GB978615A - Improvements in or relating to the production of fuel materials for nuclear reactors - Google Patents

Improvements in or relating to the production of fuel materials for nuclear reactors

Info

Publication number
GB978615A
GB978615A GB29900/61A GB2990061A GB978615A GB 978615 A GB978615 A GB 978615A GB 29900/61 A GB29900/61 A GB 29900/61A GB 2990061 A GB2990061 A GB 2990061A GB 978615 A GB978615 A GB 978615A
Authority
GB
United Kingdom
Prior art keywords
solution
ions
precipitate
uranium
uranyl
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.)
Expired
Application number
GB29900/61A
Inventor
Ronald George Sowden
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
Priority to BE621422D priority Critical patent/BE621422A/xx
Application filed by UK Atomic Energy Authority filed Critical UK Atomic Energy Authority
Priority to GB29900/61A priority patent/GB978615A/en
Priority to DEU9135A priority patent/DE1223353B/en
Priority to FR905293A priority patent/FR1329961A/en
Priority to ES0280084A priority patent/ES280084A1/en
Publication of GB978615A publication Critical patent/GB978615A/en
Expired legal-status Critical Current

Links

Classifications

    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
    • C01G43/00—Compounds of uranium
    • C01G43/01—Oxides; Hydroxides
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
    • C01G43/00—Compounds of uranium
    • C01G43/01—Oxides; Hydroxides
    • C01G43/025—Uranium dioxide
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
    • C01G56/00—Compounds of transuranic elements
    • C01G56/003—Compounds comprising, besides transuranic elements, two or more other elements, with the exception of oxygen or hydrogen
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
    • C01G99/00—Subject matter not provided for in other groups of this subclass
    • C01G99/006—Compounds containing, besides a metal not provided for elsewhere in this subclass, two or more other elements other than oxygen or hydrogen
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/42—Selection of substances for use as reactor fuel
    • G21C3/58—Solid reactor fuel Pellets made of fissile material
    • G21C3/62—Ceramic fuel
    • G21C3/623—Oxide fuels
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01P—INDEXING SCHEME RELATING TO STRUCTURAL AND PHYSICAL ASPECTS OF SOLID INORGANIC COMPOUNDS
    • C01P2004/00—Particle morphology
    • C01P2004/80—Particles consisting of a mixture of two or more inorganic phases
    • C01P2004/82—Particles consisting of a mixture of two or more inorganic phases two phases having the same anion, e.g. both oxidic phases
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01P—INDEXING SCHEME RELATING TO STRUCTURAL AND PHYSICAL ASPECTS OF SOLID INORGANIC COMPOUNDS
    • C01P2006/00—Physical properties of inorganic compounds
    • C01P2006/12—Surface area
    • 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

Abstract

According to the Provisional Specification, uranium oxide is produced by precipitating the oxalate of uranium IV from a solution containing the corresponding metal ion and calcining the oxalate. U3O8 is formed and is reduced to UO2 by heating in hydrogen. The precipitate settles more rapidly and is more easily filtered than the precipitate of ammonium diuranate formed by addition of ammonia to a solution containing uranyl ions. In Example I a solution of uranyl nitrate, nitric acid, and urea (to inhibit reoxidation) is reduced electrolytically using a platinum anode and a mercury cathode, stirring being effected by an argon sparge. Oxalic acid solution is then added to form the precipitate. Alternatively (Example V), oxalate ions may be added to a dilute solution of uranyl ions and the solution electrolytically reduced, when the precipitate forms. Either process may be operated continuously. The anode may be of tantalum instead of platinum. The Complete Specification is restricted to the production of a mixture of uranium and plutonium oxides.ALSO:In the production of a mixture of uranium and plutonium oxides for use as nuclear fuel (see Division G6), a solution of uranyl nitrate, plutonium (IV) nitrate, nitric acid, and urea (to inhibit reoxidation) is reduced electrolytically using a platinum or tantalum anode and a mercury cathode, stirring being effected by an argon sparge. The solution then contains uranium (IV) and plutonium (III) ions which are precipitated as oxalates and the precipitate calcined. Alternatively, excess oxalate ions may be added to a dilute solution of uranyl and plutonyl ions and the solution electrolytically reduced, when the precipitate forms.
GB29900/61A 1961-08-18 1961-08-18 Improvements in or relating to the production of fuel materials for nuclear reactors Expired GB978615A (en)

Priority Applications (5)

Application Number Priority Date Filing Date Title
BE621422D BE621422A (en) 1961-08-18
GB29900/61A GB978615A (en) 1961-08-18 1961-08-18 Improvements in or relating to the production of fuel materials for nuclear reactors
DEU9135A DE1223353B (en) 1961-08-18 1962-07-21 Process for the production of a mixture of uranium and plutonium oxides
FR905293A FR1329961A (en) 1961-08-18 1962-07-27 Process for producing fuel for nuclear reactors
ES0280084A ES280084A1 (en) 1961-08-18 1962-08-17 Improvements in or relating to the production of fuel materials for nuclear reactors

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB29900/61A GB978615A (en) 1961-08-18 1961-08-18 Improvements in or relating to the production of fuel materials for nuclear reactors

