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11. 发明授权

EP0060649B1 A nuclear fuel cartridge and a method of preparing the cartridge for the extraction of nuclear material therefrom 有权
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

12. 发明授权

EP0032070B1 Appareil pour traiter des composés dans un liquide 有权
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

13. 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.

14. 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).

15. 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。

16. 发明公开

EP2657942A1 Method for corium and used nuclear fuel stabilization processing 有权
标题翻译： StabilisierungsverfahrenfürCorium undfürgebrauchten Kernbrennstoff
公开(公告)号：EP2657942A1
公开(公告)日：2013-10-30
申请号：EP13163951.0
申请日：2013-04-16
申请人： GE-Hitachi Nuclear Energy Americas LLC
发明人： Loewen, Eric P. , Berger, John F.
IPC分类号： G21C19/42 , G21C19/44 , G21C19/46 , G21C19/48
CPC分类号： G21C19/42 , G21C19/44 , G21C19/46 , G21C19/48 , Y02W30/882 , Y02W30/883 , Y02W30/884
摘要： A method 220 for stabilizing a nuclear material may include electrolytically reducing 220d the nuclear material in a first molten salt electrolyte of an electroreducer to produce a reduced material. A reducer waste may accumulate in the first molten salt electrolyte as a byproduct of the electroreduction. After the electroreduction, the reduced material may be electrolytically dissolved 230b in a second molten salt electrolyte of an electrorefiner to produce a purified metal product on a refiner cathode assembly of the electrorefiner. As a result of the electrorefining, a first refiner waste may accumulate in the second molten salt electrolyte and a second refiner waste may accumulate in a refiner anode assembly of the electrorefiner. The reducer waste from the electroreducer and the first refiner waste from the electrorefiner may be converted into a ceramic waste form, while the second refiner waste from the electrorefiner may be converted into a metallic waste form.
摘要翻译：用于稳定核材料的方法220可以包括电解还原电解质的第一熔盐电解质中的核材料220d以产生还原材料。还原剂废物可能作为电还原的副产物积累在第一熔盐电解液中。在电还原之后，还原的材料可以电解溶解在电学纯化器的第二熔盐电解液中230b，以在电学纯化器的精炼机阴极组件上产生纯化的金属产物。作为电解精炼的结果，第一精炼废物可能积聚在第二熔融盐电解质中，并且第二精炼废物可能积聚在电抛光器的精磨机阳极组件中。来自电动除菌器的还原剂废物和来自电解精炼机的第一精炼废物可以转化为陶瓷废物形式，而来自电学纯化器的第二精炼废物可以转化为金属废物形式。

17. 发明授权

EP1849164B1 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：EP1849164B1
公开(公告)日：2008-07-09
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.

18. 发明公开

EP0676771A1 NUCLEAR FUEL CYCLE 失效
标题翻译：核燃料循环
公开(公告)号：EP0676771A1
公开(公告)日：1995-10-11
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
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.
摘要翻译：一种为快速增殖和次级act系核湮灭反应堆循环核燃料的方法，其提供了具有技术优势的核燃料循环，所述技术优势例如核反应堆固有的安全性，短燃料加倍时间和高铀资源利用率以及经济优点，包括以下步骤：制备包括含铀钚混合氮化物燃料和次act系氮化物燃料的核燃料和钠热粘合材料的球形包装型燃料棒，将燃料棒安装在反应堆堆芯中使用过的燃料进行熔盐电解，将沉积在阴极上的铀，钚和次级act系元素转化成高阶氮化物，回收高阶氮化物，将回收的高阶氮化物转化为单氮化物，和从单硝酸盐制造含有铀 - 钚混合氮化物燃料和次级act系氮化物燃料的核燃料。

19. 发明公开

EP0069520A2 Continuous countercurrent liquid-solids contactor 失效
标题翻译：用于连续液体/固体接触逆流装置。
公开(公告)号：EP0069520A2
公开(公告)日：1983-01-12
申请号：EP82303359.2
申请日：1982-06-28
申请人： EXXON NUCLEAR COMPANY INC.
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.

20. 发明公开

EP0060649A1 A nuclear fuel cartridge and a method of preparing the cartridge for the extraction of nuclear material therefrom 有权
标题翻译：核燃料组件和制备药筒以除去核燃料材料的方法。
公开(公告)号：EP0060649A1
公开(公告)日：1982-09-22
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
摘要： A nuclear fuel cartridge (10) comprises a sheath (12), and nuclear material (20, 22, 24) inside the sheath (12). A continuous liquid permeable passageway (18) extends from one end of the nuclear material (20, 22, 24) to the other, and an annular end member (26, 36) is disposed at each end of the nuclear material (20,22,24). Inner spacing members (92) also of annular form may be disposed in intermediate positions along the sheath (12) between portions of the nuclear material (20a, 22a, 24a).

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