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1. 发明公开

EP4354461A1 METHOD FOR PREPARING UO2 MIXTURE POWDER FOR NUCLEAR FUEL MANUFACTURING BY MEANS OF IBC BLENDER, AND UO2 MIXTURE POWDER FOR NUCLEAR FUEL MANUFACTURING, PREPARED THEREBY 审中-实审
公开(公告)号：EP4354461A1
公开(公告)日：2024-04-17
申请号：EP21945279.4
申请日：2021-08-20
申请人： Kepco Nuclear Fuel Co., Ltd.
发明人： JO, Bohyun , CHOI, Hui Sung , CHO, Dong Hyun , SON, Ji Hwan , PARK, Junseok
IPC分类号： G21C21/00 , G21C3/62 , G21C3/04
CPC分类号： Y02E30/30 , G21C3/62 , G21C21/00 , G21C3/04
摘要： According to a method for preparing a UO2 mixture powder for nuclear fuel manufacturing, of the present invention, mixing time is short, and degrees of mixing and homogeneity of a prepared UO2 mixture powder are excellent. The present invention relates to a method for preparing a UO2 mixture powder for nuclear fuel manufacturing, and provides a method for preparing a UO2 mixture powder for nuclear fuel manufacturing, comprising the steps of: (a) weighing and sieving, by means of an automatic injection device, a UO2 powder, a porogen and a lubricant, and injecting same into a UC container; and (b) mixing the UO2 powder, the porogen and the lubricant by means of an IBC blender.

2. 发明公开

EP3158563A4 AN ADDITIVE MANUFACTURING TECHNOLOGY FOR THE FABRICATION AND CHARACTERIZATION OF NUCLEAR REACTOR FUEL 有权
公开(公告)号：EP3158563A4
公开(公告)日：2018-02-14
申请号：EP15811002
申请日：2015-06-23
申请人： FREE FORM FIBERS LLC
发明人： PEGNA JOSEPH , VAALER ERIK G , HARRISON SHAY L , SCHNEITER JOHN L , WILLIAMS KIRK L , GODUGUCHINTA RAM K
IPC分类号： G21C3/02 , B23B19/00 , C04B35/565 , C04B35/628 , C04B35/80 , G21C3/04 , G21C3/42 , G21C21/02
CPC分类号： G21C3/20 , C04B35/565 , C04B35/62857 , C04B35/6286 , C04B35/62863 , C04B35/62865 , C04B35/62868 , C04B35/62873 , C04B35/62878 , C04B35/62884 , C04B35/62889 , C04B35/62894 , C04B35/62897 , C04B35/806 , C04B35/83 , C04B2235/3244 , C04B2235/3813 , C04B2235/422 , C04B2235/524 , C04B2235/5244 , C04B2235/5264 , C04B2235/5454 , C04B2235/614 , C23C16/08 , C23C16/483 , G21C3/04 , G21C3/07 , G21C3/18 , G21C3/28 , G21C3/42 , G21C3/62 , G21C21/02 , Y02E30/38
摘要： Nuclear fuel structures and methods for fabricating are disclosed herein. The nuclear fuel structure includes a plurality of fibers arranged in the structure and a multilayer fuel region within at least one fiber of the plurality of fibers. The multilayer fuel region includes an inner layer region made of a nuclear fuel material, and an outer layer region encasing the nuclear fuel material. A plurality of discrete multilayer fuel regions may be formed over a core region along the at least one fiber, the plurality of discrete multilayer fuel regions having a respective inner layer region of nuclear fuel material and a respective outer layer region encasing the nuclear fuel material. The plurality of fibers may be wrapped around an inner rod or tube structure or inside an outer tube structure of the nuclear fuel structure, providing both structural support and the nuclear fuel material of the nuclear fuel structure.

