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1. 发明授权

US10037822B2 Method for the in situ passivation of the steel surfaces of a nuclear reactor 有权
公开(公告)号：US10037822B2
公开(公告)日：2018-07-31
申请号：US15022834
申请日：2014-03-19
申请人： Joint Stock Company “AKME-Engineering”
发明人： Petr Nikiforovich Martynov , Radomir Shamilievich Askhadullin , Konstantin Dmitrievich Ivanov , Aleksandr Urievich Legkikh , Aleksey Nikolaevich Storozhenko , Aleksandr Ivanovich Filin , Sergey Viktorovich Bulavkin , Said Mirfaisovich Sharikpulov , Stepan Artemovich Borovitsky
IPC分类号： G21C1/03 , G21C13/08 , G21C21/00 , C23C22/72 , C23C22/73 , G21C15/247 , G21C17/022
CPC分类号： G21C1/03 , C23C22/72 , C23C22/73 , G21C13/08 , G21C15/247 , G21C17/0225 , G21C21/00 , Y02E30/40
摘要： The invention relates to the field of nuclear technology, and specifically to a method for the in situ passivation of steel surfaces. The method consists in installing, in a position intended for a regular core, a core simulator in the form of a model of the core, which models the shape thereof, the relative position of the core components, and also the mass characteristics thereof; next, the reactor is filled with a heavy liquid metal heat transfer medium, the heat transfer medium is heated to a temperature which provides for the conditions of passivation, and in situ passivation is carried out in two stages, the first of which includes an isothermal passivation mode in conformity with the conditions determined for this stage, and the second mode includes non-isothermal passivation, which is carried out under different conditions, after which the core simulator is removed and the regular core is installed in the place thereof. The method provides for the corrosion-resistance of steel elements in a heavy liquid metal heat transfer medium environment and permits a decrease in the maximum rate of oxygen consumption during the initial period of operation of a nuclear actor.

2. 发明申请

US20180105915A1 METHOD OF MANUFACTURING ZIRCONIUM NUCLEAR FUEL COMPONENT USING MULTI-PASS HOT ROLLING 审中-公开
公开(公告)号：US20180105915A1
公开(公告)日：2018-04-19
申请号：US15538798
申请日：2016-01-29
申请人： KEPCO NUCLEAR FUEL CO., LTD.
发明人： Yong Kyoon MOK , Yoon Ho KIM , Tae Sik JUNG , Sung Yong LEE , Hun JANG , Chung Yong LEE , Yeon Soo NA , Min Young CHOI , Dae Gyun KO , Seung Jae LEE , Jae Ik KIM
IPC分类号： C22F1/18 , C22C16/00 , C22F1/00 , G21C3/07
CPC分类号： C22F1/186 , B21B3/00 , B21B37/16 , C22C16/00 , C22F1/002 , C22F1/18 , G21C3/07 , G21C21/00
摘要： Disclosed is a method of manufacturing a zirconium alloy plate, wherein fine precipitates having an average size of 35 nm or less are uniformly distributed in a matrix through multi-pass hot rolling, thus increasing corrosion resistance and fatigue failure resistance, the method including forming a zirconium alloy ingot (step 1); subjecting the ingot of step 1 to beta annealing and rapid cooling (step 2); preheating the ingot of step 2 (step 3); forming a multi-pass hot-rolled plate through primary hot rolling and then air cooling during which secondary hot rolling is subsequently conducted (step 4); subjecting the multi-pass hot-rolled plate of step 4 to primary intermediate annealing and primary cold rolling (step 5); subjecting the rolled plate of step 5 to secondary intermediate annealing and secondary cold rolling (step 6); subjecting the rolled plate of step 6 to tertiary intermediate annealing and tertiary cold rolling (step 7); and finally annealing the rolled plate of step 7 (step 8).

