FR2379884A1 - Procede pour la liberation des produits de fission volatils a partir de combustibles nucleaires irradies - Google Patents

Procede pour la liberation des produits de fission volatils a partir de combustibles nucleaires irradies

Info

Publication number
FR2379884A1
FR2379884A1 FR7803277A FR7803277A FR2379884A1 FR 2379884 A1 FR2379884 A1 FR 2379884A1 FR 7803277 A FR7803277 A FR 7803277A FR 7803277 A FR7803277 A FR 7803277A FR 2379884 A1 FR2379884 A1 FR 2379884A1
Authority
FR
France
Prior art keywords
fission products
volatile fission
release
irradied
nuclear fuels
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
FR7803277A
Other languages
English (en)
Other versions
FR2379884B1 (fr
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.)
Framatome ANP Richland Inc
Original Assignee
Exxon Nuclear Co Inc
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 Exxon Nuclear Co Inc filed Critical Exxon Nuclear Co Inc
Publication of FR2379884A1 publication Critical patent/FR2379884A1/fr
Application granted granted Critical
Publication of FR2379884B1 publication Critical patent/FR2379884B1/fr
Granted legal-status Critical Current

Links

Classifications

    • E—FIXED CONSTRUCTIONS
    • E21—EARTH OR ROCK DRILLING; MINING
    • E21B—EARTH OR ROCK DRILLING; OBTAINING OIL, GAS, WATER, SOLUBLE OR MELTABLE MATERIALS OR A SLURRY OF MINERALS FROM WELLS
    • E21B7/00—Special methods or apparatus for drilling
    • E21B7/26—Drilling without earth removal, e.g. with self-propelled burrowing devices
    • 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
    • B—PERFORMING OPERATIONS; TRANSPORTING
    • B25—HAND TOOLS; PORTABLE POWER-DRIVEN TOOLS; MANIPULATORS
    • B25D—PERCUSSIVE TOOLS
    • B25D9/00—Portable percussive tools with fluid-pressure drive, i.e. driven directly by fluids, e.g. having several percussive tool bits operated simultaneously
    • B25D9/14—Control devices for the reciprocating piston
    • B25D9/26—Control devices for adjusting the stroke of the piston or the force or frequency of impact thereof
    • E—FIXED CONSTRUCTIONS
    • E21—EARTH OR ROCK DRILLING; MINING
    • E21B—EARTH OR ROCK DRILLING; OBTAINING OIL, GAS, WATER, SOLUBLE OR MELTABLE MATERIALS OR A SLURRY OF MINERALS FROM WELLS
    • E21B4/00—Drives for drilling, used in the borehole
    • E21B4/06—Down-hole impacting means, e.g. hammers
    • E21B4/14—Fluid operated hammers
    • E21B4/145—Fluid operated hammers of the self propelled-type, e.g. with a reverse mode to retract the device from the hole
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/28—Treating solids
    • G21F9/30—Processing
    • 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)
  • Physics & Mathematics (AREA)
  • Mining & Mineral Resources (AREA)
  • Geology (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Fluid Mechanics (AREA)
  • Mechanical Engineering (AREA)
  • Environmental & Geological Engineering (AREA)
  • High Energy & Nuclear Physics (AREA)
  • General Life Sciences & Earth Sciences (AREA)
  • Geochemistry & Mineralogy (AREA)
  • General Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • Automation & Control Theory (AREA)
  • Inorganic Compounds Of Heavy Metals (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Physical Or Chemical Processes And Apparatus (AREA)

Abstract

Procédé pour la libération des produits de fission volatils à partir de combustibles nucléaires irradiés. Le procédé de l'invention consiste à faire réagir des pastilles de combustible nucléaire irradié avec un agent oxydant du type oxyde d'azote à une température de réaction comprise entre environ 325 degrés C et 800 degrés C pendant un temps d'une durée suffisante pour former une poudre fine, ce qui a pour effet de libérer les produits de fission volatils. Application : élimination des produits de fission volatils.
FR7803277A 1977-02-07 1978-02-06 Procede pour la liberation des produits de fission volatils a partir de combustibles nucleaires irradies Granted FR2379884A1 (fr)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US76614277A 1977-02-07 1977-02-07

Publications (2)

Publication Number Publication Date
FR2379884A1 true FR2379884A1 (fr) 1978-09-01
FR2379884B1 FR2379884B1 (fr) 1984-10-19

Family

ID=25075540

Family Applications (1)

Application Number Title Priority Date Filing Date
FR7803277A Granted FR2379884A1 (fr) 1977-02-07 1978-02-06 Procede pour la liberation des produits de fission volatils a partir de combustibles nucleaires irradies

Country Status (8)

Country Link
JP (1) JPS6034718B2 (fr)
BE (1) BE863675A (fr)
DE (1) DE2801744C2 (fr)
ES (1) ES466675A1 (fr)
FR (1) FR2379884A1 (fr)
GB (1) GB1593323A (fr)
IT (1) IT1092476B (fr)
SE (1) SE429587B (fr)

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH0439019U (fr) * 1990-08-01 1992-04-02

Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR1266186A (fr) * 1959-11-12 1961-07-07 Atomic Energy Commission Procédé de régénération par décontamination partielle et pulvérisation de uo2 fritté, utilisé comme combustible de réacteur
BE611199A (fr) * 1961-12-06 1962-06-06 Ct D Etude De L En Nucleaire Procédé de ratraitement de combustibles nucléaires, lesquels comprennent du carbone dans leur structure et/ou dans leur gaine.
FR2304994A1 (fr) * 1975-03-17 1976-10-15 Agip Nucleare Spa Separation pyrochimique du plutonium des combustibles nucleaires irradies, par decomposition thermique dans les nitrates fondus

Patent Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR1266186A (fr) * 1959-11-12 1961-07-07 Atomic Energy Commission Procédé de régénération par décontamination partielle et pulvérisation de uo2 fritté, utilisé comme combustible de réacteur
BE611199A (fr) * 1961-12-06 1962-06-06 Ct D Etude De L En Nucleaire Procédé de ratraitement de combustibles nucléaires, lesquels comprennent du carbone dans leur structure et/ou dans leur gaine.
FR2304994A1 (fr) * 1975-03-17 1976-10-15 Agip Nucleare Spa Separation pyrochimique du plutonium des combustibles nucleaires irradies, par decomposition thermique dans les nitrates fondus

Also Published As

Publication number Publication date
SE7801361L (sv) 1978-08-08
SE429587B (sv) 1983-09-12
GB1593323A (en) 1981-07-15
JPS5399196A (en) 1978-08-30
DE2801744A1 (de) 1978-08-10
IT1092476B (it) 1985-07-12
FR2379884B1 (fr) 1984-10-19
JPS6034718B2 (ja) 1985-08-10
ES466675A1 (es) 1979-11-16
IT7819802A0 (it) 1978-01-30
DE2801744C2 (de) 1986-12-11
BE863675A (fr) 1978-08-07

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Legal Events

Date Code Title Description
ST Notification of lapse