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    MOLTEN SALT NUCLEAR REACTOR
    1.
    发明申请
    MOLTEN SALT NUCLEAR REACTOR 审中-公开

    公开(公告)号：US20180322964A1

    公开(公告)日：2018-11-08

    申请号：US15771742

    申请日：2016-10-28

    申请人： TERRESTRIAL ENERGY INC.

    发明人： David LEBLANC

    IPC分类号： G21C1/22 ,  G21C1/03 ,  G21C3/24 ,  G21C5/18 ,  G21C5/12

    CPC分类号： G21C1/22 ,  G21C1/03 ,  G21C3/24 ,  G21C5/123 ,  G21C5/14 ,  G21C5/18 ,  Y02E30/40

    摘要： A molten salt nuclear reactor a neutron moderator core that has an inner region that defines channels of a first diameter separated by a first pitch and, an outer region that defines channels of a second diameter separated by a second pitch. The first diameter is larger than the second diameter and the first pitch is larger than the second pitch. This configuration allows for an increased capture of neutrons by fertile elements in the outer region. That is, less neutrons are lost to the outside of the core. The configuration is such that the neutron multiplication factor is larger than one in the inner portion and lower than one in the outer portion.

    Practical molten salt fission reactor
    2.
    发明授权
    Practical molten salt fission reactor 有权

    公开(公告)号：US10043594B2

    公开(公告)日：2018-08-07

    申请号：US14768658

    申请日：2014-02-19

    申请人： Ian Richard Scott

    发明人： Ian Richard Scott

    IPC分类号： G21C1/22 ,  G21C1/03 ,  G21C3/24 ,  G21C3/54

    CPC分类号： G21C1/22 ,  G21C1/03 ,  G21C3/24 ,  G21C3/54 ,  Y02E30/34 ,  Y02E30/35 ,  Y02E30/38

    摘要： A nuclear fission reactor comprising a core, a pool of coolant liquid, and a heat exchanger. The core comprises an array of hollow tubes which contain molten salts of fissile isotopes. The tube array is at least partly immersed in the pool of coolant liquid. The tube array comprises a critical region, where the density of the fissile isotopes during operation of the reactor is sufficient to cause a self-sustaining fission reaction. Heat transfer from the molten salts of fissile isotopes to the tubes is achieved by any one or more of natural convection of the molten salts, mechanical stirring of the molten salts, and oscillating fuel salt flow within the tubes. The molten salts of fissile isotopes are contained entirely within the tubes during operation of the reactor.

    Reactor System With A Lead-Cooled Fast Reactor
    6.
    发明申请
    Reactor System With A Lead-Cooled Fast Reactor 有权
    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。

    Method for the In Situ Passivation of the Steel Surfaces of a Nuclear Reactor
    7.
    发明申请
    Method for the In Situ Passivation of the Steel Surfaces of a Nuclear Reactor 审中-公开
    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。

    A PRACTICAL MOLTEN SALT FISSION REACTOR
    8.
    发明申请
    A PRACTICAL MOLTEN SALT FISSION REACTOR 审中-公开
    实践中的盐雾反应器

    公开(公告)号：US20160005497A1

    公开(公告)日：2016-01-07

    申请号：US14768658

    申请日：2014-02-19

    申请人： Ian Richard SCOTT

    发明人： Ian Richard SCOTT

    IPC分类号： G21C1/22 ,  G21C1/03 ,  G21C3/54

    CPC分类号： G21C1/22 ,  G21C1/03 ,  G21C3/24 ,  G21C3/54 ,  Y02E30/34 ,  Y02E30/35 ,  Y02E30/38

    摘要： A nuclear fission reactor comprising a core, a pool of coolant liquid, and a heat exchanger. The core comprises an array of hollow tubes which contain molten salts of fissile isotopes. The tube array is at least partly immersed in the pool of coolant liquid. The tube array comprises a critical region, where the density of the fissile isotopes during operation of the reactor is sufficient to cause a self-sustaining fission reaction. Heat transfer from the molten salts of fissile isotopes to the tubes is achieved by any one or more of natural convection of the molten salts, mechanical stirring of the molten salts, and oscillating fuel salt flow within the tubes. The molten salts of fissile isotopes are contained entirely within the tubes during operation of the reactor.

