FR2455565A1 - Procede pour accelerer la dissolution et augmenter la solubilite, dans de l'acide nitrique, du dioxyde de plutonium et d'oxydes mixtes d'uranium/plutonium et de leurs residus - Google Patents

Procede pour accelerer la dissolution et augmenter la solubilite, dans de l'acide nitrique, du dioxyde de plutonium et d'oxydes mixtes d'uranium/plutonium et de leurs residus

Info

Publication number
FR2455565A1
FR2455565A1 FR8009668A FR8009668A FR2455565A1 FR 2455565 A1 FR2455565 A1 FR 2455565A1 FR 8009668 A FR8009668 A FR 8009668A FR 8009668 A FR8009668 A FR 8009668A FR 2455565 A1 FR2455565 A1 FR 2455565A1
Authority
FR
France
Prior art keywords
dissolution
nitric acid
plutonium
accelerating
residues
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
FR8009668A
Other languages
English (en)
Other versions
FR2455565B1 (fr
Inventor
Alfred Leonard Mills
Laurence Russell Weatherley
John Albert Crofts
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.)
UK Atomic Energy Authority
Original Assignee
UK Atomic Energy Authority
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 UK Atomic Energy Authority filed Critical UK Atomic Energy Authority
Publication of FR2455565A1 publication Critical patent/FR2455565A1/fr
Application granted granted Critical
Publication of FR2455565B1 publication Critical patent/FR2455565B1/fr
Expired legal-status Critical Current

Links

Classifications

    • 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
    • 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

  • Chemical & Material Sciences (AREA)
  • Organic Chemistry (AREA)
  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Inorganic Chemistry (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Inorganic Compounds Of Heavy Metals (AREA)

Abstract

L'INVENTION CONCERNE LE DOMAINE DU RETRAITEMENT DES COMBUSTIBLES POUR REACTEURS A NEUTRONS RAPIDES. ON ACCELERE ET AMPLIFIE LA DISSOLUTION, DANS DE L'ACIDE NITRIQUE, DE PUO ET DE UOPUO EN UTILISANT, POUR LA DISSOLUTION, DE L'ACIDE NITRIQUE TRES CONCENTRE (MOLARITE SUPERIEURE A 7) ET EN Y ASSURANT LA PRESENCE, PAR LITRE DE SOLUTION, D'AU MOINS 200GRAMMES DE PU OU DE UPU POUR QUE LE PU EN SOLUTION JOUE LE ROLE D'UN AUTOCATALYSEUR DE LA DISSOLUTION. IL VAUT MIEUX QUE L'ACIDE NITRIQUE CONTIENNE, PAR LITRE, AU MOINS 100GRAMMES DE PU, SOUS FORME DE NITRATE DE PLUTONIUM, JOUANT LE ROLE DE CATALYSEUR DE DISSOLUTION. APPLICATION: FACILITER LA SEPARATION DE PU, U ET DES PRODUITS DE FISSION D'UN COMBUSTIBLE IRRADIE SOUMIS A RETRAITEMENT.
FR8009668A 1979-04-30 1980-04-29 Procede pour accelerer la dissolution et augmenter la solubilite, dans de l'acide nitrique, du dioxyde de plutonium et d'oxydes mixtes d'uranium/plutonium et de leurs residus Expired FR2455565B1 (fr)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
GB7914978 1979-04-30
GB7938498 1979-11-07

Publications (2)

Publication Number Publication Date
FR2455565A1 true FR2455565A1 (fr) 1980-11-28
FR2455565B1 FR2455565B1 (fr) 1985-06-14

Family

ID=26271366

Family Applications (1)

Application Number Title Priority Date Filing Date
FR8009668A Expired FR2455565B1 (fr) 1979-04-30 1980-04-29 Procede pour accelerer la dissolution et augmenter la solubilite, dans de l'acide nitrique, du dioxyde de plutonium et d'oxydes mixtes d'uranium/plutonium et de leurs residus

Country Status (5)

Country Link
US (1) US4333912A (fr)
DE (1) DE3016516A1 (fr)
FR (1) FR2455565B1 (fr)
GB (1) GB2050039B (fr)
IT (1) IT1128436B (fr)

