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    Molten salt compositions with enhanced heat transfer and reduced corrosion properties
    3.
    发明授权
    Molten salt compositions with enhanced heat transfer and reduced corrosion properties 有权

    公开(公告)号：US11050094B1

    公开(公告)日：2021-06-29

    申请号：US16039770

    申请日：2018-07-19

    申请人： UT-Battelle, LLC

    发明人： Sheng Dai ,  Carter W. Abney ,  Richard T. Mayes ,  Dmitriy Dolzhnikov ,  Huimin Luo

    IPC分类号： H01M10/39 ,  C07D307/68 ,  G21C3/54 ,  G21C1/02 ,  G21C11/06

    摘要： A heat transfer (exchange) composition comprising a halide salt matrix having dispersed therein nanoparticles comprising elemental carbon in the absence of water and surfactants, wherein said halide is fluoride or chloride, wherein the halide salt may be an alkali halide salt (e.g., lithium fluoride, sodium fluoride, potassium fluoride, rubidium fluoride, sodium chloride, potassium chloride, rubidium chloride, and eutectic mixtures thereof) or an alkaline earth halide salt (e.g., fluoride or chloride salt of beryllium, magnesium, calcium, strontium, or barium), and wherein the nanoparticles comprising elemental carbon may be solid or hollow, and wherein the composition may further include nanoparticles comprising a fissile material (e.g., U, Th, or Pu) dispersed within the composition. Molten salt reactors (MSRs) containing these heat transfer compositions in coolant loops in thermal exchange with a reactor core, as well operation of such MSRs, are also described.

    Nuclear reactor system for extinguishing radioactivity
    4.
    发明授权
    Nuclear reactor system for extinguishing radioactivity 有权

    公开(公告)号：US10395787B2

    公开(公告)日：2019-08-27

    申请号：US15759509

    申请日：2016-12-14

    申请人： CLEAR INC.

    发明人： Osao Sumita ,  Isao Ueno ,  Takehiko Yokomine

    IPC分类号： G21D1/00 ,  G21C15/28 ,  G21F9/28 ,  G21C11/06 ,  G21C3/32 ,  G21C1/28 ,  G21C1/02 ,  G21G1/02

    摘要： Provided is a nuclear reactor system and method therefor, for increasing the speed of conversion of a radionuclide to a stable nuclide to reduce radionuclide concentration using thermal neutrons produced by reducing the velocity of fast neutrons, while simultaneously subjecting fast-neutron-induced thermal energy of a primary cooling material to heat exchange with a secondary cooling material in a heat exchanger (7), and feeding the energy to a turbine system to generate power, the system having a nuclear reactor container (1) comprising a first container (11), and a second container (12), a plurality of metal fuel assemblies (22) and a liquid metal, which is the primary cooling material, being disposed in the first container, and the second cooling material capable of dual use as a neutron moderator and a MA radioactivity-extinguishing assembly or FP-extinguishing assembly (24) being loaded in the second container.

    Molten salt reactor
    5.
    发明授权
    Molten salt reactor 有权

    公开(公告)号：US10283224B2

    公开(公告)日：2019-05-07

    申请号：US15610124

    申请日：2017-05-31

    申请人： M. Sheldon Hansen

    发明人： M. Sheldon Hansen

    IPC分类号： G21C1/16 ,  G21C1/22 ,  G21C3/10 ,  G21C3/32 ,  G21C3/54 ,  G21C5/02 ,  G21C5/12 ,  G21C7/00 ,  G21D7/00 ,  G21C11/06 ,  G21C19/14 ,  G21C19/19 ,  G21C3/336 ,  G21D9/00

    摘要： Systems and methods for providing and using molten salt reactors are described. While the systems can include any suitable component, in some cases, they include a graphite reactor core defining an internal space that houses one or more fuel wedges, where each wedge defines one or more fuel channels that extend from a first end to a second end of the wedge. In some cases, one or more of the fuel wedges comprise multiple wedge sections that are coupled together end to end and/or in any other suitable manner. In some cases, one or more alignment pins also extend between two sections of a fuel wedge to align the sections. In some cases, one or more seals are also disposed between two sections of a fuel wedge. Thus, in some cases, the reactor core can be relatively long (e.g., to be a pipeline reactor). Other implementations are also described.

