[go: up one dir, main page]

RU2003110243A - METHOD FOR PROCESSING IRRADIATED NUCLEAR FUEL (OPTIONS) - Google Patents

METHOD FOR PROCESSING IRRADIATED NUCLEAR FUEL (OPTIONS)

Info

Publication number
RU2003110243A
RU2003110243A RU2003110243/06A RU2003110243A RU2003110243A RU 2003110243 A RU2003110243 A RU 2003110243A RU 2003110243/06 A RU2003110243/06 A RU 2003110243/06A RU 2003110243 A RU2003110243 A RU 2003110243A RU 2003110243 A RU2003110243 A RU 2003110243A
Authority
RU
Russia
Prior art keywords
solution
extraction
flow rate
nitric acid
nuclear fuel
Prior art date
Application number
RU2003110243/06A
Other languages
Russian (ru)
Other versions
RU2249267C2 (en
Inventor
Борис Яковлевич Зильберман
Леонид Васильевич Сытник
Аркадий Григорьевич Горский
Евгений Алексеевич Боровиков
Елена Николаевна Ковригина
Original Assignee
Государственное унитарное предприятие Научно-производственное объединение "Радиевый институт им. В.Г. Хлопина"
Filing date
Publication date
Application filed by Государственное унитарное предприятие Научно-производственное объединение "Радиевый институт им. В.Г. Хлопина" filed Critical Государственное унитарное предприятие Научно-производственное объединение "Радиевый институт им. В.Г. Хлопина"
Priority to RU2003110243A priority Critical patent/RU2249267C2/en
Priority claimed from RU2003110243A external-priority patent/RU2249267C2/en
Publication of RU2003110243A publication Critical patent/RU2003110243A/en
Application granted granted Critical
Publication of RU2249267C2 publication Critical patent/RU2249267C2/en

Links

Claims (2)

1. Способ переработки облученного ядерного топлива для получения совместного раствора U и Рu, включающий экстракцию U, Pu, Np, Тс из азотнокислого раствора 30%-ным раствором трибутилфосфата, отделение Np и Тc, отличающийся тем, что последующую реэкстракцию Pu проводят раствором обедненного или регенерированного четырехвалентного урана, подаваемым в среднюю часть блока реэкстракции Pu с расходом, обеспечивающим в реэкстракте весовое соотношения Pu:U=l:4 после отмывки реэкстрата оборотным экстрагентом от избыточного U(VI), при одновременной подаче в конец блока раствора 0,1-0,7 моль/л азотной кислоты с расходом, исключающим проскок U(IV) с экстрактом U(VI).1. A method of processing irradiated nuclear fuel to obtain a joint solution of U and Pu, including extraction of U, Pu, Np, Tc from a nitric acid solution with a 30% tributyl phosphate solution, separating Np and Tc, characterized in that the subsequent Pu re-extraction is carried out with a depleted or of regenerated tetravalent uranium supplied to the middle part of the Pu stripping unit with a flow rate providing the weight ratio Pu: U = l: 4 in the stripping after washing the stripping with reverse extractant from excess U (VI), while feeding to nets block solution of 0.1-0.7 mol / l of nitric acid with a flow rate excluding the slip of U (IV) with extract U (VI). 2. Способ переработки облученного ядерного топлива для получения совместного раствора U и Pu, включающий экстракцию U, Pu, Np, Тc из азотнокислого раствора 30%-ным раствором трибутилфосфата, отделение Np и Тc, отличающийся тем, что совместную реэкстракцию плутония и части урана проводят раствором комплексообразователя, подаваемым с постоянным составом и расходом, обеспечивающим полную реэкстракцию плутония, при одновременной подаче в конец блока раствора 0,1-0,7 моль/л азотной кислоты с расходом, обеспечивающим заданное поступление урана в смешанный реэкстракт.2. A method of processing irradiated nuclear fuel to produce a joint solution of U and Pu, including extraction of U, Pu, Np, Tc from a nitric acid solution with a 30% tributyl phosphate solution, separating Np and Tc, characterized in that the joint re-extraction of plutonium and parts of uranium is carried out a complexing agent solution supplied with a constant composition and flow rate, which ensures complete re-extraction of plutonium, while at the same time supplying 0.1-0.7 mol / L nitric acid to the end of the block with a flow rate providing a predetermined supply of uranium to the mixed boiled re-extract.
RU2003110243A 2003-04-09 2003-04-09 Method for recovering irradiated nuclear fuel (alternatives) RU2249267C2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
RU2003110243A RU2249267C2 (en) 2003-04-09 2003-04-09 Method for recovering irradiated nuclear fuel (alternatives)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
RU2003110243A RU2249267C2 (en) 2003-04-09 2003-04-09 Method for recovering irradiated nuclear fuel (alternatives)

Publications (2)

Publication Number Publication Date
RU2003110243A true RU2003110243A (en) 2004-10-20
RU2249267C2 RU2249267C2 (en) 2005-03-27

Family

ID=35560800

Family Applications (1)

Application Number Title Priority Date Filing Date
RU2003110243A RU2249267C2 (en) 2003-04-09 2003-04-09 Method for recovering irradiated nuclear fuel (alternatives)

Country Status (1)

Country Link
RU (1) RU2249267C2 (en)

