公开(公告)号：US20190311816A1

公开(公告)日：2019-10-10

申请号：US16096228

申请日：2017-04-25

申请人： Clear Inc.

发明人： Osao SUMITA ,  Isao UENO ,  Takehiko YOKOMINE

IPC分类号： G21C1/02 ,  G21C3/02 ,  G21C7/02 ,  G21C7/28 ,  G21C7/30

摘要： Engineering safety systems always have insufficiencies in terms of safety, and construction of a complete safety system causes installation costs for the safety system to become very high. Provided is a small nuclear reactor HAVING a load following control system in which a nuclear reaction in the nuclear reactor is naturally controlled by the generated heat, the small nuclear reactor being provided with: a reactor core provided with a plurality of fuel assemblies of metallic fuels containing uranium (U) 235, 238 and/or plutonium (Pu) 239; a primary coolant comprising a liquid metal; a neutron reflector which serves to control the nuclear reaction in the reactor core and is disposed to enclose the periphery of the reactor core; and a mechanism which contains a liquid or a gas having an expansion coefficient greater than that of the neutron reflector, converts the coefficient of volumetric expansion into an amount of linear thermal expansion, and, by using same, moves the neutron reflector or adjusts the spacing between the plurality of fuel assemblies.

公开(公告)号：US10163534B2

公开(公告)日：2018-12-25

申请号：US14605831

申请日：2015-01-26

申请人： TerraPower, LLC

发明人： Micah Hackett ,  Ryan Latta ,  Samuel J. Miller ,  Gary Povirk ,  Mark R. Werner ,  Cheng Xu

IPC分类号： G21D3/00 ,  G21C3/04 ,  G21C3/02 ,  G21C3/06

摘要： A computerized system for modeling reactor fuel element and fuel design to determine the thermo-mechanical performance thereof includes a processor coupled to memory, the memory configuring the processor to execute a fuel element analysis and an output configured to communicate data that describes the thermo-mechanical performance of the fuel element and fuel design based on the fuel element performance analysis. The processor is configured to estimate the mechanical behavior of a fuel by creating separate variables for the open and closed porosity components, conducting a routine for the open and closed porosity components that processes the current state of the fuel and updates the current state and forces of each of the open and closed porosity components, and combining the updates for the current state and forces according to a weighting; and estimate the creep and swelling behavior of a cladding.

公开(公告)号：US08920871B1

公开(公告)日：2014-12-30

申请号：US14011726

申请日：2013-08-27

申请人： Sandia Corporation

发明人： Dennis L. Youchison ,  Brian E. Williams ,  Robert E. Benander

IPC分类号： G21C3/02 ,  G21C3/58 ,  G21C21/02

CPC分类号： G21C21/02 ,  G21C3/58 ,  Y02E30/33 ,  Y02E30/38

摘要： Porous nuclear fuel elements for use in advanced high temperature gas-cooled nuclear reactors (HTGR's), and to processes for fabricating them. Advanced uranium bi-carbide, uranium tri-carbide and uranium carbonitride nuclear fuels can be used. These fuels have high melting temperatures, high thermal conductivity, and high resistance to erosion by hot hydrogen gas. Tri-carbide fuels, such as (U,Zr,Nb)C, can be fabricated using chemical vapor infiltration (CVI) to simultaneously deposit each of the three separate carbides, e.g., UC, ZrC, and NbC in a single CVI step. By using CVI, the nuclear fuel may be deposited inside of a highly porous skeletal structure made of, for example, reticulated vitreous carbon foam.

摘要翻译： 用于先进高温气冷核反应堆（HTGR）的多孔核燃料元件及其制造工艺。 可以使用高级铀二碳化物，三碳酸铀和碳氮化铀核燃料。 这些燃料具有高熔融温度，高导热性和高耐热氢气侵蚀性。 可以使用化学气相渗透（CVI）制造三碳化碳燃料，例如（U，Zr，Nb）C，以在单个CVI步骤中同时沉积三种分离的碳化物，例如UC，ZrC和NbC中的每一种。 通过使用CVI，核燃料可以沉积在由例如网状玻璃碳泡沫制成的高度多孔的骨架结构的内部。

公开(公告)号：US08891724B2

公开(公告)日：2014-11-18

申请号：US12559059

申请日：2009-09-14

申请人： Hyung-Kyu Kim ,  Jong-Hun Kim ,  Dae-Ho Kim ,  Kun-Woo Song ,  Kyung-Ho Yoon ,  Young-Ho Lee ,  Jae-Yong Kim ,  Kang-Hee Lee

发明人： Hyung-Kyu Kim ,  Jong-Hun Kim ,  Dae-Ho Kim ,  Kun-Woo Song ,  Kyung-Ho Yoon ,  Young-Ho Lee ,  Jae-Yong Kim ,  Kang-Hee Lee

IPC分类号： G21C3/00 ,  G21C3/02 ,  G21C3/10 ,  G21C21/02

CPC分类号： G21C3/02 ,  G21C3/10 ,  G21C21/02 ,  Y02E30/40

摘要： A dual-cooled nuclear fuel rod and a method of manufacturing the same are provided. The nuclear fuel rod includes an outer cladding tube having a circular cross section, an inner cladding tube having an outer diameter smaller than an inner diameter of the outer cladding tube, and a length longer than the outer cladding tube, and located in parallel in the outer cladding tube, a pellet charged in a space between the outer and inner cladding tubes and generating energy by nuclear fission, and first and second end plugs coupling opposite ends of the outer cladding tube to stepped outer joints formed on outer circumferences of first ends thereof and coupling opposite ends of the inner cladding tube to stepped inner joints formed on inner circumferences of the first ends thereof.