3. 发明公开

EP3076397A1 FUEL ROD CLADDING, FUEL ROD AND FUEL ASSEMBLY 有权
标题翻译： BRENNSTABHÜLLE，BRENNSTAB UND BRENNSTOFFANORDNUNG
公开(公告)号：EP3076397A1
公开(公告)日：2016-10-05
申请号：EP14864912.2
申请日：2014-06-03
申请人： Joint Stock Company "Akme-Engineering"
发明人： DERUNOV, Viacheslav Vasilievich , MAYOROV, Viktor Mihailovich , POMESCHIKOV, Pavel Andreevich , RUSANOV, Aleksander Evgenievich , SMIRNOV, Aleksandr Alekseevich , SHULEPIN, Sergey Viktorovich , SHARIKPULOV, Said Mirfaisovich
IPC分类号： G21C3/02 , G21C3/08 , G21C3/30
CPC分类号： G21C3/08 , G21C1/03 , G21C3/04 , G21C3/07 , G21C3/12 , G21C3/30 , G21C21/02 , Y02E30/40
摘要： The invention relates to the field of nuclear engineering and can be used in the manufacture of fuel rods and fuel assemblies for heavy liquid metal cooled reactors, and also in the manufacture of fuel rod simulators for use in irradiation devices designed to test the operability of real fuel assemblies. The present cladding of a fuel rod for a heavy liquid metal cooled reactor is in the form of a weldless tubular element with helically-coiled fins disposed on the outer surface of said element, which is made from a ferritic-martensitic chromium-silicon steel with a minimum ferrite grain size of 7 on the GOST 5639 scale, wherein each fin has an opening angle of from 22 to 40º (preferably from 30 to 40º) and the cross-section of the fin is in the shape of a trapezoid with rounded corners at the top of the trapezoid and smooth corners at the base of the trapezoid. Also disclosed are a fuel rod comprising the above cladding, and a fuel assembly. The technical result of the invention is an improvement in the performance characteristics of fuel rods and assemblies as a result of the long-term resistance of the cladding in the environment of a heavy liquid metal coolant such as lead or a eutectic of lead and bismuth.
摘要翻译：本发明涉及核工程领域，并且可用于制造用于重液态金属冷却反应器的燃料棒和燃料组件，并且还可用于制造燃料棒模拟器，其用于设计用于测试真实的可操作性的照射装置燃料组件用于重液态金属冷却反应器的燃料棒的现有包层是无焊接管状元件的形式，其中螺旋形螺旋翅片设置在所述元件的外表面上，该铁芯由铁素体 - 马氏体铬硅钢制成，在GOST 5639刻度上的最小铁素体晶粒尺寸为7，其中每个翅片具有22至40度（优选30至40度）的开度角，并且翅片的横截面呈梯形，具有圆角在梯形顶部的梯形和平滑的角落在梯形的基地。还公开了包括上述包层和燃料组件的燃料棒。本发明的技术结果是由于诸如铅或铅和铋的共晶体的重液态金属冷却剂的环境中包层的长期阻力而导致燃料棒和组件的性能特性的改进。

4. 发明授权

EP2109113B1 Detachable nuclear reactor fuel assembly component 失效
标题翻译：的装置的可拆卸的燃料组件
公开(公告)号：EP2109113B1
公开(公告)日：2014-09-03
申请号：EP09157187.7
申请日：2009-04-02
申请人： Global Nuclear Fuel-Americas, LLC
发明人： Lutz, Daniel Reese
IPC分类号： G21C3/04 , G21C3/326
CPC分类号： G21C3/04 , G21C3/326 , Y02E30/38

5. 发明公开

EP2511909A3 Nuclear fuel pellet 审中-公开
标题翻译：颗粒燃料
公开(公告)号：EP2511909A3
公开(公告)日：2013-01-02
申请号：EP12002540.8
申请日：2012-04-10
申请人： Westinghouse Electric Company LLC
发明人： Aleshin, Yurly , Mitchell, David B.
IPC分类号： G21C3/04 , G21C3/58
CPC分类号： G21C3/16 , G21C3/04 , G21C3/58 , G21C3/623 , Y02E30/38
摘要： A nuclear fuel pellet design that is a cylindrical axial profile with either a larger radius or conical shaped ends such that the as built diameter at the ends of the pellet are slightly smaller than at the middle and at normal operating conditions, the diameter at the ends is nearly the same as at the middle. Preferably, there are short chamfers at the axial ends of the pellet.

6. 发明授权

EP0545587B1 Fuel bundle and spacer utilizing tapered fuel rods 失效
标题翻译：燃料棒束和间隔件的使用锥形燃料棒
公开(公告)号：EP0545587B1
公开(公告)日：1997-09-03
申请号：EP92310607.4
申请日：1992-11-20
申请人： GENERAL ELECTRIC COMPANY
发明人： Johansson, Eric Bertil
IPC分类号： G21C3/04 , G21C3/34
CPC分类号： G21C3/344 , G21C3/04 , G21C3/334 , G21C3/34 , G21Y2002/30 , G21Y2002/302 , G21Y2004/30 , Y02E30/40

