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1. 发明公开

US20240203613A1 MOLTEN SALT NUCLEAR REACTOR, OF FAST NEUTRON TYPE, THE PRIMARY CIRCUIT OF WHICH CIRCULATES BY NATURAL CONVECTION 审中-公开
公开(公告)号：US20240203613A1
公开(公告)日：2024-06-20
申请号：US18542987
申请日：2023-12-18
申请人： COMMISSARIAT A L'ENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES
发明人： Guillaume CAMPIONI , Antoine GERSCHENFELD , Vincent PASCAL , Yannick GORSSE
IPC分类号： G21C3/54 , G21C1/02 , G21C11/06 , G21C19/40
CPC分类号： G21C3/54 , G21C1/02 , G21C11/06 , G21C19/40
摘要： A molten salt nuclear reactor of the fast neutron reactor type may be designed as a reactor vessel free of moderator or at the very least of a moderator enabling a reactor to be qualified as a thermal neutron reactor, having a shape exhibiting symmetry of revolution surrounded by another vessel at the periphery of the reactor vessel thereby delimiting a guard gap filled with an inert liquid salt which acts as a coolant for removing the decay heat from the reactor by conduction through the reactor vessel.

2. 发明公开

US20240153652A1 Core of Fast Reactor and Method of Operating Fast Reactor 审中-公开
公开(公告)号：US20240153652A1
公开(公告)日：2024-05-09
申请号：US18507246
申请日：2023-11-13
申请人： Hatachi-GE Nuclear Energy, Ltd.
发明人： Koji FUJIMURA , Kazuhiro Fujimata , Suo Fuchita , Junichi Miwa
IPC分类号： G21C1/02 , G21C1/03 , G21C3/28
CPC分类号： G21C1/02 , G21C1/03 , G21C3/28 , G21C7/28
摘要： A core of a fast reactor including a sodium plenum installed above a core fuel, which is capable of reliably reducing a void reactivity, and an operation method thereof are provided. The core of a fast reactor including the sodium plenum installed above the core fuel is characterized in that a tip of a primary control rod is inserted into a core fuel region, and a tip of a backup control rod is arranged above an upper end of the core fuel region for operation.

3. 发明授权

US10030865B2 System for passive heat removal from the pressurized water reactor through the steam generator 有权
公开(公告)号：US10030865B2
公开(公告)日：2018-07-24
申请号：US15532895
申请日：2015-11-16
申请人： JOINT-STOCK COMPANY SCIENTIFIC RESEARCH AND DESIGN INSTITUTE FOR ENERGY TECHNOLOGIES ATOMPROEKT (JSC “ATOMPROEKT”)
发明人： Vladimir Victorovich Bezlepkin , Valdimir Grigorievich Sidorov , Sergey Borisovich Alekseev , Sergey Victorovich Svetlov , Vladimir Olegovich Kukhtevich , Sergey Evgenivich Semashko , Teymuraz Georgievich Vardanidze , Igor Mihaylovich Ivkov
IPC分类号： G21C15/18 , F22B1/02
CPC分类号： F22B1/023 , F22B1/08 , F28D1/0206 , F28D1/047 , F28D1/05316 , F28D2021/0054 , F28F9/26 , G21C1/02 , G21C15/18
摘要： The invention relates to the nuclear energy field, including systems for passive heat removal from the pressurized water reactor through the steam generator. The invention increases heat removal efficiency, coolant flow stability and system reliability. The system includes at least one coolant circulation circuit comprising a steam generator and a section heat exchanger above the steam generator in the cooling water supply tank and connected to the steam generator through the inlet and outlet pipelines. The heat exchanger is divided into parallel sections wherein L/D≤20, L being the half-section length, D being the header bore, and includes an upper and lower header interconnected by heat-exchange tubes, startup valves with different nominal bores are installed on the outlet pipeline. The inlet and outlet pipeline sections of the circulation circuit comprise a set of branched parallel pipelines individually connected to each of the above heat exchanger sections.

