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1. 发明申请

US20160336082A1 Reactor System With A Lead-Cooled Fast Reactor 有权
标题翻译：反应堆系统与铅冷却快堆
公开(公告)号：US20160336082A1
公开(公告)日：2016-11-17
申请号：US15112548
申请日：2014-11-27
申请人： STATE ATOMIC ENERGY CORPORATION "ROSATOM" ON BEHALF OF THE RUSSIAN FEDERATION
发明人： Boris Borisovich KUBINTSEV , Viktor Nikolaevich LEONOV , Aleksandr Viktorovich LOPATKIN , Yuriy Vasilievich CHERNOBROVKIN
IPC分类号： G21C15/18 , G21C15/02 , G21C15/253 , G21C1/03 , G21C15/247
CPC分类号： G21C15/18 , F22B1/063 , G21C1/03 , G21C15/02 , G21C15/247 , G21C15/253 , G21C15/26 , G21C15/28 , G21Y2002/50 , G21Y2004/302 , G21Y2004/40 , Y02E30/34 , Y02E30/35
摘要： Steam generators are in the form of tubular heat exchangers in which molten lead coolant flows within the pipes, while the water-steam flows in a space between the pipes, the steam generators are arranged in separate boxes and communicate with the reactor cavity by means of circulation conduits for raising and discharging the lead coolant, the steam generators and most of the circulation conduits and are arranged higher than the level of the lead coolant within the reactor cavity, and the circulation pumps are arranged within the reactor cavity on the circulation conduits and for raising the “hot” lead coolant, and a technical means is provided for ensuring natural circulation of the lead coolant through the reactor core when the circulation pumps are switched off. The specific volume of lead coolant per unit of power of the reactor is reduced and the safety of the reactor is increased.
摘要翻译：蒸汽发生器是管式热交换器的形式，其中熔融铅冷却剂在管道内流动，而水蒸汽在管道之间的空间中流动，蒸汽发生器被布置在分离的箱中并且通过用于升高和排出铅冷却剂，蒸汽发生器和大部分循环管道的循环管道布置成高于反应器腔内的铅冷却剂的水平面，并且循环泵布置在循环管道中的反应器腔内，用于提高“热”铅冷却剂，并且提供了一种技术手段，用于在循环泵关闭时确保铅冷却剂自然循环通过反应堆堆芯。反应堆每单位功率的铅冷却剂的比容积减少，反应堆的安全性增加。

2. 发明申请

US20160247587A1 Liquid metal cooled nuclear reactor, system for monitoring oxygen thermodynamic activity in such reactors and method of monitoring oxygen thermodynamic activity 审中-公开
标题翻译：液态金属冷却核反应堆，用于监测这种反应器中氧气热力学活动的监测系统以及监测氧气热力学活动的方法
公开(公告)号：US20160247587A1
公开(公告)日：2016-08-25
申请号：US15021697
申请日：2014-05-08
申请人： Joint Stock Company "AKME-Engineering"
发明人： Radomir Shamilievich Askhadullin , Konstantin Dmitrievich Ivanov , Petr Nikiforovich Martynov , Aleksey Nikolaevich Storozhenko
IPC分类号： G21C17/025 , G21C15/247
CPC分类号： G21C17/025 , G21C15/247
摘要： The invention relates to nuclear power engineering and can be used in power plants with lead-containing liquid metal coolants, and particularly in fast neutron reactors. The proposed nuclear reactor and the method and system for monitoring the thermodynamic activity of oxygen in a coolant with continuously operational oxygen thermodynamic activity sensors located in the “hot” and “cold” zones of the reactor vessel and an additional intermittently operational sensor make it possible to carry out continuous monitoring in order to maintain set oxygen thermodynamic activity values in a liquid metal coolant under any prescribed operating regime.
摘要翻译：本发明涉及核电工程，可用于含铅液态金属冷却剂的发电厂，特别是在快中子反应堆中。所提出的核反应堆以及用于监测冷却剂中氧的热力学活动的方法和系统，其具有位于反应堆容器的“热”和“冷”区域中的连续运行的氧热力学活动传感器以及附加的间歇运行的传感器，使其成为可能以进行连续监测，以便在任何规定的操作状态下，在液态金属冷却剂中保持设定的氧热力活动值。