7. 发明公开

EP0514121A1 Nuclear fuel assembly comprising two-diameter fuel rods 失效
标题翻译： KernbrennstabbündelmitBrennstäbenvon zwei Durchmessern。
公开(公告)号：EP0514121A1
公开(公告)日：1992-11-19
申请号：EP92304247.7
申请日：1992-05-12
申请人： GENERAL ELECTRIC COMPANY
发明人： Matzner, Bruce , Reese, Anthony Paul , Johansson, Eric Bertil
IPC分类号： G21C3/328 , G21C3/04 , G21C3/16
CPC分类号： G21C3/16 , G21C3/04 , G21C3/328 , G21Y2002/201 , G21Y2004/30 , Y02E30/31 , Y02E30/38
摘要： A two-diameter fuel rod (R) is disclosed having a large diameter bottom tube (24) for holding a column of corresponding large diameter fuel pellets (60) at the fuel rod bottom, a smaller diameter top tube (22) for holding correspondingly smaller diameter pellets (51) at the top of the fuel rod, and a reducer (26) situated between the top (46) of the large diameter lower fuel tube (24) and the bottom (44) of the smaller diameter upper fuel tube (22). The lower column of larger diameter fuel pellets (60) is supported at its lower end on a spring (68) and biased at its upper end directly against the reducer (26); the upper column of smaller diameter fuel pellets (51) is supported at its upper end as close as possible to the underlying large diameter fuel pellets. Both tubes (22,24) are conventionally sealed and constructed at their distal ends from the bell reducer (26). Various kinds of reducer sections are disclosed. These reducer sections include a bell reducer of solid metallic construction, a tapered cladding tube, and, finally, telescoping cladding tubes welded together. There results a fuel bundle which has a uniform distribution of fuel and coolant with resultant uniform critical power response, no regions of nonuniform vapor flow, and improved flow area in the upper two-phase region of the bundle.
摘要翻译：公开了一种双直径燃料棒（R），其具有用于在燃料棒底部处保持相应的大直径燃料粒子（60）的柱的大直径底管（24），用于保持相应的较小直径的顶管（22）在燃料棒顶部的较小直径的颗粒（51）和位于大直径下燃料管（24）的顶部（46）和较小直径上燃料管（24）的底部（44）之间的减速器（26）（22）。较大直径的燃料颗粒（60）的下列在其下端支撑在弹簧（68）上，并且在其上端被偏压地抵靠减速器（26）; 较小直径的燃料颗粒（51）的上柱在其上端被支撑为尽可能靠近下面的大直径燃料颗粒。两个管（22,24）通常在其远端与钟罩减速器（26）密封和构造。公开了各种减速器部分。这些减速器部分包括实心金属结构的减振器，锥形包层管，以及最后焊接在一起的伸缩包层管。导致燃料束具有均匀分布的燃料和冷却剂，具有均匀的临界功率响应，不存在不均匀蒸气流的区域，以及在束的上部两相区域中改善的流动面积。

8. 发明公开

EP4365915A3 VARIABLE FUEL ROD DIAMETER 审中-实审
公开(公告)号：EP4365915A3
公开(公告)日：2024-07-31
申请号：EP24158749.2
申请日：2022-05-17
申请人： Westinghouse Electric Company LLC
发明人： GULER, Cenk , SUNG, Yixing
IPC分类号： G21C3/04 , G21C3/17 , G21C3/32
CPC分类号： G21C3/04 , G21C3/17 , G21C3/3213 , Y02E30/30
摘要： A variable diameter fuel rod of a nuclear reactor assembly is disclosed. The variable diameter fuel rod includes an elongated cladding tube configured to house a plurality of fuel pellets including a fissile material arranged in a fuel stack orientation. The elongated cladding tube includes first and second axial reflector regions and a middle axial region therebetween, an outer cladding diameter of the middle axial region defined as d1, an outer cladding diameter of at least one of the first or second axial reflector regions defined as d2, and a transitional region between the second diameter d1 of the middle axial region and the larger diameter d2 of the axial reflector region. The diameter d2 of the axial reflector region is greater than the diameter d1 of the middle axial region.