    摘要翻译： 核裂变反应堆，包括核心，冷却液池和热交换器。 核心包括含有裂变同位素熔盐的空心管阵列。 管阵列至少部分地浸在冷却剂液体池中。 管阵列包括临界区域，其中在反应器操作期间裂变同位素的密度足以引起自维持裂变反应。 通过熔融盐的自然对流，熔融盐的机械搅拌和管内振荡的燃料盐流中的任何一种或多种来实现从裂变同位素的熔融盐到管的热传递。 在反应器运行期间，裂变同位素的熔盐完全包含在管内。

    NUCLEAR REACTOR
    9.
    发明申请
    NUCLEAR REACTOR 审中-公开
    核反应堆

    公开(公告)号：US20150325317A1

    公开(公告)日：2015-11-12

    申请号：US14646788

    申请日：2012-11-26

    申请人： Joint Stock Company "AKME- engineering"

    发明人： Georgy Iliich TOSHINSKY

    IPC分类号： G21C1/03 ,  G21C3/32 ,  G21C3/18

    CPC分类号： G21C3/18 ,  G21C1/03 ,  G21C3/17 ,  G21C3/32 ,  G21C3/322 ,  Y02E30/40

    摘要： A nuclear reactor comprising a housing having disposed therein an active region that contains a bundle of rod-type fuel elements enclosed in a tubular shell and submerged in a primary coolant that circulates between the active region and at least one heat exchanger. In order to reduce the level of pressure of gaseous fission fragments accumulating below the fuel element shell and to enable the most uniform possible distribution of the velocity field of the primary coolant at the inlet to the active part of the fuel elements, said fuel elements are provided in their upper parts with active portions, which are filled with fuel, and hollow working portions, which are situated below said active portions.

    摘要翻译： 一种核反应堆，包括壳体，其中设置有活性区域，所述活性区域包含封闭在管状壳体中并浸没在主要冷却剂中的杆状燃料元件的一束，所述主冷却剂在活性区域和至少一个热交换器之间循环。 为了减少积聚在燃料元件壳下面的气体裂变碎片的压力水平，并且能够使得在入口处的主冷却剂的速度场的最均匀的可能分布到燃料元件的有源部分，所述燃料元件 在其上部设置有充满燃料的活性部分和位于所述活性部分下方的中空加工部分。

    SYSTEM AND METHOD FOR COOLING VIA PHASE CHANGE
    10.
    发明申请
    SYSTEM AND METHOD FOR COOLING VIA PHASE CHANGE 审中-公开
    通过相位变化冷却的系统和方法

    公开(公告)号：US20140112428A1

    公开(公告)日：2014-04-24

    申请号：US13659218

    申请日：2012-10-24

    申请人： BABCOCK & WILCOX TECHNICAL SERVICES GROUP, INC.

    发明人： Timothy A. Policke ,  Erik T. Nygaard ,  Scott B. Aase

    IPC分类号： G21C15/04 ,  F28D1/047

    CPC分类号： F28D15/06 ,  F28D15/02 ,  F28D2021/0054 ,  G21C1/03 ,  G21C15/04 ,  G21C15/18 ,  Y02E30/40

    摘要： The present invention relates generally to the field of cooling systems and/or methods for cooling a heated, fissioning, or exothermic solution. In one embodiment, the present invention relates to a cooling system, and method of utilizing same, for cooling a heated, fissioning, or exothermic solution that utilizes submerged cooling coils where the system of the present invention relies on a combination of multiple factors to achieve the desired effect. In one embodiment, the present invention relates to a cooling system, and method of utilizing same, for cooling a heated, fissioning, or exothermic solution that utilizes submerged cooling coils where the system of the present invention relies on the combination of: (i) cooling coil geometry; (ii) cooling coil location and design; and (iii) cooling coil operational pressure.

    摘要翻译： 本发明一般涉及用于冷却加热的裂变或放热溶液的冷却系统和/或方法领域。 在一个实施例中，本发明涉及一种冷却系统及其利用方法，用于冷却采用浸没式冷却盘管的加热裂变或放热溶液，其中本发明的系统依赖多个因素的组合来实现 期望的效果。 在一个实施方案中，本发明涉及一种冷却系统及其利用方法，用于冷却采用浸没冷却盘管的加热裂变或放热溶液，其中本发明的系统依赖于以下组合：（i） 冷却盘管几何形状; （ii）冷却盘管的位置和设计; 和（iii）冷却盘管的操作压力。