公开(公告)号：US20240212872A1

公开(公告)日：2024-06-27

申请号：US18538496

申请日：2023-12-13

申请人： COMMISSARIAT A L'ENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES

发明人： Alessandro PANTANO ,  Philippe AMPHOUX

IPC分类号： G21C15/18 ,  G21C1/03 ,  G21C15/28

CPC分类号： G21C15/185 ,  G21C1/03 ,  G21C15/28

摘要： A nuclear reactor incorporating a DHR system that simultaneously guarantees removal of decay heat as soon as the reactor is shut down; removal of heat through the primary vessel and then behind the secondary vessel; improved and entirely passive (Seebeck effect) heat removal by thermal conduction through fins distributed around the primary vessel in the guard gap and which, when pivoted into their deployed position, form a kind of thermal bridge between the primary and secondary vessels.

公开(公告)号：US20230352201A1

公开(公告)日：2023-11-02

申请号：US17923036

申请日：2021-05-07

申请人： WITKOWITZ ATOMICA A.S.

发明人： Frantisek CERMAK ,  Bronislav KULIKOV ,  Martin GROCH ,  David CHROBOK ,  Martin ULCAK

IPC分类号： G21D5/02 ,  G21C15/28 ,  G21C17/112 ,  G21C9/033

CPC分类号： G21D5/02 ,  G21C15/28 ,  G21C17/112 ,  G21C9/033 ,  G21D3/001

摘要： An energy source using low-enriched nuclear fuel to produce heat contains a compact transportable pressure vessel containing a cylinder with the core with heating element formed by nuclear fuel and continually agitated by a directed flow of heat-exchange liquid, to which a second pressure vessel is connected with a closed water bath circuit and a heat exchanger for production of steam, while the compact transportable pressure vessel can be placed in a space selected from the group underground concrete space with stainless steel lining, sea-river vessel and container modification for road and/or railway transport.

公开(公告)号：US11798694B2

公开(公告)日：2023-10-24

申请号：US17076309

申请日：2020-10-21

申请人： TerraPower, LLC

发明人： Anselmo T. Cisneros, Jr. ,  Charles Gregory Freeman ,  Kevin Kramer ,  Jeffery F. Latkowski

IPC分类号： G21C7/28 ,  G21C3/54 ,  G21C7/22 ,  G21C7/27 ,  G21C1/02 ,  G21C1/22 ,  G21C15/28 ,  G21C1/32 ,  G21C11/06 ,  G21C15/02

CPC分类号： G21C7/28 ,  G21C3/54 ,  G21C7/22 ,  G21C7/27 ,  G21C1/026 ,  G21C1/22 ,  G21C1/326 ,  G21C11/06 ,  G21C15/02 ,  G21C15/28 ,  Y02E30/30

摘要： A molten fuel salt nuclear reactor core assembly including a fluid neutron reflecting material defining a fast spectrum fuel volume configured to breed fissile fuel from fertile fuel, a first inlet channel, and a first outlet channel through which cooled molten fuel salt can enter and heated molten fuel salt can exit the fast spectrum fuel volume. The core assembly also includes a set of neutron absorbing members sized to fit within the fast spectrum fuel volume. The set of neutron absorbing members define a thermal spectrum fuel volume for a fission reaction of the fissile fuel, a second inlet channel, and a second outlet channel through which cooled molten fuel salt can enter and heated molten fuel salt can exit the thermal spectrum fuel volume.

公开(公告)号：US20160260509A1

公开(公告)日：2016-09-08

申请号：US15030578

申请日：2014-11-25

申请人： KOREA ATOMIC ENERGY RESEARCH INSTITUTE

发明人： Young Soo KIM ,  Young In KIM ,  Cheon Tae PARK ,  Ju Hyeon YOON ,  Tae Wan KIM ,  Keung Koo KIM ,  Jae Joo HA