3. 发明授权

US09659675B2 Fuel rod auto-loading apparatus for nuclear fuel assembly 有权
公开(公告)号：US09659675B2
公开(公告)日：2017-05-23
申请号：US14149872
申请日：2014-01-08
申请人： KEPCO NUCLEAR FUEL CO., LTD.
发明人： Ju Young Lee , Chang Hwan Hwang , Hung Soon Chang , Soon Ki Guk , Yeon Doo Jung , Ui Jea Lee
IPC分类号： G21C3/334 , G21C21/00 , G21C19/32
CPC分类号： G21C19/32 , G21C3/334 , G21C21/00 , Y02E30/40
摘要： Disclosed is a fuel rod auto-loading apparatus for a nuclear fuel assembly, which disposes fuel rods in a fuel rod case in a bundle to assemble the fuel rods into the nuclear fuel assembly. The fuel rod auto-loading apparatus includes a fuel rod storage unit having a plurality of stacked racks for fuel rods, a fuel rod loading unit raised/lowered to the racks and transferring the fuel rods, a feeding unit placing the fuel rods in rows and loading the fuel rods into the fuel rod case, a fuel rod unloading unit selectively unloading some of the fuel rods stored in the fuel rod storage unit and transferring the fuel rods to the feeding unit, a fuel rod assembly lifter which is disposed parallel to the feeding unit, and a controller controlling driving of the fuel rod loading unit, the feeding unit, and the fuel rod unloading unit.

4. 发明授权

US09496058B2 Devices and methods for managing noncondensable gasses in nuclear power plants 有权
标题翻译：用于管理核电厂不可冷凝气体的装置和方法
公开(公告)号：US09496058B2
公开(公告)日：2016-11-15
申请号：US14543286
申请日：2014-11-17
申请人： Wayne Marquino , Stephan C. Moen , Richard M. Wachowiak , John L. Gels , Jesus Diaz-Quiroz , John C. Burns, Jr.
发明人： Wayne Marquino , Stephan C. Moen , Richard M. Wachowiak , John L. Gels , Jesus Diaz-Quiroz , John C. Burns, Jr.
IPC分类号： G21C19/303 , G21C9/06 , G21C19/317 , B01J12/00 , G21C21/00 , B01D53/86 , B01J23/40 , B01J35/04
CPC分类号： G21C19/303 , B01D53/8671 , B01D2255/1023 , B01D2255/1025 , B01D2257/108 , B01J12/007 , B01J23/40 , B01J35/04 , G21C9/06 , G21C19/317 , G21C21/00 , Y02E30/40
摘要： Systems passively eliminate noncondensable gasses from facilities susceptible to damage from combustion of built-up noncondensable gasses, such as H2 and O2 in nuclear power plants, without the need for external power and/or moving parts. Systems include catalyst plates installed in a lower header of the Passive Containment Cooling System (PCCS) condenser, a catalyst packing member, and/or a catalyst coating on an interior surface of a condensation tube of the PCCS condenser or an annular outlet of the PCCS condenser. Structures may have surfaces or hydrophobic elements that inhibit water formation and promote contact with the noncondensable gas. Noncondensable gasses in a nuclear power plant are eliminated by installing and using the systems individually or in combination. An operating pressure of the PCCS condenser may be increased to facilitate recombination of noncondensable gasses therein.
摘要翻译：系统被动地从不受外部电力和/或移动部件需要的情况下，消除来自容易受到核能发电厂的不凝析气体（如H2和O2）的燃烧造成损害的设备的不凝气体。系统包括安装在无源遏制冷却系统（PCCS）冷凝器的下集管中的催化剂板，催化剂填充构件和/或PCCS冷凝器的冷凝管的内表面上的催化剂涂层或PCCS的环形出口冷凝器结构可以具有抑制水形成并促进与不可冷凝气体接触的表面或疏水性元素。通过单独或组合安装和使用系统来消除核电厂中不凝气体。可以增加PCCS冷凝器的操作压力以促进其中不凝结气体的复合。