    Molten salt reactor that includes multiple fuel wedges that define fuel channels
    6.
    发明授权
    Molten salt reactor that includes multiple fuel wedges that define fuel channels 有权

    公开(公告)号：US10283223B2

    公开(公告)日：2019-05-07

    申请号：US14859100

    申请日：2015-09-18

    申请人： UTAH GREEN ENERGY TECHNOLOGIES, LLC

    发明人： M. Sheldon Hansen

    IPC分类号： G21C1/14 ,  G21C1/16 ,  G21C1/22 ,  G21C5/02 ,  G21C19/14 ,  G21C19/19 ,  G21C11/06 ,  G21C5/12 ,  G21D9/00

    摘要： Systems and methods for providing a molten salt reactor can include a graphite reactor core that defines an internal space, with multiple fuel wedges being received in the internal space, and with the wedges each defining a fuel channel extending from a first end to a second end of each of the wedges. The reactor can further include a fuel pin rod that defines an internal fuel conduit and that is disposed between at least two of the wedges. The reactor core can also define a fuel ingress port and a fuel egress port. The reactor core can further be rotatably received within a reactor housing such that the ports are configured to become at least one of more occluded and less occluded as the reactor core rotates.

    Fast Neutron Reactor and Neutron Reflector Block of a Fast Neutron Reactor
    8.
    发明申请
    Fast Neutron Reactor and Neutron Reflector Block of a Fast Neutron Reactor 审中-公开
    快中子反应堆快中子反应堆和中子反射块

    公开(公告)号：US20170018320A1

    公开(公告)日：2017-01-19

    申请号：US15102445

    申请日：2014-12-08

    申请人： Joint Stock Company "AKME-Engineering"

    发明人： Sergey Viktorovich Bulavkin

    IPC分类号： G21C15/10 ,  G21C11/06 ,  G21C15/28 ,  G21C1/02

    CPC分类号： G21C15/10 ,  G21C1/02 ,  G21C11/06 ,  G21C15/28 ,  Y02E30/34 ,  Y02E30/35

    摘要： The invention relates to the field of nuclear engineering, and more particularly to designs for removable neutron reflector blocks for heavy liquid metal-cooled fast neutron reactors. The present fast neutron reactor contains a core consisting of heavy liquid metal-cooled fuel rods, and neutron reflector blocks, disposed around the core, which comprise a steel casing with at least one inlet opening in the side walls thereof above the core boundary, said inlet opening being intended for diverting part of the coolant flow from the space between the blocks into the casing, and at least one vertical pipe mounted in the casing, through which the diverted coolant flow, which has passed through the upper and lower boundaries of the core, enters the bottom part of the casing; also, on the outer side of the casing, above the inlet opening, there is mounted a throttling device for creating hydraulic resistance to the coolant flow in the space between the blocks. The technical result is an increase in the operating safety and the performance of a fast neutron reactor and a reduction in the heat exchange surface of the steam generator.

    摘要翻译： 本发明涉及核工程领域，更具体地涉及用于重液态金属冷却快中子反应堆的可移除中子反射块的设计。 本发明的快中子反应堆包含由重液态金属冷却的燃料棒组成的核心和设置在芯体周围的中子反射器块，该中子反射块包括一个在壳体边界上方的侧壁中具有至少一个入口的钢壳体， 入口开口旨在将冷却剂流的一部分从块之间的空间转移到壳体中，以及安装在壳体中的至少一个垂直管，通过该垂直管已经通过了转向冷却剂流的上部和下部边界 芯，进入套管的底部; 另外，在外壳的外侧，在入口开口的上方，安装有用于在块之间的空间中产生对冷却剂流的液压阻力的节流装置。 技术结果是增加了快中子反应器的运行安全性和性能，并减少了蒸汽发生器的热交换面。