Families Citing this family (13)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE3038807A1 (de) * 1980-10-14 1982-06-03 Alkem Gmbh, 6450 Hanau Verfahren zum aufloesen schwerloeslicher thorium- und/oder plutoiumoxide
US4686019A (en) * 1982-03-11 1987-08-11 Exxon Research And Engineering Company Dissolution of PuO2 or NpO2 using electrolytically regenerated reagents
JPS6081025A (ja) * 1983-10-12 1985-05-09 Japan Atom Energy Res Inst 二酸化プルトニウム及びウラン・プルトニウム混合酸化物を溶解する方法
GB8403724D0 (en) * 1984-02-13 1984-03-14 British Nuclear Fuels Plc Treating nuclear fuel
DE3601826A1 (de) * 1986-01-22 1987-07-23 Alkem Gmbh Verfahren zum gewinnen einer loesung von schwer loeslichem kernbrennstoff, insbesondere von puo(pfeil abwaerts)2(pfeil abwaerts) oder (u/pu)o(pfeil abwaerts)2(pfeil abwaerts)-mischoxid
US4871479A (en) * 1986-03-25 1989-10-03 Comurhex Societe Pour La Conversion De L'uranium En Metal Et Hexafluorure Process for producing sintered mixed oxides which are soluble in nitric acid from solutions of nitrates
FR2688337B1 (fr) * 1992-03-05 1994-05-13 Commissariat Energie Atomique Procede de dissolution du bioxyde de plutonium au moyen de radicaux oh. produits par radiolyse de l'eau, utilisable pour le traitement des fines de dissolution et des dechets plutoniferes.
US5482688A (en) * 1994-02-07 1996-01-09 The United States Of America As Represented By The United States Department Of Energy Plutonium dissolution process
JP2963845B2 (ja) * 1994-07-19 1999-10-18 核燃料サイクル開発機構 核燃料の溶解方法
FR2738165B1 (fr) * 1995-09-06 1997-11-28 Cogema Procede et dispositif de dissolution d'un melange d'oxydes d'uranium et de plutonium
JP2948166B2 (ja) * 1997-04-04 1999-09-13 核燃料サイクル開発機構 使用済核燃料からの超ウラン元素の回収方法
FR2817492B1 (fr) * 2000-12-04 2003-07-18 Commissariat Energie Atomique Procede de dissolution des solides formes dans une installation nucleaire
RU2597874C2 (ru) * 2015-01-12 2016-09-20 Федеральное государственное унитарное предприятие "Горно-химический комбинат" (ФГУП "ГХК") Установка для переработки, отверждения и упаковки высокоактивных отходов

Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR1247758A (fr) * 1959-03-10 1960-12-02 Atomic Energy Commission Catalyseur de dissolution du bioxyde de plutonium dans l'acide nitrique et son procédé d'utilisation
GB968037A (en) * 1962-08-03 1964-08-26 Atomic Energy Authority Uk Improvements in or relating to the recovery of uranium values
US3813464A (en) * 1968-09-04 1974-05-28 Allied Chem Method of dissolving spent nuclear fuel
US4069293A (en) * 1975-05-06 1978-01-17 The United States Of America As Represented By The United States Department Of Energy Method for dissolving plutonium dioxide
DE2839010A1 (de) * 1977-09-08 1979-03-22 Gen Electric Verfahren zum wiedergewinnen von kernbrennstoff aus abfallmaterial und vorrichtung zur durchfuehrung des verfahrens

Family Cites Families (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2897047A (en) * 1954-02-26 1959-07-28 Wallace W Schulz Method of dissolving metallic uranium
NL293627A (fr) * 1962-06-06 1900-01-01

Patent Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR1247758A (fr) * 1959-03-10 1960-12-02 Atomic Energy Commission Catalyseur de dissolution du bioxyde de plutonium dans l'acide nitrique et son procédé d'utilisation
GB968037A (en) * 1962-08-03 1964-08-26 Atomic Energy Authority Uk Improvements in or relating to the recovery of uranium values
US3813464A (en) * 1968-09-04 1974-05-28 Allied Chem Method of dissolving spent nuclear fuel
US4069293A (en) * 1975-05-06 1978-01-17 The United States Of America As Represented By The United States Department Of Energy Method for dissolving plutonium dioxide
DE2839010A1 (de) * 1977-09-08 1979-03-22 Gen Electric Verfahren zum wiedergewinnen von kernbrennstoff aus abfallmaterial und vorrichtung zur durchfuehrung des verfahrens

Also Published As

Publication number Publication date
IT1128436B (it) 1986-05-28
IT8067684A0 (it) 1980-04-29
FR2455565B1 (fr) 1985-06-14
US4333912A (en) 1982-06-08
GB2050039B (en) 1983-01-19
DE3016516A1 (de) 1980-11-13
GB2050039A (en) 1980-12-31

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