IPC分类号： G21C15/24 ,  G21C15/18 ,  G21D1/04

CPC分类号： G21C15/24 ,  G21C1/322 ,  G21C1/324 ,  G21C1/326 ,  G21C1/328 ,  G21C15/182 ,  G21C15/243 ,  G21C15/247 ,  G21C15/28 ,  G21C2015/185 ,  G21D1/04 ,  G21Y2002/50 ,  G21Y2004/30 ,  Y02E30/40

摘要： The present invention discloses a nuclear reactor coolant pump that does not rely on an electric motor, but is operated by means of driving force generated inside a nuclear power plant, so a to be capable of maintaining the safety of the nuclear reactor when the nuclear reactor is operating normally and also in the event of an accident in the nuclear reactor. The nuclear reactor coolant pump comprises: a pump impeller rotatably installed in a first fluid passage of a nuclear reactor coolant system to circulate a first fluid inside the nuclear reactor coolant system; a drive unit receiving steam from a steam generator to generate driving force to rotate the pump impeller, and rotating about the same rotating shaft as the pump impeller to transfer the generated driving force to the pump impeller; and a steam supplying unit forming a passage between the steam generator and the drive unit to supply at least a portion of the steam released from the steam generator to the drive unit.

摘要翻译： 本发明公开了一种核反应堆冷却剂泵，其不依赖于电动机，而是通过在核电厂内产生的驱动力来操作，因此当核反应堆能够保持核反应堆的安全性时 正常运行，并且在核反应堆发生事故时也是如此。 核反应堆冷却剂泵包括：可旋转地安装在核反应堆冷却剂系统的第一流体通道中的泵叶轮，以使核反应堆冷却剂系统内的第一流体循环; 驱动单元，其接收来自蒸汽发生器的蒸汽，以产生用于使所述泵叶轮旋转的驱动力，并且围绕与所述泵叶轮相同的旋转轴旋转以将所产生的驱动力传递到所述泵叶轮; 以及蒸汽供给单元，其形成在所述蒸汽发生器和所述驱动单元之间的通道，以将从所述蒸汽发生器释放的蒸汽的至少一部分供给到所述驱动单元。

公开(公告)号：US09305669B2

公开(公告)日：2016-04-05

申请号：US14251894

申请日：2014-04-14

申请人： Searete LLC

发明人： Roderick A. Hyde ,  Muriel Y. Ishikawa ,  Nathan P. Myhrvold ,  Lowell L. Wood, Jr.

IPC分类号： G21C15/243 ,  G21C15/247 ,  G21C15/00 ,  G21C1/02 ,  G21C7/02 ,  G21C7/06 ,  G21C15/04 ,  G21D3/00 ,  G21C15/28

CPC分类号： G21C15/243 ,  G21C1/026 ,  G21C7/02 ,  G21C7/06 ,  G21C15/00 ,  G21C15/04 ,  G21C15/247 ,  G21C15/28 ,  G21D3/00 ,  Y02E30/34 ,  Y02E30/39

摘要： Exemplary embodiments provide automated nuclear fission reactors and methods for their operation. Exemplary embodiments and aspects include, without limitation, re-use of nuclear fission fuel, alternate fuels and fuel geometries, modular fuel cores, fast fluid cooling, variable burn-up, programmable nuclear thermostats, fast flux irradiation, temperature-driven surface area/volume ratio neutron absorption, low coolant temperature cores, refueling, and the like.

摘要翻译： 示例性实施例提供了自动化核裂变反应器及其操作方法。 示例性实施例和方面包括但不限于重新使用核裂变燃料，替代燃料和燃料几何形状，模块化燃料芯，快速流体冷却，可变燃烧，可编程核恒温器，快速通量照射，温度驱动表面积/ 体积比中子吸收，低冷却剂温度核心，加油等。

公开(公告)号：US20150179288A1

公开(公告)日：2015-06-25

申请号：US14374525

申请日：2013-07-01

申请人： Zhengwei Li

发明人： Zhengwei Li

IPC分类号： G21C3/04

CPC分类号： G21C3/04 ,  G21C1/07 ,  G21C3/58 ,  G21C3/626 ,  G21C15/28 ,  Y02E30/36 ,  Y02E30/38

摘要： The present invention claims a nuclear reactor which can package the nuclear fuel and the coolant together in a spherical solid and transfer heat to the steam generator through the flow of spherical solid between the reactor vessel (1) and the steam generator (2) by two sets of mechanical transmission systems (4). The reactor is featured in high inherent safety, high outlet temperature parameter and full use of the nuclear fuel. It can be applied in many fields, such as power generation, hydrogen production, heating, liquefaction and gasification of coal and so on.