4. 发明申请

US20170337992A1 SMALL, FAST NEUTRON SPECTRUM NUCLEAR POWER PLANT WITH A LONG REFUELING INTERVAL 审中-公开
公开(公告)号：US20170337992A1
公开(公告)日：2017-11-23
申请号：US15583838
申请日：2017-05-01
申请人： Advanced Reactor Concepts LLC
发明人： Leon C. Walters
IPC分类号： G21C1/02 , G21C9/027 , G21C5/06 , G21C19/20 , G21C7/08
CPC分类号： G21C1/02 , G21C5/06 , G21C7/08 , G21C9/027 , G21C19/205 , Y02E30/34 , Y02E30/39
摘要： Nuclear reactor systems and methods are described having many unique features tailored to address the special conditions and needs of emerging markets. The fast neutron spectrum nuclear reactor system may include a reactor having a reactor tank. A reactor core may be located within the reactor tank. The reactor core may include a fuel column of metal or cermet fuel using liquid sodium as a heat transfer medium. A pump may circulate the liquid sodium through a heat exchanger. The system may include a balance of plant with no nuclear safety function. The reactor may be modular, and may produce approximately 100 MWe.

5. 发明申请

US20160351278A1 Active Zone Of Lead-Cooled Fast Reactor 有权
标题翻译：铅冷快堆的主动区
公开(公告)号：US20160351278A1
公开(公告)日：2016-12-01
申请号：US15112578
申请日：2014-11-27
申请人： STATE ATOMIC ENERGY CORPORATION "ROSATOM" ON BEHALF OF THE RUSSIAN FEDERATION
发明人： Viktor Nikolaevich LEONOV , Aleksandr Viktorovich LOPATKIN , Elena Aleksandrovna RODINA , Yuriy Vasilievich CHERNOBROVKIN
IPC分类号： G21C3/04 , G21C3/58 , G21C5/14 , G21C1/02
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 includes a homogeneous uranium-plutonium nitride fuel, the mass fraction of which is a minimum 0.305, and consists of central, intermediate and peripheral parts which form fuel assemblies comprising fuel elements with geometrically identical shells but differing heights. The radial distribution of the fuel across the volume of the active zone has a stepped shape. The radius of the central part is from 0.4 to 0.5 of the effective active zone radius, while the height of the fuel column in the fuel elements in the central part is from 0.5 to 0.8 of the height of the fuel column in the peripheral part. The heights of the fuel columns forming a stepped intermediate part for diameters ranging from 0.5 to 0.85 of the effective active zone diameter are within the range from 0.55 to 0.9 of the height of the fuel column in the peripheral part.
摘要翻译：活性区域包括均质的铀 - 钚氮化物燃料，其质量分数最小为0.305，并且由中心部分，中间部分和周边部分组成，其形成燃料组件，其包括具有几何相同壳体但不同高度的燃料元件。燃料在活性区域的体积上的径向分布具有阶梯形状。中心部分的半径为有效活动区域半径的0.4至0.5，而中心部分燃料元件中的燃料柱的高度为周边部分燃料柱高度的0.5至0.8。形成直径为有效活性区域直径的0.5至0.85的阶梯式中间部分的燃料柱的高度在周边部分中的燃料柱的高度的0.55至0.9的范围内。

