ES289866A1 - Procedimiento de tratamiento o regeneración de una solución acuosa de combustible agotado de reactores nucleares y de separación de los productos de fisión - Google Patents

Procedimiento de tratamiento o regeneración de una solución acuosa de combustible agotado de reactores nucleares y de separación de los productos de fisión

Info

Publication number
ES289866A1
ES289866A1 ES289866A ES289866A ES289866A1 ES 289866 A1 ES289866 A1 ES 289866A1 ES 289866 A ES289866 A ES 289866A ES 289866 A ES289866 A ES 289866A ES 289866 A1 ES289866 A1 ES 289866A1
Authority
ES
Spain
Prior art keywords
separation
regeneration
translation
treatment
machine
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
ES289866A
Other languages
English (en)
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.)
General Electric Co
Original Assignee
General Electric Co
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 General Electric Co filed Critical General Electric Co
Publication of ES289866A1 publication Critical patent/ES289866A1/es
Expired legal-status Critical Current

Links

Classifications

    • 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
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
    • C01G43/00—Compounds of uranium
    • C01G43/04—Halides of uranium
    • C01G43/06—Fluorides
    • 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
    • C22B60/0204—Obtaining thorium, uranium, or other actinides obtaining uranium
    • C22B60/0217—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes
    • C22B60/0252—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes treatment or purification of solutions or of liquors or of slurries
    • C22B60/026—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes treatment or purification of solutions or of liquors or of slurries liquid-liquid extraction with or without dissolution in organic solvents
    • 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
    • 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
    • Y02P—CLIMATE CHANGE MITIGATION TECHNOLOGIES IN THE PRODUCTION OR PROCESSING OF GOODS
    • Y02P10/00—Technologies related to metal processing
    • Y02P10/20—Recycling
    • 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)
  • Engineering & Computer Science (AREA)
  • General Life Sciences & Earth Sciences (AREA)
  • Organic Chemistry (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Geology (AREA)
  • Mechanical Engineering (AREA)
  • Materials Engineering (AREA)
  • Manufacturing & Machinery (AREA)
  • Metallurgy (AREA)
  • Environmental & Geological Engineering (AREA)
  • Physics & Mathematics (AREA)
  • Inorganic Chemistry (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Extraction Or Liquid Replacement (AREA)
  • Inorganic Compounds Of Heavy Metals (AREA)
ES289866A 1962-07-26 1963-07-10 Procedimiento de tratamiento o regeneración de una solución acuosa de combustible agotado de reactores nucleares y de separación de los productos de fisión Expired ES289866A1 (es)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US21276862A 1962-07-26 1962-07-26

Publications (1)

Publication Number Publication Date
ES289866A1 true ES289866A1 (es) 1963-12-01

Family

ID=22792351

Family Applications (1)

Application Number Title Priority Date Filing Date
ES289866A Expired ES289866A1 (es) 1962-07-26 1963-07-10 Procedimiento de tratamiento o regeneración de una solución acuosa de combustible agotado de reactores nucleares y de separación de los productos de fisión

Country Status (5)

Country Link
CH (1) CH488250A (es)
DE (1) DE1184745B (es)
ES (1) ES289866A1 (es)
GB (1) GB1031593A (es)
NL (1) NL295851A (es)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN112614604A (zh) * 2020-11-26 2021-04-06 中国辐射防护研究院 一种脉冲萃取柱有机相着火事故源项估算方法

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3511621A (en) * 1967-02-03 1970-05-12 Japan Atomic Energy Res Inst Process for recovering uranium as uranium dioxide

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN112614604A (zh) * 2020-11-26 2021-04-06 中国辐射防护研究院 一种脉冲萃取柱有机相着火事故源项估算方法

Also Published As

Publication number Publication date
GB1031593A (en) 1966-06-02
NL295851A (es) 1900-01-01
DE1184745B (de) 1965-01-07
CH488250A (de) 1970-03-31

Similar Documents

Publication Publication Date Title
GB1084642A (en) Improvements in irradiated nuclear fuel recovery
FR1244853A (fr) Procédé de réglage de réacteurs nucléaires
ES289866A1 (es) Procedimiento de tratamiento o regeneración de una solución acuosa de combustible agotado de reactores nucleares y de separación de los productos de fisión
ES313629A1 (es) Un procedimiento de obtencion en continuo de soluciones puras y concentradas de plutonio.
GB1050608A (es)
FR1266186A (fr) Procédé de régénération par décontamination partielle et pulvérisation de uo2 fritté, utilisé comme combustible de réacteur
GB2004407A (en) Purification of plutonium
GB1260096A (en) Organic phase reduction of uranium
ES335058A1 (es) Procedimiento de separacion del molibdeno de las solucionesnitricas de productos de fision.
GB1304313A (es)
ES294442A1 (es) Procedimiento de regeneración de combustible para reactores nucleares irradiado
GB788288A (en) Nuclear reactors
GB1170128A (en) Method of Separating Actinides from Admixture and/or Various Actinides from each other during Reprocessing Spent Nuclear Fuels.
GB877500A (en) A rotary piston steam engine
GB1188063A (en) A Process for Recovering Uranium as Uranium Dioxide
ES337390A1 (es) Procedimiento para la recuperacion y purificacion de com- bustibles nucleares.
GB945184A (en) Improvements in or relating to plutonium extraction
GB1183302A (en) Plutonium Separation
GB1205169A (en) Improvements in or relating to the processing or irradiated nuclear fuel
GB1153237A (en) A Method of Selective Reduction of Plutonium Hexafluoride and Apparatus for carrying out said Method
GB1323475A (en) Nuclear reactors
CA574555A (en) Chute assembly for nuclear reactor fuel rods removal
GB858094A (en) Method of separating fissile material
FR2330649A1 (fr) Procede de fabrication de 99mo et de 133xe
CA632473A (en) Liquid homogeneous nuclear reactor fuel fission products separation process