FR2456545A1 - Procede de dissolution dans l'acide nitrique, de l'oxyde de plutonium, notamment contenu sous forme d'oxyde dans les residus issus de l'industrie nucleaire - Google Patents

Procede de dissolution dans l'acide nitrique, de l'oxyde de plutonium, notamment contenu sous forme d'oxyde dans les residus issus de l'industrie nucleaire

Info

Publication number
FR2456545A1
FR2456545A1 FR7912185A FR7912185A FR2456545A1 FR 2456545 A1 FR2456545 A1 FR 2456545A1 FR 7912185 A FR7912185 A FR 7912185A FR 7912185 A FR7912185 A FR 7912185A FR 2456545 A1 FR2456545 A1 FR 2456545A1
Authority
FR
France
Prior art keywords
nitric acid
oxide
dissolving
mixing
pelleting
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
FR7912185A
Other languages
English (en)
Other versions
FR2456545B1 (fr
Inventor
Thierry Arnal
Jacques Heyraud
Jean-Claude Trestini
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.)
Commissariat a lEnergie Atomique et aux Energies Alternatives CEA
Original Assignee
Commissariat a lEnergie Atomique CEA
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 a lEnergie Atomique CEA filed Critical Commissariat a lEnergie Atomique CEA
Priority to FR7912185A priority Critical patent/FR2456545A1/fr
Publication of FR2456545A1 publication Critical patent/FR2456545A1/fr
Application granted granted Critical
Publication of FR2456545B1 publication Critical patent/FR2456545B1/fr
Granted legal-status Critical Current

Links

Classifications

    • 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
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
    • C01G56/00—Compounds of transuranic elements
    • C01G56/004—Compounds of plutonium
    • C—CHEMISTRY; METALLURGY
    • C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22B—PRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
    • C22B60/00—Obtaining metals of atomic number 87 or higher, i.e. radioactive metals
    • C22B60/02—Obtaining thorium, uranium, or other actinides
    • C22B60/04—Obtaining plutonium
    • 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
    • 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)
  • Organic Chemistry (AREA)
  • High Energy & Nuclear Physics (AREA)
  • General Engineering & Computer Science (AREA)
  • Metallurgy (AREA)
  • Materials Engineering (AREA)
  • Mechanical Engineering (AREA)
  • Geology (AREA)
  • Environmental & Geological Engineering (AREA)
  • Inorganic Chemistry (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Manufacturing & Machinery (AREA)
  • General Life Sciences & Earth Sciences (AREA)
  • Plasma & Fusion (AREA)
  • Inorganic Compounds Of Heavy Metals (AREA)

Abstract

LA PRESENTE INVENTION A POUR OBJET UN PROCEDE DE DISSOLUTION DANS L'ACIDE NITRIQUE DE L'OXYDE DE PLUTONIUM, NOTAMMENT CONTENU SOUS FORME D'OXYDE DANS LES RESIDUS ISSUS DE L'INDUSTRIE NUCLEAIRE. CE PROCEDE SE CARACTERISE EN CE QUE L'ON BROIE ET QU'ON MELANGE LE PRODUIT SEC CONTENANT L'OXYDE DE PLUTONIUM AVEC UNE QUANTITE CONVENABLE D'OXYDE D'URANIUM, QU'ON FRACTIONNE LE MELANGE OBTENU, PUIS QU'ON LE PORTE A UNE TEMPERATURE DE 1600 A 1800C PENDANT QUELQUES HEURES. LES PRODUITS OBTENUS PEUVENT ENSUITE ETRE DISSOUS FACILEMENT DANS UN BAIN D'ACIDE NITRIQUE CONCENTRE PORTE A EBULLITION. APPLICATION AU RETRAITEMENT DES RESIDUS ISSUS DE L'INDUSTRIE NUCLEAIRE.
FR7912185A 1979-05-14 1979-05-14 Procede de dissolution dans l'acide nitrique, de l'oxyde de plutonium, notamment contenu sous forme d'oxyde dans les residus issus de l'industrie nucleaire Granted FR2456545A1 (fr)

Priority Applications (1)

Application Number Priority Date Filing Date Title
FR7912185A FR2456545A1 (fr) 1979-05-14 1979-05-14 Procede de dissolution dans l'acide nitrique, de l'oxyde de plutonium, notamment contenu sous forme d'oxyde dans les residus issus de l'industrie nucleaire

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR7912185A FR2456545A1 (fr) 1979-05-14 1979-05-14 Procede de dissolution dans l'acide nitrique, de l'oxyde de plutonium, notamment contenu sous forme d'oxyde dans les residus issus de l'industrie nucleaire

Publications (2)

Publication Number Publication Date
FR2456545A1 true FR2456545A1 (fr) 1980-12-12
FR2456545B1 FR2456545B1 (fr) 1983-06-17

Family

ID=9225429

Family Applications (1)

Application Number Title Priority Date Filing Date
FR7912185A Granted FR2456545A1 (fr) 1979-05-14 1979-05-14 Procede de dissolution dans l'acide nitrique, de l'oxyde de plutonium, notamment contenu sous forme d'oxyde dans les residus issus de l'industrie nucleaire

Country Status (1)

Country Link
FR (1) FR2456545A1 (fr)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0049827A1 (fr) * 1980-10-14 1982-04-21 Alkem Gmbh Procédé de dissolution d'oxyde de plutonium difficilement soluble
FR2621578A1 (fr) * 1987-10-13 1989-04-14 Commissariat Energie Atomique Procede de dissolution reductrice du puo2, utilisable notamment pour le traitement de dechets organiques contamines par puo2

Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0049827A1 (fr) * 1980-10-14 1982-04-21 Alkem Gmbh Procédé de dissolution d'oxyde de plutonium difficilement soluble
US4528130A (en) * 1980-10-14 1985-07-09 Alkem Gmbh Method for dissolving hard-to-dissolve thorium and/or plutonium oxides
FR2621578A1 (fr) * 1987-10-13 1989-04-14 Commissariat Energie Atomique Procede de dissolution reductrice du puo2, utilisable notamment pour le traitement de dechets organiques contamines par puo2
EP0312433A1 (fr) * 1987-10-13 1989-04-19 Commissariat A L'energie Atomique Procédé de dissolution réductrice du Pu02, utilisable notamment pour le traitement de déchets organiques contaminés par Pu02
US5069827A (en) * 1987-10-13 1991-12-03 Commissariat A L'energie Atomique Process for reducing and dissolving puo2

Also Published As

Publication number Publication date
FR2456545B1 (fr) 1983-06-17

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Legal Events

Date Code Title Description
ST Notification of lapse