9. 发明公开

EP4365915A2 VARIABLE FUEL ROD DIAMETER 审中-实审
公开(公告)号：EP4365915A2
公开(公告)日：2024-05-08
申请号：EP24158749.2
申请日：2022-05-17
申请人： Westinghouse Electric Company LLC
发明人： GULER, Cenk , SUNG, Yixing
IPC分类号： G21C3/32
CPC分类号： G21C3/04 , G21C3/17 , G21C3/3213 , Y02E30/30
摘要： A variable diameter fuel rod of a nuclear reactor assembly is disclosed. The variable diameter fuel rod includes an elongated cladding tube configured to house a plurality of fuel pellets including a fissile material arranged in a fuel stack orientation. The elongated cladding tube includes first and second axial reflector regions and a middle axial region therebetween, an outer cladding diameter of the middle axial region defined as d1, an outer cladding diameter of at least one of the first or second axial reflector regions defined as d2, and a transitional region between the second diameter d1 of the middle axial region and the larger diameter d2 of the axial reflector region. The diameter d2 of the axial reflector region is greater than the diameter d1 of the middle axial region.

10. 发明公开

EP3101657A4 ACTIVE ZONE OF A LEAD-COOLED FAST REACTOR 失效
标题翻译： AKTIVER BEREICH EINES BLEIGEKLHLTEN SCHNELLEN REAKTORS
公开(公告)号：EP3101657A4
公开(公告)日：2017-08-30
申请号：EP14881368
申请日：2014-11-27
申请人： STATE ATOMIC ENERGY CORP ROSATOM ON BEHALF OF THE RUSSIAN FEDERATION
发明人： LEONOV VIKTOR NIKOLAEVICH , LOPATKIN ALEKSANDR VIKTOROVICH , RODINA ELENA ALEKSANDROVNA , CHERNOBROVKIN YURIY VASILIEVICH
IPC分类号： G21C1/02 , G21C3/04 , G21C3/42 , G21C3/58 , G21C5/14
CPC分类号： G21C3/04 , G21C1/02 , G21C1/022 , G21C3/42 , G21C3/58 , G21C5/14 , G21C2003/045 , G21Y2002/50 , G21Y2004/10 , G21Y2004/30 , Y02E30/34 , Y02E30/35 , Y02E30/38
摘要： An active zone of a reactor, a fuel element and a fuel assembly for creating said active zone are intended for use in fast reactors with a nitride fuel and a liquid-metal coolant primarily in the form of molten lead and alloys thereof. The problem addressed by the invention consists in creating an active zone with a void reactivity effect and with effective power flattening along the radius of the active zone. The active zone comprises a homogeneous uranium-plutonium nitride fuel, the mass fraction of which in the active zone is a minimum 0.305, and consists of 3 parts - a central part, an intermediate part and a peripheral part which form fuel assemblies comprising fuel elements with geometrically identical shells but with a differing height of the fuel column in the central part, the intermediate part and the peripheral part of the active zone, wherein the radial distribution of the fuel across the volume of the active zone is characterized by a stepped shape in a longitudinal section. The radius of the central part of the active zone is from 0.4 to 0.5 of the effective radius of the active zone, while the height of the fuel column in the fuel elements of the fuel assemblies in the central part is from 0.5 to 0.8 of the height of the fuel column in the fuel elements arranged in the fuel assemblies in the peripheral part of the active zone. The heights of the fuel columns forming a stepped intermediate part (with at least one step) for diameters ranging from 0.5 to 0.85 of the effective diameter of the active zone are selected within the range from 0.55 to 0.9 of the height of the fuel column in fuel elements arranged in the fuel assemblies in the peripheral part of the active zone.
摘要翻译：用于产生所述活性区的反应器，燃料元件和燃料组件的活性区域旨在用于具有主要为熔融铅及其合金形式的氮化物燃料和液态金属冷却剂的快速反应器中。本发明解决的问题在于创建具有空隙反应性效应的有效区域以及沿有效区域的半径的有效功率平坦化。活性区包括均质的铀 - 氮化钚燃料，其活性区中的质量分数最小为0.305，并且由3部分组成 - 中央部分，中间部分和周边部分，其形成包括燃料元件具有几何相同的壳体，但在活性区域的中心部分，中间部分和周边部分具有不同高度的燃料柱，其中燃料在活性区体积上的径向分布的特征在于阶梯形状在纵向部分。有效区域中心部分的半径为有效区域的有效半径的0.4至0.5，而中心部分中的燃料组件的燃料元件中的燃料柱的高度为0.5至0.8 布置在活性区域的周边部分中的燃料组件中的燃料元件中的燃料柱的高度。对于活性区的有效直径的直径为0.5至0.85的直径范围内的形成阶梯状中间部分（具有至少一个台阶）的燃料柱的高度选择在燃料柱高度的0.55至0.9的范围内燃料元件布置在活性区的周边部分中的燃料组件中。

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