3. 发明申请

US20160232990A1 Method for the In Situ Passivation of the Steel Surfaces of a Nuclear Reactor 审中-公开
标题翻译：原子反应堆钢表面原位钝化的方法
公开(公告)号：US20160232990A1
公开(公告)日：2016-08-11
申请号：US15022834
申请日：2014-03-19
申请人： (JOINT STOCK COMANY "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 , C23C22/73 , C23C22/72 , G21C15/247
CPC分类号： G21C1/03 , C23C22/72 , C23C22/73 , G21C13/08 , G21C15/247 , G21C17/0225 , G21C21/00 , G21Y2002/101 , G21Y2004/20 , 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.
摘要翻译：本发明涉及核技术领域，具体涉及一种用于钢表面原位钝化的方法。该方法包括将芯体模型的形状，核心部件的相对位置以及其质量特征的核心模拟器安装在用于规则芯的位置上; 接下来，反应器填充有重的液态金属传热介质，将传热介质加热到提供钝化条件的温度，原位钝化分两个阶段进行，其中第一个包括等温钝化模式符合本阶段确定的条件，第二种模式包括在不同条件下进行的非等温钝化，然后去除芯模拟器，并将规则芯安装在其中。该方法提供了在重液态金属传热介质环境中的钢元件的耐腐蚀性，并且允许在核演员的初始操作期间降低最大的氧消耗速率。

4. 发明授权

US09093182B2 Fast reactor 有权
标题翻译：快堆
公开(公告)号：US09093182B2
公开(公告)日：2015-07-28
申请号：US13266489
申请日：2010-04-27
申请人： Takanari Inatomi , Ayano Ebihara , Hiroshi Nakamura , Hideo Kobayashi , Katsushi Hasegawa
发明人： Takanari Inatomi , Ayano Ebihara , Hiroshi Nakamura , Hideo Kobayashi , Katsushi Hasegawa
IPC分类号： G21C15/00 , G21C1/32 , G21C1/02 , G21C15/02 , G21C15/247 , G21C11/02
CPC分类号： G21C1/322 , G21C1/02 , G21C11/022 , G21C15/02 , G21C15/247 , Y02E30/34
摘要： A fast reactor 1 includes: a reactor vessel 7 accommodating therein a core 2 and a primary coolant 21; a core support 13 supporting the core 2 from below; and a bulkhead 6 disposed on the core support 13, the bulkhead 6 extending upward and surrounding the core 2 from a lateral side. Between an inner surface of the reactor vessel 7 and the bulkhead 6, there is disposed an intermediate heat exchanger 15 configured to cool the primary coolant 21, and an electromagnetic pump 14 configured to pressurize the cooled primary coolant 21. A neutron shield 8 supported by an upper supporting plate 29 from above is disposed below the electromagnetic pump 14. The upper supporting plate 29 has an opening 29a. Between an outlet 14b of the electromagnetic pump 14 and the upper supporting plate 29, there is disposed a coolant guide mechanism 17 configured to guide the pressurized primary coolant 21 from the electromagnetic pump 14 to the neutron shield through the opening 29a of the upper supporting plate 29.
摘要翻译：快堆1包括：反应容器7，容纳有芯2和主冷却剂21; 核心支撑13支撑下面的核心2; 以及设置在芯支撑件13上的隔板6，隔板6从外侧向上延伸并围绕芯2。在反应堆容器7的内表面和隔板6之间设置有构造成冷却主冷却剂21的中间热交换器15和构造成对冷却的一次冷却剂21加压的电磁泵14.中子屏蔽8由来自上方的上支撑板29设置在电磁泵14的下方。上支撑板29具有开口29a。在电磁泵14的出口14b和上支撑板29之间设置有冷却剂引导机构17，其构造成通过上支撑板的开口29a将加压的一次冷却剂21从电磁泵14引导到中子屏蔽 29。

