WO2008150188A1 - Rocédé de retraitement de combustible nucléaire usé - Google Patents

Rocédé de retraitement de combustible nucléaire usé Download PDF

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Publication number
WO2008150188A1
WO2008150188A1 PCT/RU2007/000400 RU2007000400W WO2008150188A1 WO 2008150188 A1 WO2008150188 A1 WO 2008150188A1 RU 2007000400 W RU2007000400 W RU 2007000400W WO 2008150188 A1 WO2008150188 A1 WO 2008150188A1
Authority
WO
WIPO (PCT)
Prior art keywords
nuclear fuel
processing method
processing
carried out
spent
Prior art date
Application number
PCT/RU2007/000400
Other languages
English (en)
Russian (ru)
Inventor
Nikolay Victorovich Stepanov
Petr Anatolievich Aleksandrov
Evgeniy Victorovich Burlakov
Aleksandra Vladimirovna Bocharova
Mikhail Andreevich Pavlov
Original Assignee
Nikolay Victorovich Stepanov
Petr Anatolievich Aleksandrov
Evgeniy Victorovich Burlakov
Bocharova Aleksandra Vladimiro
Mikhail Andreevich Pavlov
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 Nikolay Victorovich Stepanov, Petr Anatolievich Aleksandrov, Evgeniy Victorovich Burlakov, Bocharova Aleksandra Vladimiro, Mikhail Andreevich Pavlov filed Critical Nikolay Victorovich Stepanov
Publication of WO2008150188A1 publication Critical patent/WO2008150188A1/fr

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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
    • 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
    • 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

Definitions

  • the present invention relates to a technology for the processing of spent (irradiated) solid nuclear fuel of nuclear reactors - uranium dioxide by metallurgical method for the purpose of its further safe storage,.
  • the activity of spent nuclear fuel during long-term storage is determined mainly by the content of long-lived isotopes of xenon, strontium, etc.
  • This method does not allow complete removal of cesium during reprocessing of spent nuclear fuel, which leads to high radioactivity of the fuel to be stored.
  • the closest in technical essence to the proposed solution is a method for the reduction of metal oxides present in spent nuclear fuel (SNF), including loading into the crucible oxide of spent nuclear fuel and reducing material, melting the mixture and reducing to metallic yp.
  • SNF spent nuclear fuel
  • RF application • N22004127170, G21 C 19/44, 2004 In the known method, electrolytic separation of spent nuclear fuel is used.
  • the problem solved by the invention is the creation of a method for the processing of spent (irradiated) solid nuclear fuel, devoid of the above disadvantages, namely, a metallurgical processing method that reduces the activity of the reprocessed fuel, accelerates the recovery of spent nuclear fuel, and therefore significantly reduces the cost and makes it environmentally safe. storage and transportation.
  • the technical result in the present invention is achieved by the creation of a method for processing spent (irradiated) solid nuclear fuel, including loading the oxide of spent nuclear fuel and reducing material, melting the resulting charge and reducing to metal nuclear fuel, characterized in that the slag-diluent is added to the charge, then it is crushed and the resulting homogeneous charge is melted by high-frequency heating in an inert gas medium, and an exothermic reaction with at least one reducing material is used for the reduction process , then carry out the removal of slag saturating it with the most active products.
  • the proposed method will allow to separate the active material
  • the proposed method allows you to concentrate energy on heating oxide SNF (which determines the energy intensity of the process, since high-frequency heating reduces the energy intensity of deoxidation, since the process itself proceeds with the release of heat).
  • the invention is also characterized by the fact that the remaining melt of the uranium-based alloy is subjected to secondary isothermal segregation in a crucible settler, quenched, and then the obtained ingot is divided into at least three parts containing uranium, transuranic and light elements. This allows you to: get metallic uranium with a low content of impurities with a high capture cross section of thermal neutrons;
  • Freezing the melt allows you to collect slag, which includes all the elements that need to be removed, in the upper part of the melt, and then remove them.
  • the use of calcium metal, or sodium, or magnesium, or alloys based on them as a reducing agent is necessary for the deoxidation of spent nuclear fuel.
  • cryolite CaAlFb a diluent of cryolite CaAlFb, because It has a low melting point, and high wetting ability of oxide SNF.
  • the melting of a homogeneous charge which is carried out by high-frequency heating in an argon atmosphere at a frequency of 45-450 kHz and subsequent exothermic reaction at a temperature of 1450-1500 0 C for 15-60 minutes, is necessary for the formation of calcium oxide on the surface of SNF, which is extremely refractory and its can be separated.
  • Spent nuclear fuel (SNF) fuel pellets are crushed by co-grinding (wet grinding) with metal or a reducing material and a slag-thinner in the ratio:
  • the resulting mixture is dried in an inert gas atmosphere at a temperature of 60-90 0 C for 15-30 minutes.
  • the dried mass of the mixture is fed into the crucible and deoxidized by high-frequency heating in an atmosphere of inert gas, for example, argon at a frequency of 45-450 kHz until a molten metal and slag are formed. After the subsequent exothermic reaction of the melt at a temperature of 1450-1500 0 C for 15-60 minutes, slag saturated with active gases and elements with a low melting point is removed.
  • inert gas for example, argon
  • a metal reducing agent for example, calcium metal takes away oxygen from uranium dioxide UOg and decomposition products, except platinum, and a slag-diluent, for example, CaAlFb cryolite, sharply reduces the melting point of the newly formed oxides of the metal reducing agent CaO and floats the reactive charge.
  • a slag-diluent for example, CaAlFb cryolite
  • the resulting slag is removed together with the most active decay products that have saturated it and placed in a container for burial or storage.
  • the melt remaining in the crucible is poured into an isothermal settling crucible and kept therein at a temperature of 1,150–1300 ° C for 24–120 minutes with a temperature change along the length of the crucible of 0.1–0.2 ° C and fluctuation of the magnetic field voltage of 7– 1 OTe.
  • the ingot After cooling the ingot in a settling crucible, it is exposed to X-ray diffraction to reveal the delamination boundaries and is divided into three parts, uranium, transuranic and light elements.
  • the subsequent process of refining or extraction of individual elements can be carried out by traditional methods for weakly active materials.