5. 发明申请

US20160232991A1 LAYER PROTECTING THE SURFACE OF ZIRCONIUM ALLOYS USED IN NUCLEAR REACTORS 审中-公开
标题翻译：保护核反应堆中使用的锆合金表面的层
公开(公告)号：US20160232991A1
公开(公告)日：2016-08-11
申请号：US15022536
申请日：2014-09-16
申请人： CZECH TECHNICAL UNIVERSITY IN PRAGUE, FACULTY OF M ECHANICAL ENGINEERING, DEPARTMENT OF ENERGY ENGIE , INSTITUTE OF PHYSICS OF THE ACADEMY OF SCIENCES OF THE CZECH REPUBLIC, V.V.I.
发明人： Radek SKODA , Jan SKAROHLID , Irena KRATOCHVILOVA , Frantisek FENDRYCH , Andrew James TAYLOR
IPC分类号： G21C3/07 , G21C3/34 , C23C16/27
CPC分类号： G21C3/07 , C23C16/27 , G21C3/34 , G21C17/0225 , G21C21/00
摘要： A layer protecting the surface of zirconium alloys used as materials for nuclear reactors is formed by a homogenous polycrystalline diamond layer prepared by chemical vapor deposition method. This diamond layer is 100 nm to 50 μm thick and the size of the crystalline cores in the layer ranges from 10 nm to 500 nm. Maximum content of non-diamond carbon is 25 mol %, total content of non-carbon impurities is maximum up to 0.5 mol %, RMS surface roughness of the polycrystalline diamond layer has a value less than 40 nm and thermal conductivity of the layer ranges from 1000 to 1900 W⊙m−1⊙⊙K−1. Coating of the zirconium alloys surface with the described polycrystalline diamond layer serves as a zirconium alloys surface protection against undesirable changes and processes in the nuclear reactor environment.
摘要翻译：通过化学气相沉积法制备的均质多晶金刚石层形成了保护用作核反应堆材料的锆合金表面的层。该金刚石层的厚度为100nm〜50μm，层内的晶核尺寸为10nm〜500nm。非金刚石碳的最大含量为25mol％，非碳杂质的总含量最高达0.5mol％，多晶金刚石层的RMS表面粗糙度小于40nm，该层的热导率范围为 1000〜1900W⊙m-1⊙⊙K-1。用所述的多晶金刚石层涂覆锆合金表面起到锆合金表面保护作用，防止核反应堆环境中的不希望的变化和过程。

6. 发明授权

US09236151B2 Process for fabrication of a part with tubular geometry made from a ceramic matrix composite material 有权
标题翻译：由陶瓷基复合材料制成的具有管状几何形状的部件的工艺
公开(公告)号：US09236151B2
公开(公告)日：2016-01-12
申请号：US13564281
申请日：2012-08-01
申请人： Christophe Lorrette , Daniel Nunes , Cédric Sauder
发明人： Christophe Lorrette , Daniel Nunes , Cédric Sauder
IPC分类号： B21F9/00 , B66F3/00 , G21C3/06 , C04B35/52 , C04B35/565 , C04B35/80 , C04B35/83 , G21C21/00
CPC分类号： G21C3/06 , C04B35/52 , C04B35/565 , C04B35/806 , C04B35/83 , C04B2235/5244 , C04B2235/5248 , C04B2235/5252 , C04B2235/614 , C04B2235/94 , G21C21/00 , Y02E30/40
摘要： A device for tensioning a preform made from interlaced fibers is applied to tension the preform used in a process for fabricating a part made from a ceramic matrix composite material. During this process, the preform is tensioned before and during its densification using the tensioning device (100), which comprises a main body (2), a first assembly element (3) and a second assembly element (4) and a control rod, rotation of the control rod causing translation of the second assembly element, separation of the first and second assembly elements from each other and tensioning of the preform along the longitudinal direction.
摘要翻译：施加用于张紧由隔行纤维制成的预成型件的装置，用于张紧用于制造由陶瓷基复合材料制成的部件的工艺中的预成型件。在该过程中，使用包括主体（2），第一组件元件（3）和第二组件元件（4）以及控制杆的张紧装置（100），在其致密化之前和期间使预成型件张紧，所述控制杆的旋转导致所述第二组装元件的平移，所述第一和第二组件元件彼此分离并且沿着所述纵向方向张紧所述预成型件。

