AU1291501A - A method of separating uranium from irradiated nuclear fuel - Google Patents

A method of separating uranium from irradiated nuclear fuel

Info

Publication number
AU1291501A
AU1291501A AU12915/01A AU1291501A AU1291501A AU 1291501 A AU1291501 A AU 1291501A AU 12915/01 A AU12915/01 A AU 12915/01A AU 1291501 A AU1291501 A AU 1291501A AU 1291501 A AU1291501 A AU 1291501A
Authority
AU
Australia
Prior art keywords
nuclear fuel
irradiated nuclear
separating uranium
uranium
separating
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.)
Abandoned
Application number
AU12915/01A
Other languages
English (en)
Inventor
Eric George Hope
Kevin James Webb
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.)
Sellafield Ltd
Original Assignee
British Nuclear Fuels PLC
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 British Nuclear Fuels PLC filed Critical British Nuclear Fuels PLC
Publication of AU1291501A publication Critical patent/AU1291501A/en
Abandoned 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
    • G21C19/48—Non-aqueous processes
    • 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)
  • Inorganic Compounds Of Heavy Metals (AREA)
AU12915/01A 1999-11-27 2000-11-14 A method of separating uranium from irradiated nuclear fuel Abandoned AU1291501A (en)

Applications Claiming Priority (3)

Application Number Priority Date Filing Date Title
GB9928035A GB9928035D0 (en) 1999-11-27 1999-11-27 A method of separating Uranium from irradiated Nuclear Fuel
GB9928035 1999-11-27
PCT/GB2000/004434 WO2001039209A2 (en) 1999-11-27 2000-11-22 A method of separating uranium from irradiated nuclear fuel

Publications (1)

Publication Number Publication Date
AU1291501A true AU1291501A (en) 2001-06-04

Family

ID=10865247

Family Applications (1)

Application Number Title Priority Date Filing Date
AU12915/01A Abandoned AU1291501A (en) 1999-11-27 2000-11-14 A method of separating uranium from irradiated nuclear fuel

Country Status (6)

Country Link
US (1) US6960326B1 (https=)
EP (1) EP1243000B1 (https=)
JP (1) JP4410446B2 (https=)
AU (1) AU1291501A (https=)
GB (1) GB9928035D0 (https=)
WO (1) WO2001039209A2 (https=)

Families Citing this family (11)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2008105928A2 (en) * 2006-09-08 2008-09-04 Michael Ernest Johnson Process for treating compositions containing uranium and plutonium
US20080161629A1 (en) * 2007-01-03 2008-07-03 Oleg Naljotov Radioactive waste processing
US8116423B2 (en) 2007-12-26 2012-02-14 Thorium Power, Inc. Nuclear reactor (alternatives), fuel assembly of seed-blanket subassemblies for nuclear reactor (alternatives), and fuel element for fuel assembly
JP5585883B2 (ja) 2007-12-26 2014-09-10 トリウム・パワー、インク 核燃料集合体、核燃料集合体を含む軽水炉、及び核燃料集合体の使用方法
CA2748367C (en) 2008-12-25 2016-11-29 Thorium Power, Inc. A light-water reactor fuel assembly and a fuel element thereof
US8506911B2 (en) 2009-07-29 2013-08-13 Battelle Memorial Institute Compositions and methods for treating nuclear fuel
WO2011143172A1 (en) 2010-05-11 2011-11-17 Thorium Power, Inc. Fuel assembly with metal fuel alloy kernel and method of manufacturing thereof
US10170207B2 (en) 2013-05-10 2019-01-01 Thorium Power, Inc. Fuel assembly
US10192644B2 (en) 2010-05-11 2019-01-29 Lightbridge Corporation Fuel assembly
RU2484020C1 (ru) * 2011-11-10 2013-06-10 Открытое акционерное общество "Сибирский химический комбинат" Способ получения тетрафторида урана
CN104361917B (zh) * 2014-11-06 2017-01-25 中国原子能科学研究院 用于乏燃料元件燃耗测量的自动化放化分离系统

Family Cites Families (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
NL250195A (https=) * 1959-04-06 1900-01-01
BE605293A (https=) * 1961-06-22 1961-12-22
US3145078A (en) * 1962-05-07 1964-08-18 Strickland Gerald Method of reprocessing nuclear fuel elements
FR1588220A (https=) * 1968-07-05 1970-04-10
US3832439A (en) 1973-01-10 1974-08-27 Atomic Energy Commission Method for the suppression of hydrogen during the dissolution of zirconium and zirconium alloys
US4212686A (en) * 1978-03-03 1980-07-15 Ab Atomenergi Zirconium alloys

Also Published As

Publication number Publication date
GB9928035D0 (en) 2000-01-26
JP2003515727A (ja) 2003-05-07
JP4410446B2 (ja) 2010-02-03
WO2001039209A3 (en) 2002-03-21
EP1243000A2 (en) 2002-09-25
WO2001039209A2 (en) 2001-05-31
EP1243000B1 (en) 2005-08-24
US6960326B1 (en) 2005-11-01

Similar Documents

Publication Publication Date Title
IL126216A0 (en) Separation of isotopes by ionisation for processing of nuclear fuel materials
ZA9810827B (en) A method and apparatus for direct conversion of uranium hexafluoride into uranium oxide
AU5716396A (en) Integrated data management system for nuclear power plant co mponents
AU6046398A (en) Method for separating bi-213 from a solution of radionuclides
AU5014100A (en) Methods for forming a radioactive stent
FI962648L (fi) Menetelmä cesiumin erottamiseksi ydinjäteliuoksista sekä menetelmä heksasyanoferraattien valmistamiseksi
AU1291501A (en) A method of separating uranium from irradiated nuclear fuel
AU5221300A (en) Stent for neutron capture therapy and method of manufacture therefor
GB2330448B (en) Method of processing spent reactor fuel
GB9722930D0 (en) Nuclear fuel reprocessing
AU2001242540A1 (en) Method for incinerating transuranian chemical elements and nuclear reactor usingsame
AU2526799A (en) Nuclear fuel reprocessing
AU8946991A (en) Method of inhibiting transcription utilizing nuclear receptors
AU5641596A (en) Process to remove rare earths from spent nuclear fuel
AU4961196A (en) A capsule for the containment of spent nuclear fuel and a method of manufacturing such a capsule
AU2001267367A1 (en) Method of incineration of minor actinides in nuclear reactors
IL146657A0 (en) Power from fission of spent nuclear waste
AUPM414594A0 (en) A process for extraction of uranium
AU5725596A (en) Methods and agents for the extraction of cesium and strontiu m from nuclear waste
AU2003273024A1 (en) Method and apparatus for reprocessing spent fuel from light-water reactor
AU2002324471A1 (en) Apparatus and method for installing nuclear reactors
AU2833999A (en) Method for cutting up a radioactive component of a nuclear reactor and device for carrying out said method
GB9507644D0 (en) Method of processing oxide nuclear fuel
GB2317612B (en) A method for producing an extract containing artemesinin
AU2190101A (en) A method of separating uranium

Legal Events

Date Code Title Description
MK6 Application lapsed section 142(2)(f)/reg. 8.3(3) - pct applic. not entering national phase