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Manufacture And Refinement Of Metals (AREA)

Abstract

L'invention concerne la technologie de retraitement de combustible nucléaire solide usé (irradié) des réacteurs nucléaires, à savoir de dioxyde d'uranium, par un procédé métallurgique à des fins de son stockage ultérieur sécurisé. L'invention permet de créer un procédé de retraitement de combustible nucléaire solide usé (irradié) qui n'a pas les défauts des procédés existants; ce procédé métallurgique de retraitement permet de réduire l'activité de combustible nucléaire retraité, d'accélérer le procédé de réduction de combustible nucléaire usé et, partant, de rendre le stockage et le transport de celui-ci sensiblement moins onéreux et plus sûr du point de vue environnemental.
PCT/RU2007/000400 2007-06-05 2007-07-20 Rocédé de retraitement de combustible nucléaire usé WO2008150188A1 (fr)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
RU2007120888A RU2340021C1 (ru) 2007-06-05 2007-06-05 Способ переработки отработавшего ядерного топлива
RU2007120888 2007-06-05

Publications (1)

Publication Number Publication Date
WO2008150188A1 true WO2008150188A1 (fr) 2008-12-11

Family

ID=40093895

Family Applications (1)

Application Number Title Priority Date Filing Date
PCT/RU2007/000400 WO2008150188A1 (fr) 2007-06-05 2007-07-20 Rocédé de retraitement de combustible nucléaire usé

Country Status (2)

Country Link
RU (1) RU2340021C1 (fr)
WO (1) WO2008150188A1 (fr)

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
RU2711214C1 (ru) * 2019-07-12 2020-01-15 Федеральное государственное бюджетное учреждение "Национальный исследовательский центр "Курчатовский институт" Способ переработки отработавшего топлива тепловыделяющих сборок ядерного реактора

Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB981044A (en) * 1961-06-22 1965-01-20 Euratom Method of treating partly used nuclear fuels
GB1194624A (en) * 1967-05-19 1970-06-10 Euratom Oven for Processing Irradiated Nuclear Fuels
WO2001041152A2 (fr) * 1999-12-03 2001-06-07 British Nuclear Fuels Plc Production d'actinides
RU2004127170A (ru) * 2002-02-28 2005-05-10 Бритиш Нуклеа Фюэлс Плс (GB) Устройство для восстановления оксидов металла в металлическую форму и способ восстановления с применением этого устровства
RU2253916C1 (ru) * 2004-06-28 2005-06-10 Российский научный центр "Курчатовский институт" Способ переработки облученного ядерного топлива

Patent Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB981044A (en) * 1961-06-22 1965-01-20 Euratom Method of treating partly used nuclear fuels
GB1194624A (en) * 1967-05-19 1970-06-10 Euratom Oven for Processing Irradiated Nuclear Fuels
WO2001041152A2 (fr) * 1999-12-03 2001-06-07 British Nuclear Fuels Plc Production d'actinides
RU2004127170A (ru) * 2002-02-28 2005-05-10 Бритиш Нуклеа Фюэлс Плс (GB) Устройство для восстановления оксидов металла в металлическую форму и способ восстановления с применением этого устровства
RU2253916C1 (ru) * 2004-06-28 2005-06-10 Российский научный центр "Курчатовский институт" Способ переработки облученного ядерного топлива

Also Published As

Publication number Publication date
RU2340021C1 (ru) 2008-11-27

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