[go: up one dir, main page]

GB1456457A - Method of prolonging the activity of organic extracting agents - Google Patents

Method of prolonging the activity of organic extracting agents

Info

Publication number
GB1456457A
GB1456457A GB5062674A GB5062674A GB1456457A GB 1456457 A GB1456457 A GB 1456457A GB 5062674 A GB5062674 A GB 5062674A GB 5062674 A GB5062674 A GB 5062674A GB 1456457 A GB1456457 A GB 1456457A
Authority
GB
United Kingdom
Prior art keywords
mixture
lead
nov
contacted
nuclear fuel
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
GB5062674A
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.)
Gesellschaft fuer Kernforschung mbH
Original Assignee
Gesellschaft fuer Kernforschung mbH
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 Gesellschaft fuer Kernforschung mbH filed Critical Gesellschaft fuer Kernforschung mbH
Publication of GB1456457A publication Critical patent/GB1456457A/en
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
    • 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

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Extraction Or Liquid Replacement (AREA)

Abstract

1456457 Reprocessing nuclear fuel KERNFORSCHUNG mbH GES FUR 22 Nov 1974 [24 Nov 1973] 50626/74 Heading G6R A mixture of an organophosphoric acid ester and a hydrocarbon, which has been used in the processing of spent nuclear fuel, is purified by bringing the mixture into contact with a quadrivalent lead compound. A mixture of tributyl phosphate and an alkane may be contacted with lead dioxide or lead tetra-acetate, for example by passing the mixture through a column heated to 50‹ C. and containing a mixture of silica gel and lead dioxide. A preliminary treatment may comprise washing with sodium carbonate solution and equilibration with nitric acid. Tests are described in which the treated organic mixture is contacted with a nitric acid solution containing radioactive Zr or Hf.
GB5062674A 1973-11-24 1974-11-22 Method of prolonging the activity of organic extracting agents Expired GB1456457A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
DE2358688A DE2358688C3 (en) 1973-11-24 1973-11-24 Process for increasing the service life of organic extractants

Publications (1)

Publication Number Publication Date
GB1456457A true GB1456457A (en) 1976-11-24

Family

ID=5899015

Family Applications (1)

Application Number Title Priority Date Filing Date
GB5062674A Expired GB1456457A (en) 1973-11-24 1974-11-22 Method of prolonging the activity of organic extracting agents

Country Status (3)

Country Link
DE (1) DE2358688C3 (en)
FR (1) FR2252631B1 (en)
GB (1) GB1456457A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE4423398A1 (en) * 1994-07-04 1996-01-11 Siemens Ag Method and device for disposing of a cation exchanger
CN107051957A (en) * 2017-04-14 2017-08-18 中国原子能科学研究院 It is a kind of to remove the method that sodium is glued on damaged irradiated fuel assembly surface

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH0798122B2 (en) * 1991-07-12 1995-10-25 動力炉・核燃料開発事業団 Regeneration method of spent solvent generated from nuclear fuel cycle

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE4423398A1 (en) * 1994-07-04 1996-01-11 Siemens Ag Method and device for disposing of a cation exchanger
US5835865A (en) * 1994-07-04 1998-11-10 Siemens Aktiengesellschaft Method and device for the disposal of a cation exchanger
CN107051957A (en) * 2017-04-14 2017-08-18 中国原子能科学研究院 It is a kind of to remove the method that sodium is glued on damaged irradiated fuel assembly surface

Also Published As

Publication number Publication date
DE2358688C3 (en) 1979-02-22
DE2358688B2 (en) 1978-06-08
FR2252631B1 (en) 1980-10-31
DE2358688A1 (en) 1975-06-05
FR2252631A1 (en) 1975-06-20

Similar Documents

Publication Publication Date Title
GB1206776A (en) Irradiated fuel reprocessing
BR7602512A (en) PROCESS FOR RECOVERY OF URANIUM CONTENT AS URANYL PEROXIDE
GB1507170A (en) Method for increasing the lifetime of an extraction medium used for reprocessing spent nuclear fuel and/or breeder materials
GB1456457A (en) Method of prolonging the activity of organic extracting agents
GB1531985A (en) Technetium-99m
ES237011A1 (en) Process for separation of protactinium,thorium and uranium from neutronirradiated thorium
ES322748A1 (en) A method of treating an aqueous solution of irradiated nuclear reactor fuel. (Machine-translation by Google Translate, not legally binding)
GB1452115A (en) Method of selective stripping of plutonium for organic solvents loaded with plutonium
GB1312852A (en) Decontamination processes for radio-active liquids
FR1266186A (en) Regeneration process by partial decontamination and spraying of sintered uo2, used as reactor fuel
PH12225A (en) Process for sealing nuclear rector fuel rods
GB1068104A (en) Dissolution of nuclear fuel
GB1304313A (en)
GB822290A (en) Improvements in or relating to a process for the treatment of nuclear fuel
GB1365405A (en) Radionuclide generator and method for producing same
GB1324024A (en) Method for the separation of neptunium and plutonium
CH488250A (en) Process for the processing of aqueous solutions from irradiated nuclear reactor fuels
CH416853A (en) Process for improving the efficiency of nuclear reactors
GB945184A (en) Improvements in or relating to plutonium extraction
FR1261578A (en) Process for preparing uranium oxide
GB879041A (en) Improvements in or relating to the processing of nuclear reactor fuel elements
GB841602A (en) Method for the separation of plutonium from uranium
ES294442A1 (en) Fuel regeneration procedure for irradiated nuclear reactors (Machine-translation by Google Translate, not legally binding)
GB1000798A (en) Method for the inhibition of radiation damage to the reprocessing solvent tbp
CA640402A (en) Method of reprocessing uo2 reactor fuel

Legal Events

Date Code Title Description
PS Patent sealed
PCNP Patent ceased through non-payment of renewal fee