摘要翻译： 提供了双冷核燃料棒及其制造方法。 核燃料棒包括具有圆形横截面的外包层管，外包层的外径小于外包层管的内径，长度比外包层管长，并且平行于 外包层管，填充在外包层管和内包壳管之间的空间中并通过核裂变产生能量的颗粒，以及将外包层管的相对端连接到形成在其第一端的外周上的阶梯式外接头的第一和第二端塞 并且将内包层管的相对端连接到形成在其第一端的内周上的阶梯式内接头。

公开(公告)号：US20120263271A1

公开(公告)日：2012-10-18

申请号：US13086504

申请日：2011-04-14

申请人： Yuriy Aleshin ,  David B. Mitchell

发明人： Yuriy Aleshin ,  David B. Mitchell

IPC分类号： G21C3/30 ,  G21C3/02

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.

摘要翻译： 核燃料芯片设计是具有更大半径或圆锥形端部的圆柱形轴向轮廓，使得颗粒端部处的直径略小于在中间和在正常操作条件下的直径，在端部处的直径 几乎和中间一样。 优选地，在颗粒的轴向端部处具有短的倒角。

公开(公告)号：US20110170653A1

公开(公告)日：2011-07-14

申请号：US13119469

申请日：2009-09-18

申请人： Julien Cabrero ,  René Pailler ,  Fabienne Audubert

发明人： Julien Cabrero ,  René Pailler ,  Fabienne Audubert

IPC分类号： G21C3/02 ,  G21C3/06

CPC分类号： G21C3/07 ,  C04B35/5611 ,  C04B35/5615 ,  C04B35/5622 ,  C04B35/6286 ,  C04B35/62873 ,  C04B35/62884 ,  C04B35/62894 ,  C04B35/62897 ,  C04B35/6325 ,  C04B35/806 ,  C04B2235/3232 ,  C04B2235/3244 ,  C04B2235/3418 ,  C04B2235/3813 ,  C04B2235/3826 ,  C04B2235/444 ,  C04B2235/5244 ,  C04B2235/5252 ,  C04B2235/614 ,  C04B2235/77 ,  G21C3/20 ,  G21C21/02 ,  Y02E30/40

摘要： The invention relates to a nuclear fuel cladding totally or partially made of a composite material with a ceramic matrix containing silicon carbide (SiC) fibers as a matrix reinforcement and an interphase layer provided between said matrix and said fibers, the matrix including at least one carbide selected from titanium carbide (TiC), zirconium carbide (ZrC), or ternary titanium silicon carbide (Ti3SiC2).When irradiated and at temperatures of between 800° C. and 1200° C., said cladding can mechanically maintain the nuclear fuel within the cladding while enabling optimal thermal-energy transfer towards the coolant.The invention also relates to a method for making the nuclear fuel cladding.

摘要翻译： 本发明涉及一种全部或部分由复合材料制成的核燃料包层，该复合材料具有含有碳化硅（SiC）纤维作为基质增强层的陶瓷基体和在所述基质和所述纤维之间提供的界面层，该基质包括至少一种碳化物 选自碳化钛（TiC），碳化锆（ZrC）或三元钛碳化硅（Ti 3 SiC 2）。 当照射并且在800℃和1200℃之间的温度下时，所述包层可以将核燃料机械地保持在包壳内，同时能够使朝向冷却剂的最佳热能传递。 本发明还涉及制造核燃料包层的方法。

公开(公告)号：US20110080987A1

公开(公告)日：2011-04-07

申请号：US12904781

申请日：2010-10-14

申请人： Souichi WATANABE ,  Hironori Kumanomido ,  Ishi Mitsuhashi ,  Satoshi Sugahara ,  Makoto Ueda

发明人： Souichi WATANABE ,  Hironori Kumanomido ,  Ishi Mitsuhashi ,  Satoshi Sugahara ,  Makoto Ueda

IPC分类号： G21C3/02 ,  G21C3/07 ,  G21G4/00

CPC分类号： G21C3/62 ,  G21C3/623 ,  G21C21/02 ,  Y02E30/38

摘要： Among fuel rods constituting a fuel assembly, Gd compound oxide is added to low Gd containing fuel rods that containing uranium dioxide of which enrichment exceeds 5 wt %. The Gd compound oxide is oxide of gadolinium and rare earth element A except for gadolinium and is expressed as a chemical formula A1-xGdxO2-0.5x or a chemical formula A1-xGdxO1.5. As the rare earth element A, cerium Ce, lanthanum La or erbium Er can be used.