    HIGH POWER DENSITY LIQUID-COOLED PEBBLE-CHANNEL NUCLEAR REACTOR
    9.
    发明申请
    HIGH POWER DENSITY LIQUID-COOLED PEBBLE-CHANNEL NUCLEAR REACTOR 有权
    高功率密度液体冷却的通道核反应堆

    公开(公告)号：US20100296620A1

    公开(公告)日：2010-11-25

    申请号：US12776599

    申请日：2010-05-10

    申请人： Per F. Peterson

    发明人： Per F. Peterson

    IPC分类号： G21C15/247 ,  G21C1/02 ,  G21C3/04 ,  G21C11/06

    CPC分类号： G21C3/30 ,  G21C1/07 ,  G21C3/22 ,  G21C7/107 ,  G21Y2002/201 ,  G21Y2002/301 ,  G21Y2004/30 ,  Y02E30/36

    摘要： A high-temperature nuclear reactor, cooled by a liquid fluoride salt, is described. The reactor uses an annular fuel pebble comprised of an inert graphite center kernel, a TRISO fuel particles region, and a graphite outer shell, with an average pebble density lower than the density of the liquid salt so the pebbles float. The pebbles are introduced into a coolant entering the reactor and are carried into the bottom of the reactor core, where they form a pebble bed inside a plurality of vertical channels inside one or more replaceable Pebble Channel Assemblies (PCAs). Pebbles are removed through defueling chutes located at the top of each PCA. Each PCA also includes channels for insertion of neutron control and shutdown elements, and channels for insertion of core flux mapping and other instrumentation.

    摘要翻译： 描述了由液态氟化物盐冷却的高温核反应堆。 反应器使用由惰性石墨中心核，TRISO燃料颗粒区域和石墨外壳组成的环形燃料卵石，其平均卵石密度低于液体盐的密度，以使卵石浮动。 鹅卵石被引入到进入反应器的冷却剂中并被运送到反应堆堆芯的底部，在反应堆堆芯的底部，它们在一个或多个可更换的卵石通道组件（PCAs）内的多个垂直通道内形成卵石床。 通过位于每个PCA顶部的排污槽来移除卵石。 每个PCA还包括用于插入中子控制和关闭元件的通道，以及用于插入核心通量映射和其他仪器的通道。

    Assembly for a core of a nuclear reactor
    10.
    发明授权
    Assembly for a core of a nuclear reactor 失效
    核反应堆核心大会

    公开(公告)号：US4617170A

    公开(公告)日：1986-10-14

    申请号：US570830

    申请日：1984-01-16

    申请人： Peter Suchy

    发明人： Peter Suchy

    IPC分类号： G21C5/00 ,  G21C3/30 ,  G21C3/326 ,  G21C11/02 ,  G21C11/06 ,  G21C3/34

    CPC分类号： G21C11/024 ,  G21C3/326 ,  G21Y2002/102 ,  G21Y2002/201 ,  G21Y2004/30 ,  Y02E30/38

    摘要： An element for a core of a nuclear reactor, includes a square grid assembly formed of a plurality of spacers distributed over the length of the element, structural elements interconnecting the spacers, rods regularly disposed in the square grid assembly and surrounded by the spacers, including a plurality of the rods disposed at an edge of the core, and neutron-shielding material having a substantially square cross section respectively disposed in each of the plurality of rods at the edge of the core.

    摘要翻译： 用于核反应堆核心的元件包括由分布在元件的长度上的多个间隔件形成的方形栅格组件，将隔离物互相连接的结构元件，规则地设置在正方形格栅组件中并被间隔物包围的杆，包括 设置在芯的边缘处的多个杆和在芯的边缘处分别设置在多个杆中的每一个中的基本正方形横截面的中子屏蔽材料。