7. 发明授权

US09205507B2 Nuclear power plant construction preparation unit, nuclear power plant construction system, and nuclear power plant construction method 有权
标题翻译：核电厂建设准备单位，核电厂建设系统和核电厂施工方法
公开(公告)号：US09205507B2
公开(公告)日：2015-12-08
申请号：US13349043
申请日：2012-01-12
申请人： Isao Seki , Hisanobu Watanabe , Yuichi I , Takayuki Matsuura
发明人： Isao Seki , Hisanobu Watanabe , Yuichi I , Takayuki Matsuura
IPC分类号： G06F19/00 , B23K9/00 , B23K31/12 , B23K9/08
CPC分类号： B23K9/0052 , B23K9/08 , B23K31/12 , B23K31/125 , B23K2101/06 , B25J5/00 , B25J11/005 , B25J19/02 , G21C17/017 , G21C19/207 , G21C21/00
摘要： A nuclear power plant construction preparation unit includes: a device main body which enters into a space; a moving part which causes the device main body to enter into the space; an eddy-current inspection sensor which is provided on the device main body, and which detects a target portion of a member surface within the space; a punch marking part which is provided on the device main body, and which performs marking on the member surface; and a control part which controls the moving part and the marking device based on detection results from the target portion detection device, to thereby perform marking at a relative position with respect to the target portion.
摘要翻译：核电厂建设准备单元包括：进入空间的装置主体; 使装置主体进入空间的移动部; 涡流检查传感器，其设置在所述装置主体上，并且检测所述空间内的构件表面的目标部分; 冲压标记部，其设置在所述装置主体上，并且在所述构件表面上进行标记; 以及控制部，其基于来自所述目标部位检测装置的检测结果来控制所述移动部和所述标记装置，从而在相对于所述目标部的相对位置进行标记。

8. 发明授权

US08958520B2 Top nozzle for nuclear fuel assembly having spring insert hole improved in fastening stability and method of manufacturing the same 有权
标题翻译：用于核燃料组件的顶部喷嘴，其具有提高紧固稳定性的弹簧插入孔及其制造方法
公开(公告)号：US08958520B2
公开(公告)日：2015-02-17
申请号：US13524254
申请日：2012-06-15
申请人： Joon Kyoo Park , Jin Seok Lee , Kyeong Lak Jeon , Jung Min Suh , Gi-Jun Gwon , Nam Gyu Park , Kyong Bo Eom , Jin Sun Kim , Dong Geun Ha , Kyoung Joo Kim
发明人： Joon Kyoo Park , Jin Seok Lee , Kyeong Lak Jeon , Jung Min Suh , Gi-Jun Gwon , Nam Gyu Park , Kyong Bo Eom , Jin Sun Kim , Dong Geun Ha , Kyoung Joo Kim
IPC分类号： G21C21/00 , G21C21/16 , G21C3/33
CPC分类号： G21C3/331 , G21C3/3315 , G21C21/00 , Y02E30/40 , Y10T29/494 , Y10T29/49432
摘要： A top nozzle is provided. The top nozzle can include a coupling plate, a perimeter wall and a hold-down spring unit. The coupling plate can be coupled to a guide thimble of the nuclear fuel assembly. The perimeter wall can protrude upwards from the perimeter of the coupling plate. A spring clamp can be provided on the upper surface of the perimeter wall. The hold-down spring unit can be mounted to the upper surface of the perimeter wall in such a way to couple a corresponding end of the hold-down spring unit to the spring clamp. A fastening pin hole can be vertically formed through an upper surface of the spring clamp. A spring insert hole into which the hold-down spring unit can be inserted and formed by electro-discharge machining in an insert direction of the hold-down spring.
摘要翻译：提供顶部喷嘴。顶部喷嘴可以包括联接板，周边壁和压紧弹簧单元。联接板可以联接到核燃料组件的导向套管。周边壁可以从联接板的周边向上突出。可以在周壁的上表面上设置弹簧夹。压紧弹簧单元可以以这样的方式安装到周壁的上表面，以将压紧弹簧单元的相应端部联接到弹簧夹。紧固销孔可以通过弹簧夹的上表面垂直地形成。弹簧插入孔，压紧弹簧单元可以通过放电加工在压紧弹簧的插入方向上插入和形成。