5. 发明申请

US20140348287A1 Dual Fluid Reactor 审中-公开
标题翻译：双流体反应器
公开(公告)号：US20140348287A1
公开(公告)日：2014-11-27
申请号：US14345647
申请日：2012-09-21
申请人： Armin Huke , Götz Ruprecht , Ahmed Hussein , Konrad Czerski , Stephan Gottlieb
发明人： Armin Huke , Götz Ruprecht , Ahmed Hussein , Konrad Czerski , Stephan Gottlieb
IPC分类号： G21C15/24
CPC分类号： G21C15/24 , G21C1/02 , G21C1/22 , G21C1/32 , G21C3/44 , G21C3/54 , G21C15/02 , G21C15/247 , G21C15/28 , G21C19/307 , G21D5/08 , Y02E30/34 , Y02E30/38
摘要： The present invention describes a nuclear reactor with a loop for liquid nuclear fuel, which, contrary to similar systems like the Molten-Salt Reactor of the Generation-IV canon, does not use the fuel loop for the heat transport at the same time. Instead, cooling is provided by an additional coolant loop, which is intensively coupled to the nuclear fuel duct for heat transport. That way, the advantages of liquid fuel can be utilized while optimizing the coolant loop performance, so the complexity of safety systems can be reduced significantly. This reactor design further includes an optimized neutron economy and is able to deactivate long-lived fission products generated by its own, so only short-lived radiotoxic waste has to be stored. With the neutron surplus it is also possible to deactivate long-lived radiotoxic waste from used fuel of today's light water reactors or to produce medical radioisotopes.
摘要翻译：本发明描述了一种具有用于液体核燃料的回路的核反应堆，其与类似的系统（如第IV代教规的熔盐反应器）相反，不同时使用燃料回路进行热运输。相反，通过附加的冷却剂回路提供冷却，冷却剂回路集中耦合到用于热运输的核燃料管道。这样，可以在优化冷却剂回路性能的同时利用液体燃料的优点，从而可以显着降低安全系统的复杂性。该反应堆设计还包括优化的中子经济性，并且能够使由其自身产生的长寿命裂变产物失活，因此只能存储短寿命的放射性毒性废物。利用中子剩余，还可能停用今天轻水反应堆二手燃料的长寿命放射毒性废物，或生产医用放射性同位素。

6. 发明申请

US20130216015A1 INTEGRATED SODIUM-COOLED FAST NUCLEAR REACTOR 审中-公开
标题翻译：一体化冷却的快速核反应堆
公开(公告)号：US20130216015A1
公开(公告)日：2013-08-22
申请号：US13877906
申请日：2011-10-03
申请人： Guy-Marie Gautier
发明人： Guy-Marie Gautier
IPC分类号： G21C1/32 , G21C15/247
CPC分类号： G21C1/322 , G21C1/02 , G21C1/03 , G21C1/32 , G21C15/18 , G21C15/247 , Y02E30/34 , Y02E30/35
摘要： An improvement to an SFR reactor of the integrated type wherein each of the outlet windows of the intermediate exchangers is surrounded in an enclosure in fluid communication with a pipe shaped into a toroid; and each of the inlets of the pump group which pumps the sodium from the hot area to the cold area through the intermediate exchangers is also in fluid communication with the toroid, such that the primary sodium originating from the hot area and exiting from the intermediate exchangers flows through the toroid and is then directed to the cold area by the said pump group.
摘要翻译：对一体型SFR反应器的改进，其中中间交换器的每个出口窗口在与形成环形线圈的管道流体连通的外壳中包围; 并且通过中间交换器将钠从热区域泵送到冷区域的泵组的每个入口也与环形线圈流体连通，使得源自热区域并从中间交换器出来的主要钠流过环形面，然后通过所述泵组导向冷区。

7. 发明申请

US20120138179A1 Electromagnetic flow regulator, system, and methods for regulating flow of an electrically conductive fluid 有权
公开(公告)号：US20120138179A1
公开(公告)日：2012-06-07
申请号：US12924914
申请日：2010-10-06
申请人： Roderick A. Hyde , Muriel Y. Ishikawa , Jon D. McWhirter , Ashok Odedra , Joshua C. Walter , Kevan D. Weaver , Lowell L. Wood, JR.
发明人： Roderick A. Hyde , Muriel Y. Ishikawa , Jon D. McWhirter , Ashok Odedra , Joshua C. Walter , Kevan D. Weaver , Lowell L. Wood, JR.
IPC分类号： F15C1/04
CPC分类号： G05D7/0635 , G21C1/026 , G21C15/247 , G21C17/032 , G21C17/10 , H02K44/02 , Y02E30/34 , Y10T137/2082 , Y10T137/2191 , Y10T137/2224 , Y10T137/86718 , Y10T137/87507
摘要： Disclosed embodiments include electromagnetic flow regulators for regulating flow of an electrically conductive fluid, systems for regulating flow of an electrically conductive fluid, methods of regulating flow of an electrically conductive fluid, nuclear fission reactors, systems for regulating flow of an electrically conductive reactor coolant, and methods of regulating flow of an electrically conductive reactor coolant in a nuclear fission reactor.