6. 发明申请

US20160125963A1 INTRINSICALLY SAFE NUCLEAR REACTOR 审中-公开
标题翻译：本质安全核反应堆
公开(公告)号：US20160125963A1
公开(公告)日：2016-05-05
申请号：US14527356
申请日：2014-10-29
申请人： Robin Jerry McDaniel
发明人： Robin Jerry McDaniel
IPC分类号： G21C9/00 , F04D13/06 , G21C9/04
CPC分类号： G21C1/02 , G21C9/027 , G21C15/247 , Y02E30/34 , Y02E30/35
摘要： An improved nuclear fission reactor of the liquid metal cooled type including a core configuration allowing for only two operational states, “Power” or “Rest”. The flow of the primary cooling fluid suspends the core in the “Power” state, with sufficient flow to remove the heat to an intermediate heat exchanger during normal operation. This invention utilizes the force of gravity to shut down the reactor after any loss of coolant flow, either a controlled reactor shut down or a “LOCA” event, as the core is controlled via dispersion of fuel elements. Electromagnetic pumps incorporating automatic safety electrical cut-offs are employed to shutdown the primary cooling system to disassemble the core to the “Rest” configuration due to a loss of secondary coolant or loss of ultimate heat sink. This invention is a hybrid pool-loop pressurized high-temperature or unpressurized reactor unique in its use of a minimum number of components, utilizing no moving mechanical parts, no rotating seals, optimized piping, and no control rods. Thus defining an elegantly simple intrinsically safe nuclear reactor.
摘要翻译：一种改进的液态金属冷却型核裂变反应堆，其包括允许只有两个操作状态“电源”或“休息”的核心配置。主冷却流体的流动使芯处于“动力”状态，具有足够的流动以在正常操作期间将热量移除到中间热交换器。本发明利用重力来在冷却剂流动的任何损失（受控反应堆关闭或“LOCA”）事件之后关闭反应器，因为通过燃料元件的分散来控制核心。采用包含自动安全电气截止阀的电磁泵关闭主冷却系统，由于二次冷却液的损失或最终的散热器损失，将芯拆卸到“休息”配置。本发明是混合池循环加压高温或非加压反应器，其独特的是使用最少数量的部件，不使用移动的机械部件，没有旋转密封件，优化的管道和没有控制棒。从而确定了一个优雅简单的本质安全的核反应堆。

7. 发明申请

US20160111175A1 MECHANICAL COMPONENT 审中-公开
标题翻译：机械部件
公开(公告)号：US20160111175A1
公开(公告)日：2016-04-21
申请号：US14868934
申请日：2015-09-29
申请人： ROLLS-ROYCE PLC
发明人： Claire ALLISON
IPC分类号： G21C19/307 , G21C1/02
CPC分类号： G21C19/307 , G21C1/02 , G21C1/03 , G21C19/02 , G21C19/20
摘要： This disclosure concerns reducing or elimination the build-up of coolant materials in the fuel handling and component maintenance systems of nuclear reactors, thereby reducing or eliminating manual cleaning of said components. A mechanical component (2) for use within the handling route of the reactor is provided with drainage channels (8) to disperse coolant material deposited on the component. A heater (4) may also be employed to avoid the build-up.
摘要翻译：本公开涉及减少或消除在核反应堆的燃料处理和部件维护系统中的冷却剂材料的积聚，从而减少或消除对所述部件的手动清洁。在反应器的处理路径内使用的机械部件（2）设置有排放通道（8），以分散沉积在部件上的冷却剂材料。还可以使用加热器（4）来避免积聚。

8. 发明申请

US20160012924A1 ELECTRIC FISSION REACTOR FOR SPACE APPLICATIONS 审中-公开
标题翻译：空间应用电动反应器
公开(公告)号：US20160012924A1
公开(公告)日：2016-01-14
申请号：US14770894
申请日：2014-03-26
申请人： LOS ALAMOS NATIONAL SECURITY, LLC
发明人： Patrick Ray McClure , David Duff Dixon , David Irvin Poston , Lee Mason , Marc Gibson
IPC分类号： G21C15/257
CPC分类号： G21C15/257 , G21C1/02 , G21C1/32 , G21C3/04 , G21C3/22 , G21C7/08 , G21C11/06 , G21C15/04 , G21D5/02 , G21H1/00 , G21H3/00 , Y02E30/34 , Y02E30/39
摘要： Embodiments of the present invention pertain to a power system utilizing a uranium-based reactor for space missions. For example, the power system may include a reactor configured to generate thermal energy using a uranium core. A plurality of heat pipes may be configured to transfer thermal energy from the reactor core to a plurality of Stirling engines to generate electricity for a spacecraft.
摘要翻译：本发明的实施例涉及利用铀基反应堆进行太空任务的动力系统。例如，电力系统可以包括被配置为使用铀核产生热能的反应器。多个热管可以被配置成将热能从反应堆堆芯传递到多个斯特林发动机以为航天器发电。

