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RU2012120148A - METHOD FOR CLEANING IRRADIATED NUCLEAR FUEL - Google Patents

METHOD FOR CLEANING IRRADIATED NUCLEAR FUEL Download PDF

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Publication number
RU2012120148A
RU2012120148A RU2012120148/07A RU2012120148A RU2012120148A RU 2012120148 A RU2012120148 A RU 2012120148A RU 2012120148/07 A RU2012120148/07 A RU 2012120148/07A RU 2012120148 A RU2012120148 A RU 2012120148A RU 2012120148 A RU2012120148 A RU 2012120148A
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RU
Russia
Prior art keywords
melt
molybdenum
nuclear fuel
electropositive
dissolved
Prior art date
Application number
RU2012120148/07A
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Russian (ru)
Other versions
RU2499306C1 (en
Inventor
Владимир Анатольевич Волкович
Борис Дмитриевич Васин
Дмитрий Сергеевич Мальцев
Денис Евгеньевич Александров
Original Assignee
Федеральное государственное автономное образовательное учреждение высшего профессионального образования "Уральский федеральный университет имени первого Президента России Б.Н. Ельцина"
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Application filed by Федеральное государственное автономное образовательное учреждение высшего профессионального образования "Уральский федеральный университет имени первого Президента России Б.Н. Ельцина" filed Critical Федеральное государственное автономное образовательное учреждение высшего профессионального образования "Уральский федеральный университет имени первого Президента России Б.Н. Ельцина"
Priority to RU2012120148/07A priority Critical patent/RU2499306C1/en
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Publication of RU2012120148A publication Critical patent/RU2012120148A/en
Publication of RU2499306C1 publication Critical patent/RU2499306C1/en

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    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

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  • Inorganic Compounds Of Heavy Metals (AREA)
  • Manufacture And Refinement Of Metals (AREA)

Abstract

1. Способ очистки облученного ядерного топлива в хлоридных расплавах, содержащих продукты растворения оксидного топлива посредством хлорирования, путем поэтапного извлечения электроположительных продуктов деления, отличающийся тем, что извлечение электроположительных продуктов деления осуществляют путем погружения в расплав пластины металлического молибдена и ее выдержки в контакте с расплавом в течение 2-5 ч, с последующей очисткой расплава от растворившегося молибдена.2. Способ по п.1, отличающийся тем, что растворившийся в расплаве молибден удаляют путем продувки расплава газообразным хлором.1. A method of purifying irradiated nuclear fuel in chloride melts containing the products of dissolution of oxide fuel by chlorination, by stage-by-stage extraction of electropositive fission products, characterized in that the extraction of electropositive fission products is carried out by immersing a plate of metal molybdenum in the melt and keeping it in contact with the melt in for 2-5 hours, followed by purification of the melt from dissolved molybdenum. 2. The method according to claim 1, characterized in that the molybdenum dissolved in the melt is removed by blowing the melt with gaseous chlorine.

Claims (2)

1. Способ очистки облученного ядерного топлива в хлоридных расплавах, содержащих продукты растворения оксидного топлива посредством хлорирования, путем поэтапного извлечения электроположительных продуктов деления, отличающийся тем, что извлечение электроположительных продуктов деления осуществляют путем погружения в расплав пластины металлического молибдена и ее выдержки в контакте с расплавом в течение 2-5 ч, с последующей очисткой расплава от растворившегося молибдена.1. The method of purification of irradiated nuclear fuel in chloride melts containing products of dissolution of oxide fuel by chlorination, by phased extraction of electropositive fission products, characterized in that the extraction of electropositive fission products is carried out by immersing a plate of metallic molybdenum in the melt and holding it in contact with the melt in for 2-5 hours, followed by purification of the melt from dissolved molybdenum. 2. Способ по п.1, отличающийся тем, что растворившийся в расплаве молибден удаляют путем продувки расплава газообразным хлором. 2. The method according to claim 1, characterized in that the molybdenum dissolved in the melt is removed by purging the melt with gaseous chlorine.
RU2012120148/07A 2012-05-15 2012-05-15 Method of cleaning irradiated nuclear fuel RU2499306C1 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
RU2012120148/07A RU2499306C1 (en) 2012-05-15 2012-05-15 Method of cleaning irradiated nuclear fuel

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Application Number Priority Date Filing Date Title
RU2012120148/07A RU2499306C1 (en) 2012-05-15 2012-05-15 Method of cleaning irradiated nuclear fuel

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RU2499306C1 RU2499306C1 (en) 2013-11-20

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Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
RU2603844C1 (en) * 2015-10-01 2016-12-10 Федеральное государственное бюджетное учреждение науки Институт высокотемпературной электрохимии Уральского отделения Российской Академии наук Method of nitride spent nuclear fuel recycling in salt melts

Families Citing this family (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP3734615B1 (en) * 2017-12-29 2024-10-09 State Atomic Energy Corporation "Rosatom" on Behalf of The Russian Federation Method for reprocessing nitride spent nuclear fuel in molten salts
US12431253B2 (en) 2023-06-21 2025-09-30 Abilene Christian University Fission product extraction system and methods of use thereof
US20250037889A1 (en) * 2023-07-26 2025-01-30 Abilene Christian University Extraction of fission products from molten salt via redox reaction with reducting agents
WO2025029454A2 (en) 2023-07-31 2025-02-06 Abilene Christian University Methods for the purification of molybdenum-99 with phase transfer agents

Family Cites Families (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CA768062A (en) * 1967-09-26 European Atomic Energy Community (Euratom) Process for the purification of nuclear fuels
FR2619952B1 (en) * 1987-09-01 1989-11-17 Pechiney Uranium PROCESS FOR CLEANING TRACES OF RADIOACTIVE ELEMENTS GENERATED DURING STORAGE OF URANIUM FROM THE PROCESSING OF IRRADIATED NUCLEAR FUELS
SU1746827A1 (en) * 1991-01-09 1997-02-10 Научно-исследовательский институт атомных реакторов им.В.И.Ленина Uranium-plutonium nuclear fuel regenerating method

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
RU2603844C1 (en) * 2015-10-01 2016-12-10 Федеральное государственное бюджетное учреждение науки Институт высокотемпературной электрохимии Уральского отделения Российской Академии наук Method of nitride spent nuclear fuel recycling in salt melts

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Effective date: 20140516