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11. 发明公开

EP1093657A2 APPARATUS FOR DISSOLVING NUCLEAR FUEL 审中-公开
标题翻译：设备为解决核燃料
公开(公告)号：EP1093657A2
公开(公告)日：2001-04-25
申请号：EP99955361.3
申请日：1999-06-03
申请人： British Nuclear Fuels PLC
发明人： RAGINSKII, Leonid Solomonovich , MORKOVNIKOV, Vyacheslav Evgen'evich , MOROZOV, Nikolai Viktorovich , ELISEEV, Sergei Petrovich , RANCE, Peter , TINSLEY, Timothy , DENNISS, Iain
IPC分类号： G21C19/44 , G21C19/38 , B01F1/00
CPC分类号： G21C19/44 , Y02W30/882
摘要： Nuclear fuel dissolution apparatus comprises a perforated sloping ramp (6) located within a process chamber (1). A pulsation member creates pulses in the solvent in the container, and the perforations of the sloping ramp are designed to direct pulses of solvent along and up the ramp. A discharge point (17, 18) for fuel holes is disposed at an upper region of the ramp. A method of dissolving fuel in chopped nuclear fuel pins is also described.

12. 发明公开

EP3314613A1 NUCLEAR FUEL STRUCTURE AND METHOD OF MAKING A NUCLEAR FUEL STRUCTURE USING A DETACHABLE CATHODE MATERIAL 有权
标题翻译：核燃料结构和使用可拆卸阴极材料制造核燃料结构的方法
公开(公告)号：EP3314613A1
公开(公告)日：2018-05-02
申请号：EP16732380.7
申请日：2016-06-02
申请人： Ge-Hitachi Nuclear Energy Americas LLC
发明人： MILLER, Gary, L. , KELLER, Keith, H.
IPC分类号： G21C19/42 , C25C3/34 , C25C7/00 , C25C7/02 , C22B60/02 , G21C19/44 , G21C19/48 , G21F9/30
CPC分类号： C25D17/12 , C25C3/34 , C25C7/005 , C25C7/025 , C25C7/08 , C25D3/54 , G21C19/42 , G21C19/44 , G21C19/48 , G21C21/02 , G21F9/30 , Y02W30/882 , Y02W30/884
摘要： A method of making a nuclear fuel structure may include reducing a metal oxide in a cathode assembly so as to deposit a metal of the metal oxide on the cathode plate of the cathode assembly, and processing the cathode plate with the metal deposited thereon to fabricate the nuclear fuel structure. The cathode plate may include an upper blade including an electrically conductive material, a lower blade portion connected to the upper blade, and a connection structure configured to secure the lower blade portion to the upper blade while providing electrical continuity. The connection structure may be configured to be disconnected from the lower blade portion to detach the lower blade portion from the upper blade.

13. 发明公开

EP2701158A1 METHOD FOR REPROCESSING IRRADIATED NUCLEAR FUEL 有权
标题翻译： VERFAHREN ZUR AUFARBEITUNG VON BESTRAHLTEM KERNBRENNSTOFF
公开(公告)号：EP2701158A1
公开(公告)日：2014-02-26
申请号：EP12774058.7
申请日：2012-03-05
申请人： Federal State Unitary Enterprise "Mining and Chemical Combine" (FSUE "MCC")
发明人： GAVRILOV, Petr Mikhailovich , KUDRYAVTSEV, Yevgeny Georgievich , REVENKO, Yury Alexandrovich , MERKULOV, Igor Alexandrovich , BONDIN, Vladimir Victorovich , VOLK, Vladimir Ivanovich , BYCHKOV, Sergey Ivanovich , ALEXEYENKO, Vladimir Nikolaevich
IPC分类号： G21F9/32 , G21C19/44
CPC分类号： G21C19/44 , G21C19/48 , G21F9/02 , G21F9/32 , Y02W30/882 , Y02W30/884
摘要： The method concerns processing irradiated (spent) nuclear fuel (SNF), is primarily aimed at isolating and trapping tritium, and can be used in nuclear power industry for treating SNF.
This method provides for the breakage of SNF elements comprising uranium dioxide into fragmented reaction mass and a two-phase voloxidation of the reaction mass using gas-air mixture. The first phase is carried out at 400-650°C in the presence of air and carbon dioxide. The second phase is carried out at 350-450°C using air-vapor mixture. Both phases are carried out at a continuous or periodic mechanical activation of the reaction mass. In the course of the voloxidation, the gas flow rate provides for 10-50-fold change of the reaction chamber gas volume per hour, and before being introduced into the reaction chamber, the gas is heated up to the chamber temperature at the respective phase.
摘要翻译：该方法涉及加工辐射（废）核燃料（SNF），主要是为了分离和捕获氚，可用于核电工业用于处理SNF。该方法提供了使用气体 - 空气混合物将包含二氧化铀的SNF元件断裂成碎片化的反应物质和反应物质的两相挥发。第一相在空气和二氧化碳的存在下，在400-650℃下进行。第二相使用空气 - 蒸汽混合物在350-450℃下进行。两相在反应物质的连续或周期性机械活化下进行。在氧化过程中，气体流量提供每小时反应室气体体积的10-50倍的变化，并且在引入反应室之前，将气体在各自的相位被加热到室温度。

