ES280084A1 - 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
ES280084A1
ES280084A1 ES0280084A ES280084A ES280084A1 ES 280084 A1 ES280084 A1 ES 280084A1 ES 0280084 A ES0280084 A ES 0280084A ES 280084 A ES280084 A ES 280084A ES 280084 A1 ES280084 A1 ES 280084A1
Authority
ES
Spain
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
ES0280084A
Other languages
Spanish (es)
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 ES280084A1 publication Critical patent/ES280084A1/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

Landscapes

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

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.
ES0280084A 1961-08-18 1962-08-17 Improvements in or relating to the production of fuel materials for nuclear reactors Expired ES280084A1 (en)

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
ES280084A1 true ES280084A1 (en) 1963-02-01

Family

ID=10299021

Family Applications (1)

Application Number Title Priority Date Filing Date
ES0280084A Expired ES280084A1 (en) 1961-08-18 1962-08-17 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)

Families Citing this family (11)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB1096592A (en) * 1965-01-22 1967-12-29 Atomic Energy Authority Uk Electrolytic reduction for solutions containing nuclear fuel material
DE2262868C3 (en) 1972-12-22 1979-03-29 Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe Process for the production of pure monocarbides, mononitrides and carbonitrides
GB8625657D0 (en) * 1986-10-27 1986-11-26 British Nuclear Fuels Plc Ion exchange material
FR2779974B1 (en) 1998-06-19 2000-07-13 Commissariat Energie Atomique PROCESS FOR THE DISSOLUTION OF PLUTONIUM OR A PLUTONIUM ALLOY
FR2815035B1 (en) 2000-10-05 2003-03-07 Commissariat Energie Atomique PROCESS FOR COPRECIPITATION OF ACTINIDES AND PROCESS FOR PREPARING MIXED ACTINIDE OXIDES
FR2870841B1 (en) * 2004-05-28 2007-02-09 Commissariat Energie Atomique PROCESS FOR COPRECIPITATION OF ACTINIDES TO SEPARATE OXIDATION STATES AND PROCESS FOR THE PREPARATION OF MIXED ACTINIDE COMPOUNDS
FR2940267B1 (en) * 2008-12-19 2011-12-09 Commissariat Energie Atomique PROCESS FOR THE PREPARATION OF ACTINIDE OXALATE (S) AND PREPARATION OF ACTINIDE COMPOUND (S)
FR2998288B1 (en) * 2012-11-19 2017-05-19 Commissariat Energie Atomique PROCESS FOR THE PREPARATION OF A COMPOSITION BASED ON AT LEAST ONE OXIDE COMPRISING URANIUM OTHER THAN U3O8 AND USE OF SAID COMPOSITION FOR THE MANUFACTURE OF DENSE NUCLEAR FUEL
FR2998287B1 (en) * 2012-11-19 2020-11-27 Commissariat Energie Atomique PROCESS FOR PREPARING A COMPOSITION BASED ON A POROGENIC AGENT OF THE U3O8 TYPE AND USE OF THIS COMPOSITION FOR THE MANUFACTURE OF A NUCLEAR FUEL
FR3074794B1 (en) * 2017-12-11 2020-01-10 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

Also Published As

Publication number Publication date
BE621422A (en)
GB978615A (en) 1964-12-23
DE1223353B (en) 1966-08-25

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