FR2102358A2 - Thorium and/or uranium chloride - recovery from nuclear fuel elements - Google Patents

Thorium and/or uranium chloride - recovery from nuclear fuel elements

Info

Publication number
FR2102358A2
FR2102358A2 FR7129905A FR7129905A FR2102358A2 FR 2102358 A2 FR2102358 A2 FR 2102358A2 FR 7129905 A FR7129905 A FR 7129905A FR 7129905 A FR7129905 A FR 7129905A FR 2102358 A2 FR2102358 A2 FR 2102358A2
Authority
FR
France
Prior art keywords
thorium
uranium
recovery
nuclear fuel
fuel elements
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.)
Granted
Application number
FR7129905A
Other languages
French (fr)
Other versions
FR2102358B2 (en
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 Juelich GmbH
Original Assignee
Kernforschungsanlage Juelich GmbH
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 DE19681806077 external-priority patent/DE1806077A1/en
Priority claimed from DE19702040686 external-priority patent/DE2040686C3/en
Application filed by Kernforschungsanlage Juelich GmbH filed Critical Kernforschungsanlage Juelich GmbH
Publication of FR2102358A2 publication Critical patent/FR2102358A2/en
Application granted granted Critical
Publication of FR2102358B2 publication Critical patent/FR2102358B2/fr
Granted 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
    • G21C19/48—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

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Carbon And Carbon Compounds (AREA)

Abstract

Equipment for volatilising throium and/or uranium by chlorination, for the treatment of fissile and/or ground irradiated fertile nuclear material, more especially particles of diameter a frew hundred microns dispersed in graphite and in certain cases coated with pyrolytic carbon and/or silicon carbide, produced from carbides and/or oxides of thorium and uranium, at temperatures between 900 and 1200 degrees C, in which the reactor is a shaft furnace heater by the direct passage of electric curent. It consists of a porous graphite tube surrounded coaxially by a known type of ceramic shell provided with a branch connected to the condenser for the removal of the reaction products.
FR7129905A 1968-10-30 1971-08-17 Thorium and/or uranium chloride - recovery from nuclear fuel elements Granted FR2102358A2 (en)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
DE19681806077 DE1806077A1 (en) 1968-10-30 1968-10-30 Process for the processing of irradiated nuclear fuel and / or breeding material containing thorium
DE19702040686 DE2040686C3 (en) 1970-08-17 Device for chlorinating volatilization of thorium and / or uranium

Publications (2)

Publication Number Publication Date
FR2102358A2 true FR2102358A2 (en) 1972-04-07
FR2102358B2 FR2102358B2 (en) 1978-06-02

Family

ID=25756343

Family Applications (1)

Application Number Title Priority Date Filing Date
FR7129905A Granted FR2102358A2 (en) 1968-10-30 1971-08-17 Thorium and/or uranium chloride - recovery from nuclear fuel elements

Country Status (1)

Country Link
FR (1) FR2102358A2 (en)

Non-Patent Citations (6)

* Cited by examiner, † Cited by third party
Title
"ENTWICKLUNG EINES VERFAHRENS ZUR CHLORIERENDEN WIEDERAUFARBEITUNG GRAPHITUMHULLTER BRENN-UND *
(REVUE DT"KERNTECHNIK",VOL.12,AOUT 1970,NO 8 *
BRUTELEMENTE".) *
PAGES 321-326.ARTICLE DE FISCHER ET AL INTITULE : *
PAGES 321-326.ARTICLE DE FISCHER ET AL INTITULE : "ENTWICKLUNG EINES VERFAHRENS ZUR CHLORIERENDEN WIEDERAUFARBEITUNG GRAPHITUMHULLTER BRENN-UND BRUTELEMENTE".) *
REVUE DT"KERNTECHNIK",VOL.12,AOUT 1970,NO 8 *

Also Published As

Publication number Publication date
FR2102358B2 (en) 1978-06-02

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