14. 发明公开

EP1849164A1 HEAD-END PROCESS FOR THE REPROCESSING OF REACTOR CORE MATERIAL 有权
标题翻译：前端过程核材料再处理反应器
公开(公告)号：EP1849164A1
公开(公告)日：2007-10-31
申请号：EP06708310.5
申请日：2006-02-16
申请人： The European Atomic Energy Community (EURATOM), represented by the European Commission , Forschungszentrum Karlsruhe GmbH
发明人： FÜTTERER, Michael, A. , BLUHM, Hansjoachim , HOPPE , Peter , SINGER, Josef
IPC分类号： G21C19/34 , G21C19/44
CPC分类号： G21C19/34 , G21C19/44 , Y02W30/881 , Y02W30/882
摘要： In a head-end process for the reprocessing of reactor core material with embedded fuel particles, reactor core material is arranged in a reactor containing a fluid. The reactor comprises a voltage discharge installation in the fluid. Voltage discharges are applied through the fluid for fragmenting the fuel particles into fragmentation products and the fragmentation products are segregated.

15. 发明授权

EP0676771B1 NUCLEAR FUEL CYCLE 失效
标题翻译： KERNKRAFTSTOFFZYCLUS
公开(公告)号：EP0676771B1
公开(公告)日：1997-09-10
申请号：EP94929675.0
申请日：1994-10-18
申请人： Japan Atomic Energy Research Institute
发明人： HANDA, Muneo , KOBAYASHI, Fumiaki Annacs Tokai Village A-1 , KATSUTA, Hiroji
IPC分类号： G21C3/62 , G21C3/20 , G21C19/44 , C01B21/06 , C01G56/00
CPC分类号： C22B60/02 , G21C1/022 , G21C3/16 , G21C3/62 , G21C19/44 , G21Y2002/201 , G21Y2002/304 , G21Y2004/10 , G21Y2004/40 , G21Y2004/60 , Y02E30/34 , Y02E30/38 , Y02W30/882
摘要： A method of cycling a nuclear fuel for a fast breeder and a minor actinoids annihilation reactor, which provides a nuclear fuel cycle having technical advantages, such as a safety inherent in a nuclear reactor, a short fuel doubling time and a high uranium resources utilization factor, and economical advantages, comprising the steps of: preparing sphere pack type fuel pins including a nuclear fuel containing uranium-plutonium-mixed nitride fuel and a minor actinoids nitride fuel, and a sodium heat bonding material, installing the fuel pins in a reactor core and burning the same, subjecting the used fuel to fused salt electrolysis, converting the uranium, plutonium and minor actinoids deposited on a cathode into a high-order nitride, recovering the high-order nitride, converting the recovered high-order nitride into mononitride, and manufacturing a nuclear fuel, which contains a uranium-plutonium-mixed nitride fuel and a minor actinoids nitride fuel, from the mononitride.

16. 发明授权

EP0060649B1 A nuclear fuel cartridge and a method of preparing the cartridge for the extraction of nuclear material therefrom 失效
标题翻译：核燃料箱及其制备用于提取核材料的盒子的方法
公开(公告)号：EP0060649B1
公开(公告)日：1985-10-16
申请号：EP82301071.5
申请日：1982-03-03
申请人： UNITED KINGDOM ATOMIC ENERGY AUTHORITY
发明人： Hodgson, Thomas David
IPC分类号： G21C3/00 , G21C3/16
CPC分类号： G21C19/44 , Y02W30/882 , Y10S376/901

17. 发明授权

EP0032070B1 Appareil pour traiter des composés dans un liquide 失效
标题翻译：用于处理液体中的化合物的装置
公开(公告)号：EP0032070B1
公开(公告)日：1983-07-13
申请号：EP80401706.9
申请日：1980-11-28
申请人： COMMISSARIAT A L'ENERGIE ATOMIQUE Etablissement de Caractère Scientifique Technique et Industriel
发明人： Sauvage, Henri , Tarnero, Maurice
IPC分类号： B01D11/02 , G21C19/44
CPC分类号： B01D11/0261 , G21C19/38 , G21C19/44 , Y02W30/881 , Y02W30/882

18. 发明公开

EP0069520A3 Continuous countercurrent liquid-solids contactor 失效
标题翻译：连续反电势液体固体接触器
公开(公告)号：EP0069520A3
公开(公告)日：1983-03-09
申请号：EP82303359
申请日：1982-06-28
申请人： EXXON NUCLEAR COMPANY
发明人： Boldt, Allyn Lee
IPC分类号： B01D11/02 , G21C19/38
CPC分类号： B01D11/02 , B01D11/0223 , G21C19/38 , G21C19/44 , Y02W30/882 , Y10S422/903
摘要： An apparatus for continuously providing counter-current liquid-solid contact. A preferred embodiment of the apparatus includes an Archimedes' screw in the form of a spiral (24) and a distribution system which includes a central tube (6) disposed along the axis of the spiral. The central tube includes a plurality of weirs (20) and is in open communication with the spiral through a plurality of hollow spokes (22) fixed at one end to the spiral and at the other end to the central tube. Dissolving solution is distributed by the distribution system to the spiral when it encounters nuclear material moving upward due to the pumping action of the spiral. The dissolved material moves counter-current to the nuclear material and is removed near the bottom of the apparatus.