Families Citing this family (9)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2903025B1 (en) * 2006-07-03 2008-10-10 Cogema PROCESS FOR SEPARATING A CHEMICAL ELEMENT FROM URANIUM FROM AN ACOUSTIC AQUEOUS PHASE IN A URANIUM EXTRACTION CYCLE
RU2382425C1 (en) * 2008-09-09 2010-02-20 Федеральное государственное унитарное предприятие "Горно-химический комбинат" Metod of processing spent nuclear fuel
RU2494479C1 (en) * 2012-04-09 2013-09-27 Российская Федерация, от имени которой выступает Федеральное государственное унитарное предприятие "Федеральный центр ядерной и радиационной безопасности" Method for obtaining solid solutions of oxides of actinides
RU2537013C2 (en) * 2012-12-07 2014-12-27 Открытое акционерное общество "Радиевый институт имени В.Г. Хлопина" Fuel composition for water-cooled thermal-neutron reactors
RU2561065C1 (en) * 2014-03-31 2015-08-20 Открытое акционерное общество "Радиевый институт имени В.Г. Хлопина" METHOD OF PRODUCING COMBINED SOLUTION OF U AND Pu
FR3039696B1 (en) * 2015-07-29 2017-07-28 Commissariat Energie Atomique ONE-CYCLE TREATMENT METHOD, FREE OF PLUTONIUM REDUCTIVE EXTRACTION OPERATION, OF A NITRIC AQUEOUS SOLUTION OF DISSOLUTION OF US NUCLEAR FUEL
FR3053151B1 (en) * 2016-06-23 2018-08-10 Commissariat A L'energie Atomique Et Aux Energies Alternatives PROCESS FOR DISSOLVING NUCLEAR FUEL
RU2691621C1 (en) * 2017-11-27 2019-06-17 Акционерное общество "Радиевый институт имени В.Г. Хлопина" Fuel composition for water-cooled thermal-neutron reactors
RU2691132C1 (en) * 2018-07-26 2019-06-11 Акционерное общество "Высокотехнологический научно-исследовательский институт неорганических материалов имени академика А.А. Бочвара" Method of plutonium extraction and purification

Family Cites Families (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3714324A (en) * 1968-06-18 1973-01-30 Gen Electric Irradiated fuel recovery system
RU2012075C1 (en) * 1992-05-14 1994-04-30 Научно-производственное объединение "Радиевый институт" им.В.Г.Хлопина Method of processing of irradiated fuel of atomic power plants
RU2132578C1 (en) * 1997-06-16 1999-06-27 Научно-производственное объединение "Радиевый институт им.В.Г.Хлопина" Method of processing irradiated nuclear fuel on nuclear power plants

Similar Documents

Publication Publication Date Title
JP4717078B2 (en) Complete the PUREX method and use it
ES2334852T3 (en) PROCESS FOR THE REPROCESSING OF AN EXHAUSTED NUCLEAR FUEL AND PREPARATION OF A MIXED URANUM-PLUTONIUM OXIDE.
WO2018097871A4 (en) Separation of metal ions by liquid-liquid extraction
CN107851470B (en) Method for treating aqueous nitric acid solution produced by dissolving spent nuclear fuel
RU2012106520A (en) METHOD FOR SELECTIVE EXTRACTION OF AMERICA FROM A NITRIC ACID WATER PHASE
RU2003110243A (en) METHOD FOR PROCESSING IRRADIATED NUCLEAR FUEL (OPTIONS)
KR102077380B1 (en) Method for separating americium from rare earth elements and method for separating americium from liquid radioactive waste
CN107245588A (en) A kind of method of extraction and recovery neptunium in post processing waste liquid from spentnuclear fuel
Wuhua et al. Extraction of rare earth elements from their oxides using organophosphorus reagent complexes with HNO3 and H2O in supercritical CO2
CN107177744B (en) A kind of method of extraction and separation group of the lanthanides and actinides
JP2017504013A (en) A method for treating spent nuclear fuel comprising the step of decontaminating uranium (VI) by complexing the actinide (IV) from at least one actinide (IV)
RU2249267C2 (en) Method for recovering irradiated nuclear fuel (alternatives)
Vanel et al. Modeling and flowsheet design of an Am separation process using TODGA and H4TPAEN
Chung et al. The reduction of Np (VI) by acetohydroxamic acid in nitric acid solution
JPS63198897A (en) Method particularly used for reprocessing irradiated nuclear fuel in order to separate technetium existing in organic solvent together with one kind or more of other metal such as zirconium and uranium or plutonium
CN103820656A (en) Uranium and plutonium separation technology in Purex process
JPH0453277B2 (en)
RU97110319A (en) METHOD FOR PROCESSING IRRADIATED NUCLEAR FUEL (SNF) NPP
Tkachenko et al. Dynamic test of extraction process for americium partitioning from the PUREX raffinate
CN116246812A (en) A method for retaining plutonium in the sewage solvent of the treatment process after neutral complexing agent elution
RU2007109748A (en) METHOD FOR EXTRACTION PROCESSING OF REGENERATED URANIUM
JP2971729B2 (en) Method for co-extraction of uranium, plutonium and neptunium
RU2447523C2 (en) Method for treatment of reprocessed uranium
JPH07239396A (en) High-level water liquid-treating method at reprocessing facilities
JP7108519B2 (en) Isolation method for minor actinides