Publications (1)

Publication Number Publication Date
GB978615A true GB978615A (en) 1964-12-23

Family

ID=10299021

Family Applications (1)

Application Number Title Priority Date Filing Date
GB29900/61A Expired GB978615A (en) 1961-08-18 1961-08-18 Improvements in or relating to the production of fuel materials for nuclear reactors

Country Status (4)

Country Link
BE (1) BE621422A (en)
DE (1) DE1223353B (en)
ES (1) ES280084A1 (en)
GB (1) GB978615A (en)

Cited By (11)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3361651A (en) * 1965-01-22 1968-01-02 Atomic Energy Authority Uk Electrolytic reduction of uranyl solutions
US3976749A (en) 1972-12-22 1976-08-24 Gesellschaft Fur Kernforschung M.B.H Method for producing pure monocarbides, mononitrides and carbonitrides
GB2196549A (en) * 1986-10-27 1988-05-05 British Nuclear Fuels Plc Ion exchange materials
WO1999066086A1 (en) * 1998-06-19 1999-12-23 Commissariat A L'energie Atomique Method for dissolving plutonium or a plutonium alloy and converting it into nuclear fuel
WO2002028778A1 (en) * 2000-10-05 2002-04-11 Commissariat A L'energie Atomique Method for co-precipitating actinides and method for preparing mixed actinide oxides
FR2870841A1 (en) * 2004-05-28 2005-12-02 Commissariat Energie Atomique PROCESS FOR COPRECIPITATION OF ACTINIDES TO SEPARATE OXIDATION STATES AND PROCESS FOR THE PREPARATION OF MIXED ACTINIDE COMPOUNDS
RU2505484C2 (en) * 2008-12-19 2014-01-27 Коммиссариат А Л' Энержи Атомик Э Оз Энержи Альтернатив Methods of preparing actinoid oxalate and preparation of actinoid compounds
FR2998288A1 (en) * 2012-11-19 2014-05-23 Commissariat Energie Atomique Preparing a uranium containing composition used for preparing a compacted fuel, by thermally treating a composition including a coordination complex consisting of a ligand, uranium and/or element e.g. plutonium under sufficient conditions
FR2998287A1 (en) * 2012-11-19 2014-05-23 Commissariat Energie Atomique Preparing a uranium containing composition used for preparing a porous fuel used in fast neutron or thermal neutron reactors, comprises thermally treating a coordination complex including uranium and an element under sufficient conditions
FR3074794A1 (en) * 2017-12-11 2019-06-14 Areva Nc PROCESS FOR THE PREPARATION OF A POWDER COMPRISING URANIUM SESQUIOXIDE PARTICLES AND PLUTONIUM DIOXIDE PARTICLES
WO2019115394A1 (en) * 2017-12-11 2019-06-20 Orano Cycle Method for preparing a powder comprising particles of triuranium octoxide and particles of plutonium dioxide

Family Cites Families (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2771340A (en) * 1944-06-27 1956-11-20 Martin D Kamen Improved uranium recovery and purification processes
US2933369A (en) * 1944-09-28 1960-04-19 David M Ritter Concentration of pu using oxalate type carrier
GB834531A (en) * 1954-12-11 1960-05-11 Atomic Energy Authority Uk Improvements in or relating to the recovery of plutonium from organic solvents