19. 发明授权

EP2709111B1 Methods of fabricating metallic fuel from surplus plutonium 有权
标题翻译：从多余的钚制造金属燃料的方法
公开(公告)号：EP2709111B1
公开(公告)日：2018-04-04
申请号：EP13184181.9
申请日：2013-09-12
申请人： GE-Hitachi Nuclear Energy Americas LLC
发明人： Loewen, Eric P. , Kosslow, Zachary W. , Berger, John F.
IPC分类号： G21C3/60 , G21C21/00 , C25C3/36 , G21C19/44
CPC分类号： C25C3/36 , G21C3/02 , G21C3/60 , G21C19/44 , G21C19/48 , G21C21/00 , Y02E30/34 , Y02E30/38 , Y02W30/882
摘要： A method of fabricating metallic fuel from surplus plutonium may include combining (102) plutonium oxide powder and uranium oxide powder to obtain a mixed powder with reduced proliferation potential. The mixed powder may be electroreduced (104) in a bath of molten salt so as to convert the mixed powder to a first alloy. The first alloy may be pressed (110) to remove a majority of the molten salt adhered to the first alloy to form a pressed alloy-salt mixture. The first alloy may be isolated (112) from the salt by melting the pressed alloy-salt mixture. The first alloy may be further processed to fabricate a fuel rod. Accordingly, the metallic fuel produced may be used in a fast reactor system, such as a Power Reactor Innovative Small Module (PRISM).

20. 发明公开

EP3300082A1 ELECTROLYTIC TANK AND ELECTROLYTIC METHOD FOR HIGH-EFFICIENCY DRY REPROCESSING 有权
标题翻译：高效率干法再处理的电解槽和电解方法
公开(公告)号：EP3300082A1
公开(公告)日：2018-03-28
申请号：EP16853421.2
申请日：2016-09-20
申请人： Clear Inc.
发明人： SUMITA, Osao , UENO, Isao , YOKOMINE, Takehiko
IPC分类号： G21C19/44 , C25C3/34 , C25C7/00 , C25C7/02 , C25C7/06
CPC分类号： C25C3/34 , C25C7/00 , C25C7/02 , C25C7/06 , G21C19/44 , G21C19/46
摘要： The present invention solves causes that reduce the efficiency in anodic electrolysis of a high-temperature molten salt during dry reprocessing of a spent metal fuel containing U and/or Pu. A molten salt electrolysis tank, in which electrolytic refining is performed by melting a spent metal fuel rod through anodic electrolysis in a crucible filled with a molten salt so as to cause U and/or Pu to be reduced and precipitated once again on the surface of a cathode, comprises: an anode feeder which is equipped with a mechanism for recovering deteriorated contact resistance that takes place between the metal fuel rod and the anode in the course of the anodic electrolysis; a cathode feeder which is controlled so as to have a potential in a range that causes U and/or Pu ions to be reduced to metal; a heating mechanism for locally heating the metal fuel rod and/or an excitation mechanism for bringing the metal fuel rod into a locally excited state; and a solenoid coil or a permanent magnet that is disposed between the anode feeder and the cathode feeder so as to improve separation efficiency of U and/or Pu ions by applying a combination of an electric field and a magnetic field. This molten salt electrolysis tank is used to carry out the anodic electrolysis.
摘要翻译：本发明解决了在含有U和/或Pu的废金属燃料的干再加工过程中降低高温熔盐的阳极电解效率的原因。一种熔盐电解槽，其中通过在充满熔盐的坩埚中通过阳极电解熔化废金属燃料棒来进行电解精炼，以使U和/或Pu再次还原并沉淀在一个阴极，包括：一个阳极馈线，它装备有一个机构，用于恢复在阳极电解过程中在金属燃料棒和阳极之间发生的接触电阻变差; 阴极供电装置，其被控制为具有使U和/或Pu离子还原成金属的电位; 用于局部加热金属燃料棒的加热机构和/或用于使金属燃料棒进入局部激励状态的激励机构; 以及设置在阳极进料器和阴极进料器之间以通过施加电场和磁场的组合来提高U和/或Pu离子的分离效率的螺线管线圈或永磁体。该熔盐电解槽用于进行阳极电解。

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