RU98117069A - METHOD FOR PROCESSING SPENT NUCLEAR FUEL - Google Patents

METHOD FOR PROCESSING SPENT NUCLEAR FUEL

Info

Publication number
RU98117069A
RU98117069A RU98117069/12A RU98117069A RU98117069A RU 98117069 A RU98117069 A RU 98117069A RU 98117069/12 A RU98117069/12 A RU 98117069/12A RU 98117069 A RU98117069 A RU 98117069A RU 98117069 A RU98117069 A RU 98117069A
Authority
RU
Russia
Prior art keywords
uranium
separated
nuclear fuel
spent nuclear
neptunium
Prior art date
Application number
RU98117069/12A
Other languages
Russian (ru)
Other versions
RU2182379C2 (en
Inventor
Робин Джон Тейлор
Ян Стюарт Деннисс
Эндрю Линдсей Уолворк
Original Assignee
Бритиш Ньюклиар Фьюэлз ПЛС
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 claimed from GB9603059A external-priority patent/GB9603059D0/en
Application filed by Бритиш Ньюклиар Фьюэлз ПЛС filed Critical Бритиш Ньюклиар Фьюэлз ПЛС
Publication of RU98117069A publication Critical patent/RU98117069A/en
Application granted granted Critical
Publication of RU2182379C2 publication Critical patent/RU2182379C2/en

Links

Claims (6)

1. Способ переработки отработанного ядерного топлива, который включает по меньшей мере образование водного раствора и проведение по меньшей мере одного этапа экстракции растворителем, отличающийся тем, что используют формогидроксамовую кислоту для восстановления Np(VI) в Np(V) и/или для образования комплексного соединения с Np(IV), при этом по существу весь имеющийся нептуний остается в водной фазе во время экстракции растворителем.1. A method of processing spent nuclear fuel, which includes at least forming an aqueous solution and carrying out at least one solvent extraction step, characterized in that formohydroxamic acid is used to reduce Np (VI) to Np (V) and / or to form a complex compounds with Np (IV), while essentially all of the available neptunium remains in the aqueous phase during solvent extraction. 2. Способ по п. 1, отличающийся тем, что отработанное ядерное топливо содержит уран и плутоний, при этом уран экстрагируют фазой растворителя. 2. The method according to p. 1, characterized in that the spent nuclear fuel contains uranium and plutonium, while uranium is extracted with a solvent phase. 3. Способ по п. 1 или 2, отличающийся тем, что нептуний отделяют от урана на том же этапе, когда уран отделяют от плутония. 3. The method according to p. 1 or 2, characterized in that the neptunium is separated from uranium at the same stage when the uranium is separated from plutonium. 4. Способ по п. 1 или 2, отличающийся тем, что плутоний первым отделяют от урана, а нептуний отделяют от урана на следующем этапе. 4. The method according to p. 1 or 2, characterized in that the plutonium is first separated from uranium, and neptunium is separated from uranium in the next step. 5. Способ по любому из предыдущих пунктов, отличающийся тем, что формогидроксамовую кислоту удаляют путем бурного газообразования в сильной азотной кислоте или с помощью добавления азотистой кислоты. 5. The method according to any one of the preceding paragraphs, characterized in that the formohydroxamic acid is removed by vigorous gas formation in strong nitric acid or by adding nitrous acid. 6. Способ по любому из предыдущих пунктов, отличающийся тем, что используют по меньшей мере один центробежный реактор. 6. The method according to any one of the preceding paragraphs, characterized in that at least one centrifugal reactor is used.
RU98117069A 1996-02-14 1997-02-14 Method for recovering spent nuclear fuel RU2182379C2 (en)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
GB9603059A GB9603059D0 (en) 1996-02-14 1996-02-14 Nuclear fuel processing
GB9603059.8 1996-02-14

Publications (2)

Publication Number Publication Date
RU98117069A true RU98117069A (en) 2000-08-20
RU2182379C2 RU2182379C2 (en) 2002-05-10

Family

ID=10788715

Family Applications (1)

Application Number Title Priority Date Filing Date
RU98117069A RU2182379C2 (en) 1996-02-14 1997-02-14 Method for recovering spent nuclear fuel

Country Status (9)

Country Link
US (1) US6093375A (en)
EP (1) EP0885444B1 (en)
JP (1) JP3927602B2 (en)
KR (1) KR19990082526A (en)
CN (1) CN1123013C (en)
CA (1) CA2243455C (en)
GB (1) GB9603059D0 (en)
RU (1) RU2182379C2 (en)
WO (1) WO1997030456A1 (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
RU2537952C2 (en) * 2009-07-02 2015-01-10 Арева Нс Improved method to process spent nuclear fuel

