (en)
DE (1) DE1809163B2 (en)
ES (1) ES360437A1 (en)
FR (1) FR1552176A (en)
GB (1) GB1171257A (en)
IL (1) IL30961A (en)
LU (1) LU57316A1 (en)
RO (1) RO58521A (en)
SE (1) SE337870B (en)

Families Citing this family (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE3103900C2 (en) * 1981-02-05 1984-02-02 Kernforschungsanlage Jülich GmbH, 5170 Jülich Plant for processing graphitic fuel elements from high-temperature nuclear reactors
JPS604890A (en) * 1983-06-23 1985-01-11 株式会社日立製作所 Pre-processing method in reprocessing of ceramics nuclear fuel
KR100347107B1 (en) * 1999-10-28 2002-07-31 한국전력공사 Decladding method and equipment of nuclear fuel pellet
FR3053151B1 (en) * 2016-06-23 2018-08-10 Commissariat A L'energie Atomique Et Aux Energies Alternatives PROCESS FOR DISSOLVING NUCLEAR FUEL
WO2020236516A1 (en) 2019-05-17 2020-11-26 Metatomic, Inc. Systems and methods for molten salt reactor fuel-salt preparation
US10685753B1 (en) 2019-05-17 2020-06-16 Metatomic, Inc. Systems and methods for fast molten salt reactor fuel-salt preparation

Also Published As

Publication number Publication date
GB1171257A (en) 1969-11-19
ES360437A1 (en) 1972-01-01
DE1809163B2 (en) 1971-06-16
IL30961A0 (en) 1970-01-29
RO58521A (en) 1975-09-15
LU57316A1 (en) 1969-02-25
BE722979A (en) 1969-04-01
IL30961A (en) 1972-07-26
SE337870B (en) 1971-08-23
FR1552176A (en) 1969-01-03
DE1809163A1 (en) 1970-03-19

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Legal Events

Date Code Title Description
PL Patent ceased