9. 发明申请

US20150146840A1 Sodium-resistant joining glass and the use thereof 有权
标题翻译：耐钠连接玻璃及其用途
公开(公告)号：US20150146840A1
公开(公告)日：2015-05-28
申请号：US14526672
申请日：2014-10-29
申请人： SCHOTT AG
发明人： Jens Suffner
IPC分类号： C03C8/24 , H02G3/22 , G21C13/02 , H01M2/08 , F16B11/00
CPC分类号： C03C8/24 , C03C3/091 , C03C3/093 , C03C8/02 , C03C8/04 , C03C2204/00 , C03C2205/00 , F16B11/00 , G21C1/02 , G21C13/02 , H01M2/08 , H01M10/39 , H02G3/22 , Y02E30/40 , Y10T29/4911 , Y10T403/477
摘要： The sodium-resistant joining glass (1) is substantially free of ZrO2 and is based on a SiO2—B2O3—Na2O—Al2O3 glass system. It is suitable for producing a joint of a metal and/or ceramic component with a further joining component (2, 3, 4) using the joining glass (1). Feedthrough-devices (20) using the joining glass (1) as fixing material are also disclosed.
摘要翻译：耐钠接合玻璃（1）基本上不含ZrO 2，并且基于SiO 2 -B 2 O 3 -Na 2 O-Al 2 O 3玻璃体系。适用于使用接合玻璃（1）制造金属和/或陶瓷部件的接头与另外的接合部件（2,3,4）。还公开了使用接合玻璃（1）作为固定材料的穿通装置（20）。

10. 发明申请

US20140205054A1 NUCLEAR FUEL ROD FOR FAST REACTORS INCLUDING METALLIC FUEL SLUG COATED WITH PROTECTIVE COATING LAYER AND FABRICATION METHOD THEREOF 有权
标题翻译：用于快速反应器的核燃料油，其中包括用保护涂层包覆的金属燃料SLUG及其制造方法
公开(公告)号：US20140205054A1
公开(公告)日：2014-07-24
申请号：US14079740
申请日：2013-11-14
申请人： KOREA HYDRO & NUCLEAR POWER CO., LTD. , KOREA ATOMIC ENERGY RESEARCH INSTITUTE
发明人： Chan Bock LEE , Jun Hwan KIM , Jong-Hyuk BAEK , Jin-Sik CHEON , ByoungOon LEE , Ki Hwan KIM , Sung-Ho KIM , Junehyung KIM , Seok-Jin OH , Young-Mo KO , Yoon-Myeong WOO , Seong Woo YANG
IPC分类号： G21C3/04
CPC分类号： G21C3/20 , G21C1/02 , G21C3/04 , G21C3/60 , G21C21/02 , G21C2003/047 , G21Y2002/30 , Y02E30/40
摘要： Provided are a nuclear fuel rod for fast reactors that includes a metallic fuel slug coated with a protective coating layer and a fabrication method thereof. The nuclear fuel rod for fast reactors that includes a surface treated metallic fuel slug and a cladding tube according to the present invention has an excellent effect of stabilizing components of the metallic fuel slug and fission products or impurities, because the interdiffusion between the metallic fuel slug and the cladding tube does not occur. Also, since the uniform coating on the surface of the metallic fuel slug may be facilitated and fabrication costs may be significantly reduced in comparison to a typical technique of using a functional material for preventing the interdiffusion at an inner surface of the cladding tube, it may be suitable for fabricating the nuclear fuel rod for fast reactors.
摘要翻译：提供了一种用于快堆的核燃料棒，其包括涂覆有保护涂层的金属燃料块及其制造方法。根据本发明的包括表面处理的金属燃料块和包层管的用于快堆的核燃料棒具有极好的稳定金属燃料块和裂变产物或杂质的组分的效果，因为金属燃料块之间的相互扩散并且不发生包层管。另外，由于与使用功能性材料防止包层管内表面相互扩散的典型技术相比，由于可以促进金属燃料块表面上的均匀涂覆，并且制造成本可能显着降低，因此，适合制造快堆的核燃料棒。

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