8. 发明申请

US20080123795A1 Controllable long term operation of a nuclear reactor 审中-公开
标题翻译：核反应堆的可长期运行
公开(公告)号：US20080123795A1
公开(公告)日：2008-05-29
申请号：US11605933
申请日：2006-11-28
申请人： Roderick A. Hyde , Muriel Y. Ishikawa , Nathan P. Myhrvold , Lowell L. Wood
发明人： Roderick A. Hyde , Muriel Y. Ishikawa , Nathan P. Myhrvold , Lowell L. Wood
IPC分类号： G21C7/06
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。

9. 发明授权

US4808080A Flow coupler assembly for double-pool-type reactor 失效
标题翻译：双池式电抗器流量耦合器组件
公开(公告)号：US4808080A
公开(公告)日：1989-02-28
申请号：US888667
申请日：1986-07-22
申请人： Christopher C. Alexion , Robert M. Slepian , Richard D. Nathenson
发明人： Christopher C. Alexion , Robert M. Slepian , Richard D. Nathenson
IPC分类号： G21C15/247 , H02K44/00 , H02K44/04 , H02K44/02 , G21C15/00
CPC分类号： G21C15/247 , H02K44/00 , H02K44/04 , Y02E30/35
摘要： A liquid metal pump assembly is disclosed as being adapted to be disposed as one of a plurality of like pump assemblies in a continuous, closed array about a core of a nuclear reactor system. Each pump assembly comprises a pipe for receiving and directing a pumped, intermediate liquid metal through the pump assembly, and first and second duct modules disposed on either side of the pipe. Each duct module comprises primary ducts for receiving and directing a primary liquid metal in a first direction, and intermediate ducts in communication with the pipe for directing a first flow of the intermediate liquid metal therethrough in a second direction opposite to the first direction. A mechanism illustratively in the form of a pair of field coils, generates and directs a main magnetic field to each of the primary and intermediate ducts of the first and second duct modules, whereby the interaction of the main magnetic field and the first flow of the intermediate liquid metal generates a first current flow through the intermediate ducts and the primary ducts, and pumps the primary liquid metal through the pump ducts. Further, at least one magnetic element is disposed adjacent one of the first and second duct modules for directing the main magnetic field from the one duct module to an adjacent liquid metal pump assembly, whereby the main magnetic field as generated by each of the plurality of liquid metal pumps is directed in the continuous array.
摘要翻译：公开了一种液态金属泵组件，其适于作为多个相似的泵组件中的一个以围绕核反应堆系统的核心的连续闭合阵列的形式设置。每个泵组件包括用于接收和引导泵送的中间液体金属穿过泵组件的管道，以及设置在管道两侧的第一和第二管道模块。每个管道模块包括用于沿第一方向接收和引导主要液态金属的主要管道，以及与管道连通的中间管道，用于沿与第一方向相反的第二方向引导中间液体金属的第一流动。一种示意性地以一对场线圈的形式的机构产生并将主磁场引导到第一和第二管道模块的主要和中间管道中的每一个，由此主磁场与第一流动的相互作用中间液体金属产生通过中间管道和主管道的第一电流，并且通过泵管道泵送主液体金属。此外，至少一个磁性元件设置在第一和第二管道模块之一附近，用于将主磁场从一个管道模块引导到相邻的液体金属泵组件，由此由多个液态金属泵被引导在连续阵列中。

10. 发明授权

US4755349A Mechanism for anti-seismic connection between the pump base and the dome of a nuclear power station 失效
标题翻译：泵站与核电站圆顶之间的抗震连接机理
公开(公告)号：US4755349A
公开(公告)日：1988-07-05
申请号：US927816
申请日：1986-11-06
申请人： Jean-Marc Canini , Serge Watre
发明人： Jean-Marc Canini , Serge Watre
IPC分类号： G21D1/04 , G21C9/04 , G21C15/247 , G21C9/00
CPC分类号： G21C15/247 , G21C9/04 , Y02E30/40
摘要： A mechanism for anti-seismic connection between the pump base and the dome of a nuclear power station is characterized by the fact that the pump base (1) is equipped externally with a flange (3) seated with a slight axial play and significant radial play within a socket (4) which is a fixed cover closed by and able to slide axially with a slight play within a cylindrical reinforcement (7a) of the dome (7). A radial damping mechanism (8) is installed between the flange (3) and the socket (4) to permit slow displacements between these two entities, but to block abrupt displacements. The lower end of the socket (4) comprises a collar (15) equipped with a metallic journal (16) which can slide axially within a bearing (17) firm with the internal wall of the dome (7).
摘要翻译：泵基座和核电站的圆顶之间的抗震连接机构的特征在于，泵基座（1）在外部设有具有轻微轴向游隙和显着径向游隙的凸缘（3）在一个插座（4）内，该插座是由圆顶（7）的圆柱形加强件（7a）内的微小的松动封闭并能够轴向滑动的固定盖。径向阻尼机构（8）安装在凸缘（3）和插座（4）之间，以允许这两个实体之间的缓慢位移，而是阻止突然的位移。插座（4）的下端包括装有金属轴颈（16）的轴环（15），其可以在与圆顶（7）的内壁牢固的轴承（17）内轴向滑动。

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