摘要翻译： 本发明要求一种核反应堆，其可以将核燃料和冷却剂一起包装在球形固体中，并且通过反应器容器（1）和蒸汽发生器（2）之间的球形固体的流动将热传递到蒸汽发生器两个 机组传动系（4）。 反应堆具有高固有安全性，高出口温度参数和充分利用核燃料的特点。 可应用于发电，氢气生产，采暖，煤化液化，煤化等许多领域。

公开(公告)号：US20150155060A1

公开(公告)日：2015-06-04

申请号：US14407548

申请日：2013-06-13

申请人： ATOMIC ENERGY OF CANADA LIMITED / ÉNERGIE ATOMIQUE DU CANADA LIMITÉE

发明人： Metin Yetisir ,  Michel Gaudet ,  David Bruce Rhodes ,  James Mitchell King ,  William T. Diamond ,  Jintong Li

IPC分类号： G21C3/322 ,  G21C1/08 ,  G21C3/336

CPC分类号： G21C3/322 ,  G21C1/08 ,  G21C1/20 ,  G21C3/32 ,  G21C3/324 ,  G21C3/328 ,  G21C3/336 ,  G21C5/12 ,  G21C13/02 ,  G21C15/06 ,  G21C15/22 ,  G21C15/28 ,  Y02E30/38

摘要： A nuclear fuel bundle may include a first end face and a second end face axially spaced apart from the first end face and a plurality of elongate nuclear fuel elements supported by at least one spacer. The plurality of fuel elements and spacer being sized to be removably received within the fuel channel assembly. A coolant tube passage may extend axially through the fuel bundle between a first aperture in the first end face and a second aperture in the second end face. The coolant tube passage sized to removably receive a coolant fluid downflow tube provided in the fuel channel assembly. The tube passage extending from the first end face to the second end face to enable the coolant fluid downflow tube to pass through the fuel bundle.

摘要翻译： 核燃料束可以包括第一端面和与第一端面轴向间隔开的第二端面和由至少一个间隔件支撑的多个细长核燃料元件。 多个燃料元件和间隔件的尺寸设计成可移除地容纳在燃料通道组件内。 冷却剂管通道可以在第一端面中的第一孔和第二端面中的第二孔之间轴向延伸穿过燃料束。 冷却剂管通道的尺寸设计成可移除地容纳设置在燃料通道组件中的冷却剂流体下流管。 所述管通道从所述第一端面延伸到所述第二端面，以使所述冷却剂流体下流管能够通过所述燃料束。

公开(公告)号：US08731133B2

公开(公告)日：2014-05-20

申请号：US12280286

申请日：2007-02-22

申请人： Ronald H. Baney ,  James S. Tulenko ,  Kevin W. Powers

发明人： Ronald H. Baney ,  James S. Tulenko ,  Kevin W. Powers

IPC分类号： G21C15/28 ,  G21C1/01 ,  G21C15/00 ,  G21C1/00

CPC分类号： G21C15/28 ,  G21Y2002/201 ,  G21Y2002/304 ,  G21Y2004/302 ,  G21Y2004/40 ,  Y02E30/40

摘要： A pressurized water nuclear reactor (PWNR) includes a core having a containment shield surrounding a reactor vessel having fuel assemblies that contain fuel rods filled with fuel pellets, and control rods, and a steam generator thermally coupled to the reactor vessel. A flow loop includes the steam generator, a turbine, and a condenser, and a pump for circulating a water-based heat transfer fluid in the loop. The heat transfer fluid includes a plurality of nanoparticles having at least one carbon allotrope or related carbon material dispersed therein, such as diamond nanoparticles.