Cited By (25)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3361651A (en) * 1965-01-22 1968-01-02 Atomic Energy Authority Uk Electrolytic reduction of uranyl solutions
US3976749A (en) 1972-12-22 1976-08-24 Gesellschaft Fur Kernforschung M.B.H Method for producing pure monocarbides, mononitrides and carbonitrides
GB2196549A (en) * 1986-10-27 1988-05-05 British Nuclear Fuels Plc Ion exchange materials
US4959181A (en) * 1986-10-27 1990-09-25 British Nuclear Fuels Plc Ion exchange using hydrous uranium dioxide
GB2196549B (en) * 1986-10-27 1990-10-24 British Nuclear Fuels Plc Ion exchange materials
US6623712B1 (en) 1998-06-19 2003-09-23 Commissariat A L'energie Atomique Method for dissolving plutonium or a plutonium alloy and converting it into nuclear fuel
WO1999066086A1 (en) * 1998-06-19 1999-12-23 Commissariat A L'energie Atomique Method for dissolving plutonium or a plutonium alloy and converting it into nuclear fuel
FR2779974A1 (en) * 1998-06-19 1999-12-24 Commissariat Energie Atomique PROCESS FOR THE DISSOLUTION OF PLUTONIUM OR A PLUTONIUM ALLOY
US7169370B2 (en) 2000-10-05 2007-01-30 Commissariat A L'energie Atomique Method for co-precipitating actinides and method for preparing mixed actinide oxides
WO2002028778A1 (en) * 2000-10-05 2002-04-11 Commissariat A L'energie Atomique Method for co-precipitating actinides and method for preparing mixed actinide oxides
FR2815035A1 (en) * 2000-10-05 2002-04-12 Commissariat Energie Atomique ACTINIDE CO-PRECIPITATION PROCESS AND ACTINIDE MIXED OXIDE PREPARATION PROCESS
CN1961380B (en) * 2004-05-28 2014-06-25 法国原子能委员会 Method for co-precipitation of actinides in different oxidation states and method for preparation of mixed actinide compounds
WO2005119699A1 (en) * 2004-05-28 2005-12-15 Commissariat A L'energie Atomique Method for co-precipitation of actinides in different oxidation states and method for preparation of mixed actinide compounds
US7829043B2 (en) 2004-05-28 2010-11-09 Commissariat A L'energie Atomique Method for coprecipitation of actinides in different oxidation states and method for preparation of mixed compounds of actinides
FR2870841A1 (en) * 2004-05-28 2005-12-02 Commissariat Energie Atomique PROCESS FOR COPRECIPITATION OF ACTINIDES TO SEPARATE OXIDATION STATES AND PROCESS FOR THE PREPARATION OF MIXED ACTINIDE COMPOUNDS
RU2505484C2 (en) * 2008-12-19 2014-01-27 Коммиссариат А Л' Энержи Атомик Э Оз Энержи Альтернатив Methods of preparing actinoid oxalate and preparation of actinoid compounds
FR2998288A1 (en) * 2012-11-19 2014-05-23 Commissariat Energie Atomique Preparing a uranium containing composition used for preparing a compacted fuel, by thermally treating a composition including a coordination complex consisting of a ligand, uranium and/or element e.g. plutonium under sufficient conditions
FR2998287A1 (en) * 2012-11-19 2014-05-23 Commissariat Energie Atomique Preparing a uranium containing composition used for preparing a porous fuel used in fast neutron or thermal neutron reactors, comprises thermally treating a coordination complex including uranium and an element under sufficient conditions
FR3074794A1 (en) * 2017-12-11 2019-06-14 Areva Nc PROCESS FOR THE PREPARATION OF A POWDER COMPRISING URANIUM SESQUIOXIDE PARTICLES AND PLUTONIUM DIOXIDE PARTICLES
WO2019115394A1 (en) * 2017-12-11 2019-06-20 Orano Cycle Method for preparing a powder comprising particles of triuranium octoxide and particles of plutonium dioxide
GB2582493A (en) * 2017-12-11 2020-09-23 Orano Cycle Method for preparing a powder comprising particles of Triuranium octoxide and particles of plutonium dioxide
US20210166826A1 (en) * 2017-12-11 2021-06-03 Orano Cycle Method for preparing a powder comprising particles of triuranium octoxide and particles of plutonium dioxide
GB2582493B (en) * 2017-12-11 2022-02-16 Orano Cycle Method for preparing a powder comprising particles of triuranium octoxide and particles of plutonium dioxide
RU2767779C2 (en) * 2017-12-11 2022-03-21 Орано Сикль Method of producing powder containing triuranium octoxide particles and plutonium dioxide particles
US11594344B2 (en) * 2017-12-11 2023-02-28 Commissariat à l'énergie atomique et aux énergies alternatives Method for preparing a powder comprising particles of triuranium octoxide and particles of plutonium dioxide

Also Published As

Publication number Publication date
DE1223353B (en) 1966-08-25
ES280084A1 (en) 1963-02-01
BE621422A (en)

Similar Documents

Publication Publication Date Title
JP2004510726A (en) Actinide co-precipitation method and mixed actinide oxide preparation method
GB978615A (en) Improvements in or relating to the production of fuel materials for nuclear reactors
Ishimori et al. Distribution of neptunium between TBP and some mineral acids
JPH0611649B2 (en) Method for producing uranium tetrafluoride
US2868707A (en) Process of making a neutronic reactor fuel element composition
US3276850A (en) Method of selectively reducing plutonium values
GB991418A (en) Process for separating pure plutonium, thorium and uranium from impurities
RU2494479C1 (en) Method for obtaining solid solutions of oxides of actinides
US2982600A (en) Uranium decontamination with respect to zirconium
US3714322A (en) Method for preparing high purity 233 uranium
GB1602929A (en) Process for reducing plutonium
US2891840A (en) Method of processing neutronic reactor fuel elements
JPS6360108A (en) Separation and recovery of gadolinium
US3102848A (en) Nuclear fuel compositions and method of making the same
US2681923A (en) Compounds of the element americium
US3000697A (en) Transuranic element, composition thereof, and methods for producing, separating and purifying same
GB1370928A (en) Fuel and/or fertile material for nuclear reactors
Schulz et al. Nitric acid dissolution of uranium-molybdenum alloy reactor fuels
US3190804A (en) Method for producing, separating, and purifying plutonium
US2823978A (en) Precipitation method of separating plutonium from contaminating elements
US3005682A (en) Method of dissolving plutonium dioxide in nitric acid using cerium ions
US2989367A (en) Arsenate carrier precipitation method of separating plutonium from neutron irridiated uranium and radioactive fission products
US2917359A (en) Separation of fission product values from hexavalent plutonium by carrier precipitation
US3928538A (en) Processing of uranium hexafluoride including absorption of uranium hexafluoride in aqueous aluminum nitrate
US2892678A (en) Method of maintaining plutonium in a higher state of oxidation during processing