9. 发明申请

US20140192945A1 FUEL ROD AUTO-LOADING APPARATUS FOR NUCLEAR FUEL ASSEMBLY 有权
标题翻译：用于核燃料组件的燃油自动装载装置
公开(公告)号：US20140192945A1
公开(公告)日：2014-07-10
申请号：US14149872
申请日：2014-01-08
申请人： KEPCO NUCLEAR FUEL CO., LTD.
发明人： Ju Young LEE , Chang Hwan HWANG , Hung Soon CHANG , Soon Ki GUK , Yeon Doo JUNG , Ui Jea LEE
IPC分类号： G21C19/32
CPC分类号： G21C19/32 , G21C3/334 , G21C21/00 , Y02E30/40
摘要： Disclosed is a fuel rod auto-loading apparatus for a nuclear fuel assembly, which disposes fuel rods in a fuel rod case in a bundle to assemble the fuel rods into the nuclear fuel assembly. The fuel rod auto-loading apparatus includes a fuel rod storage unit having a plurality of stacked racks for fuel rods, a fuel rod loading unit raised/lowered to the racks and transferring the fuel rods, a feeding unit placing the fuel rods in rows and loading the fuel rods into the fuel rod case, a fuel rod unloading unit selectively unloading some of the fuel rods stored in the fuel rod storage unit and transferring the fuel rods to the feeding unit, a fuel rod assembly lifter which is disposed parallel to the feeding unit, and a controller controlling driving of the fuel rod loading unit, the feeding unit, and the fuel rod unloading unit.
摘要翻译：公开了一种用于核燃料组件的燃料棒自动装载装置，其将燃料棒在燃料棒壳中以束装配以将燃料棒组装到核燃料组件中。燃料棒自动装载装置包括燃料棒存储单元，其具有用于燃料棒的多个叠置的机架，燃料棒装载单元升高/降低到机架并传送燃料棒;馈送单元，将燃料棒放置成行;以及将燃料棒装载到燃料棒壳中，燃料棒卸载单元选择性地卸载存储在燃料棒存储单元中的一些燃料棒，并将燃料棒传送到进料单元;燃料棒组件升降器，进给单元，以及控制燃料棒装载单元，进给单元和燃料棒卸载单元的驱动的控制器。

10. 发明授权

US08756966B2 Pilger die and pilger mandrel for manufacturing dashpot tube for nuclear fuel assembly and method of manufacturing the pilger die and the pilger mandrel 有权
标题翻译：用于制造用于核燃料组件的缓冲器管的皮尔模具和打孔器心轴以及制造打孔器模头和打孔器心轴的方法
公开(公告)号：US08756966B2
公开(公告)日：2014-06-24
申请号：US13117981
申请日：2011-05-27
申请人： Sun Doo Kim , Chan Hyun Park , In Kyu Kim , Ki Bum Park , Seung Hwan Lee
发明人： Sun Doo Kim , Chan Hyun Park , In Kyu Kim , Ki Bum Park , Seung Hwan Lee
IPC分类号： B21B17/02
CPC分类号： G21C21/00 , B21B21/00
摘要： A pilger die and a pilger mandrel which are used to produce a dashpot tube which can be used in a nuclear fuel assembly having an outer diameter of 31.75 mm or less and an inner diameter 25.654 mm or less, by processing a reduced expression zirconium alloy tube in two pilgering processes (a first step pass and a second step pass) using a single pilgering apparatus. Furthermore, provided are methods of manufacturing the pilger die and the pilger mandrel, and the dashpot tube for the nuclear fuel assembly. The dashpot tube can be manufactured by the single pilgering apparatus provided with the pilger die and the pilger mandrel.
摘要翻译：一种用于制造可用于外径为31.75mm或更小，内径为25.654mm或更小的核燃料组件的缓冲器管的冲锋枪和打孔器，通过加工减少表示的锆合金管在两个通气处理（第一步通过和第二步骤步骤）中使用单个捣固装置。此外，提供了制造穿孔器模具和打孔器心轴的方法以及用于核燃料组件的缓冲器管。缓冲器管可以由设置有打孔器模头和打孔器心轴的单个穿孔装置制造。

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