摘要翻译： 在构成燃料组件的燃料棒中，将Gd复合氧化物加入到含有浓度超过5重量％的二氧化铀的低Gd含量燃料棒中。 Gd复合氧化物是除钆之外的钆和稀土元素A的氧化物，以化学式A1-xGdxO2-0.5x或化学式A1-xGdxO1.5表示。 作为稀土元素A，可以使用铈Ce，镧La或铒Er。

公开(公告)号：US6068966A

公开(公告)日：2000-05-30

申请号：US874301

申请日：1997-06-13

申请人： Atsushi Koga

发明人： Atsushi Koga

IPC分类号： G21C3/02 ,  B23K26/00 ,  B41M5/24 ,  G06K1/12 ,  B23K26/02

CPC分类号： G06K1/121 ,  Y10S430/146

摘要： The bar-code printing method of the present invention comprises a step of irradiating the circumferential surface of a metal tube with laser beams so as to make at least one group of thin elementary lines arranged in parallel with each other at intervals. The width of the intervals is determined so that each group of elementary lines can be detected as one of the thick lines contained in the bar-code.

摘要翻译： 本发明的条形码印刷方法包括以下步骤：用激光束照射金属管的圆周表面，以使至少一组薄的基本线彼此间隔布置。 确定间隔的宽度，使得每一组基本线可以被检测为条形码中包含的粗线之一。

公开(公告)号：US5477023A

公开(公告)日：1995-12-19

申请号：US53119

申请日：1993-04-23

申请人： Urban A. Schneider ,  John P. Mortara ,  Alfred C. Owens ,  Douglas L. Mann ,  Micki M. Baumert ,  Robert D. Sigman

发明人： Urban A. Schneider ,  John P. Mortara ,  Alfred C. Owens ,  Douglas L. Mann ,  Micki M. Baumert ,  Robert D. Sigman

IPC分类号： B23K26/00 ,  B23K26/02 ,  B23K26/10 ,  B23K26/12 ,  G06K1/12 ,  G21C3/02 ,  G21C17/00

CPC分类号： G06K1/126 ,  B23K26/10 ,  B23K26/127 ,  B23K26/1462 ,  G21C17/00 ,  B41M5/24 ,  G21Y2002/40 ,  Y02E30/39

摘要： System and method for engraving an image on a workpiece, such as a nuclear steam generator tubesheet. The system includes a laser assembly for generating a pulsed laser beam to engrave the image adjacent a target position on the workpiece. A positioning mechanism is connected to the laser assembly for positioning the laser assembly with reference to the target position. A controller is electrically connected to the positioning mechanism for controlling the positioning mechanism in order to controllably position the laser assembly at the target position and for verifying the image engraved at the target position. A computer is electrically connected to the controller for receiving the verified image. The computer is also electrically connected to the laser assembly for operating the laser assembly so that the laser beam emitted thereby engraves the image on the tubesheet at the target position.

摘要翻译： 用于在工件上雕刻图像的系统和方法，例如核蒸汽发生器管板。 该系统包括用于产生脉冲激光束以在工件上邻近目标位置雕刻图像的激光组件。 定位机构连接到激光组件，用于相对于目标位置定位激光组件。 控制器电连接到定位机构，用于控制定位机构，以便将激光组件可控地定位在目标位置，并用于验证雕刻在目标位置的图像。 计算机电连接到控制器以接收经验证的图像。 计算机还电连接到用于操作激光组件的激光组件，使得所发射的激光束在目标位置处雕刻在管板上的图像。

公开(公告)号：US4822559A

公开(公告)日：1989-04-18

申请号：US95095

申请日：1987-09-10

申请人： Hilding Mogard

发明人： Hilding Mogard

IPC分类号： G21C3/06 ,  G21C3/02 ,  G21C3/16 ,  G21C3/18 ,  G21C3/28 ,  G21C3/00

CPC分类号： G21C3/16 ,  G21Y2002/104 ,  G21Y2002/201 ,  G21Y2002/303 ,  G21Y2004/30 ,  Y02E30/40

摘要： A nuclear fuel element for use in power-producing nuclear reactors, comprising a circular metal cladding tube containing sintered cylindrical oxide fuel pellets, the tube being formed internally with a substantially cylindrical inner surface having a plurality of longitudinal ribs forming axially extending channels. The fuel pellets have chamfered endfaces creating toroidal spaces at the adjoining ends of the fuel pellets, the ratio of axial channel to toroidal space volumes including any pellet dishing being at most about one (1);a process for the manufacture of such fuel element.

摘要翻译： 一种用于发电核反应堆的核燃料元件，包括含有烧结的圆柱形氧化物燃料颗粒的圆形金属包层管，内部形成有具有形成轴向延伸通道的多个纵向肋的基本上圆柱形的内表面。 燃料颗粒具有倒角的端面，在燃料颗粒的相邻端产生环形空间，轴向通道与环形空间体积的比率包括任何颗粒凹陷至多约一（1）; 用于制造这种燃料元件的方法。