摘要翻译： 加压水核反应堆（PWNR）包括具有围绕反应器容器的容纳屏蔽的芯，其具有燃料组件，燃料组件包含填充有燃料颗粒的燃料棒，以及控制棒和与反应器容器热耦合的蒸汽发生器。 流动回路包括蒸汽发生器，涡轮机和冷凝器，以及用于在循环中循环水基传热流体的泵。 传热流体包括具有分散在其中的至少一种碳同素异形体或相关碳材料的多种纳米颗粒，例如金刚石纳米颗粒。

公开(公告)号：US20140102481A1

公开(公告)日：2014-04-17

申请号：US14104104

申请日：2013-12-12

申请人： AREVA GMBH

发明人： UTE RAMMINGER ,  JOERG FANDRICH ,  FERNANDO-MARIO ROUMIGUIERE

IPC分类号： B08B9/032

CPC分类号： B08B9/032 ,  C23F11/141 ,  F22B37/483 ,  F22B37/56 ,  G21C15/28 ,  G21C17/0225 ,  G21D1/00 ,  Y02E30/40

摘要： A method for conditioning the circulatory system (1) of a power plant is especially suited for a nuclear power plant. An amine, which is a film-forming agent, is metered into the working medium circulating in the circulatory system. The film-forming agent forms a hydrophobic film on the surfaces of the circulatory system. During the process, the concentration of the film-forming agent is monitored in at least one measuring point by way of measurement, and metering of the film-forming agent is stopped once its concentration in the working medium has reached a value of 1 ppm to 2 ppm in at least one measuring point M1.

摘要翻译： 用于调节发电厂的循环系统（1）的方法特别适用于核电站。 胺，其是成膜剂，计量加入在循环系统中循环的工作介质。 成膜剂在循环系统的表面形成疏水膜。 在该过程中，通过测量在至少一个测量点监测成膜剂的浓度，一旦成膜剂在工作介质中的浓度达到1ppm至 在至少一个测量点M1中为2ppm。

公开(公告)号：US20140029712A1

公开(公告)日：2014-01-30

申请号：US13234578

申请日：2011-09-16

申请人： Catherine Procik DULKA ,  Young Jin Kim ,  Rajasingh Schwartz Israel ,  David Wesley Sandusky ,  Kevin H. Janora ,  Peter W. Brown ,  Tianji Zhao

发明人： Catherine Procik DULKA ,  Young Jin Kim ,  Rajasingh Schwartz Israel ,  David Wesley Sandusky ,  Kevin H. Janora ,  Peter W. Brown ,  Tianji Zhao

IPC分类号： C23C28/04 ,  G21C19/30

CPC分类号： C23C28/044 ,  C23C16/0272 ,  C23C16/405 ,  C23C28/042 ,  C23C30/00 ,  G21C15/28 ,  G21C19/30 ,  Y02E30/40

摘要： Example embodiments relate to a method and apparatus for reducing electrostatic deposition of charged particles on wetted surfaces that are exposed, periodically or substantially continuously, to high velocity fluid flow within a coolant flow path in a nuclear reactor. The method may include depositing a first or base dielectric layer and a second or outer dielectric layer on a conductive surface that forms a portion of a high velocity flow path to attain the apparatus. The first dielectric layer material is selected to provide improved adhesion and insulation to the conductive surface and the second dielectric layer material is selected to provide suitable adhesion to the first dielectric layer and improved corrosion and/or mechanical resistance in the anticipated operating environment.

摘要翻译： 示例性实施例涉及一种用于减少暴露，周期性或基本连续的润湿表面上的带电粒子在核反应堆内的冷却剂流动路径内的高速流体流动的静电沉积的方法和装置。 该方法可以包括在形成高速流动路径的一部分的导电表面上沉积第一或基底电介质层和第二或外部电介质层以获得该装置。 选择第一介电层材料以提供对导电表面的改进的粘合性和绝缘性，并且选择第二介电层材料以在预期的操作环境中提供对第一介电层的合适的粘合性和改善的腐蚀和/或机械阻力。