Families Citing this family (14)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB9722927D0 (en) * 1997-10-31 1998-01-07 British Nuclear Fuels Plc Nuclear fuel reprocessing
GB9722930D0 (en) * 1997-10-31 1998-01-07 British Nuclear Fuels Plc Nuclear fuel reprocessing
EP1105884A1 (en) * 1998-08-28 2001-06-13 British Nuclear Fuels PLC Nuclear fuel processing including reduction of np(vi) to np(v) with a hydrophilic substitituted hydroxylamine
EP1105883A1 (en) * 1998-08-28 2001-06-13 British Nuclear Fuels PLC Nuclear fuel reprocessing including reduction of np(vi) to np(v) with an oxime
GB0125951D0 (en) * 2001-10-30 2001-12-19 British Nuclear Fuels Plc Process for controlling valence states
FR2862804B1 (en) * 2003-11-20 2006-01-13 Commissariat Energie Atomique PROCESS FOR SEPARATING URANIUM (VI) FROM ACTINIDES (IV) AND / OR (VI) AND USES THEREOF
WO2008105928A2 (en) * 2006-09-08 2008-09-04 Michael Ernest Johnson Process for treating compositions containing uranium and plutonium
US7854907B2 (en) * 2008-11-19 2010-12-21 The Board of Regents of the Nevada System of Higher Education of the University of Nevada, Las Vegas Process for the extraction of technetium from uranium
US8270554B2 (en) * 2009-05-19 2012-09-18 The United States Of America, As Represented By The United States Department Of Energy Methods of producing cesium-131
CN103105344A (en) * 2011-11-11 2013-05-15 中核四0四有限公司 Measuring device for measuring medium parameters of pulsed extraction columns in pulse state
CN105734310B (en) * 2016-03-02 2018-03-09 中国原子能科学研究院 A kind of plutonium using dioxime Asia acid amides as reduction reextraction agent purifies method for concentration
FR3068257B1 (en) * 2017-06-29 2022-01-14 Commissariat Energie Atomique CARBAMIDES FOR THE SEPARATION OF URANIUM(VI) AND PLUTONIUM(IV) WITHOUT PLUTONIUM(IV) REDUCTION
CN108519374A (en) * 2018-01-24 2018-09-11 中国原子能科学研究院 Nuclear fuel post-processes the analysis method of hydroxy amino urea in flow
RU2756277C1 (en) * 2021-03-04 2021-09-30 Федеральное государственное бюджетное учреждение "Петербургский институт ядерной физики им. Б.П. Константинова Национального исследовательского центра "Курчатовский институт" Method for chemical enrichment of uranium with light isotopes

Family Cites Families (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US422941A (en) * 1890-03-11 Separating-machine
GB1392822A (en) * 1971-03-02 1975-04-30 Comitato Nazionale Per Lenergi Extraction of metals from solutions
DE2838541A1 (en) * 1977-09-16 1979-04-05 British Nuclear Fuels Ltd METHOD OF CLEANING UP A PLUTONIUM CONTAINING PHASE
DE3332954A1 (en) * 1983-09-13 1985-03-28 Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe METHOD FOR SEPARATING NEPTUNIUM FROM AN ORGANIC PHASE IN THE REPROCESSING OF IRRADIATED NUCLEAR FUELS AND / OR IRON MATERIALS
CN87105352B (en) * 1987-08-07 1988-11-02 中国建筑科学研究院地基基础研究所 Pile-forming equipment for cast concrete pile

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
RU2537952C2 (en) * 2009-07-02 2015-01-10 Арева Нс Improved method to process spent nuclear fuel

Similar Documents

Publication Publication Date Title
RU98117069A (en) METHOD FOR PROCESSING SPENT NUCLEAR FUEL
US7731870B2 (en) Purex method and its uses
RU2008151145A (en) METHOD FOR REGENERATING WASTE NUCLEAR FUEL AND OBTAINING MIXED URANIUM-PLUTONIUM OXIDE
JP4312969B2 (en) Reprocessing method of spent nuclear fuel
RU2012157573A (en) METHOD FOR PROCESSING WASTE NUCLEAR FUEL, NOT REQUIRING REDUCTIVE RE-EXTRACTION OF PLUTONIUM
ES439039A1 (en) Method of extraction, trapping and storage of radioactive iodine contained in irradiated nuclear fuels
CA2243455A1 (en) Nuclear fuel reprocessing
US4059671A (en) Method for increasing the lifetime of an extraction medium used for reprocessing spent nuclear fuel and/or breeder materials
WO1999023667A3 (en) Nuclear fuel reprocessing
US4229421A (en) Purification of plutonium
JP2010529442A (en) Use of butyraldehyde oxime as an anti-nitrite agent in plutonium reductive stripping operations
RU2454742C1 (en) Method for processing of spent nuclear fuel of nuclear power plants
CA1172438A (en) Treatment of fuel pellets
WO2001039209A3 (en) A method of separating uranium from irradiated nuclear fuel
DE2758408A1 (en) PROCESS FOR SEPARATION OF SEPARATE PRODUCTS
JPH0217902A (en) Extraction of solvent and solvent extraction/reactor
GB2217097A (en) Separation process and apparatus
RU98115974A (en) METHOD FOR REPEATED REFINED NUCLEAR FUEL
US2992886A (en) Method for dissolving zirconiumuranium compositions
JPS5327800A (en) Uranium or/and thorium removingand recovering method from soln. containing uranium or/and thorium
RU97108410A (en) METHOD OF RESTORING THE SUITABILITY OF A BURNED URANIUM ISOTOPES MIXED IN A NUCLEAR REACTOR
RU1804652C (en) Reconditioning method for radiated fuel elements
JPH0319169B2 (en)
CA2305542C (en) Nuclear fuel reprocessing
KR830006117A (en) Method for Extracting Uranium from Wet Phosphoric Acid