TWO-FLUID MOLTEN-SALT REACTOR
    1.
    发明申请
    TWO-FLUID MOLTEN-SALT REACTOR 审中-公开
    双流体盐酸反应器

    公开(公告)号:WO2010129836A1

    公开(公告)日:2010-11-11

    申请号:PCT/US2010/033979

    申请日:2010-05-07

    Inventor: SHU, Frank, H.

    CPC classification number: G21C13/02 G21C1/22 G21C1/28 G21C5/02 G21C15/02 Y02E30/40

    Abstract: A reactor vessel includes a plenum and a reactor core with first and second sets of channels. A blanket salt flows through the first set of channels, and a fuel salt flows through the second set of channels. The plenum receives the blanket salt from the first set of channels. The blanket salt provides a breed-stock for a fission reaction in the fuel salt and transfers heat generated by the fission reaction without mixing with the fuel salt.

    Abstract translation: 反应堆容器包括具有第一和第二组通道的增压室和反应堆堆芯。 覆盖的盐流过第一组通道,燃料盐流过第二组通道。 通风室从第一组通道接收毯子盐。 覆盖盐提供了燃料盐中的裂变反应的品种,并且传递由裂变反应产生的热而不与燃料盐混合。

    MINIATURE NEUTRON GENERATOR FOR ACTIVE NUCLEAR MATERIALS DETECTION
    4.
    发明申请
    MINIATURE NEUTRON GENERATOR FOR ACTIVE NUCLEAR MATERIALS DETECTION 审中-公开
    微型中子发生器用于主动核材料检测

    公开(公告)号:WO2008030212A2

    公开(公告)日:2008-03-13

    申请号:PCT/US2006/025607

    申请日:2006-06-29

    CPC classification number: H05H3/06 H05H6/00

    Abstract: This miniature neutron generator is for active detection of highly enriched uranium using a movable detection system. It is a small size, lightweight, low power consumption neutron generator with ease of operation and maintenance. The detector is based on a simplified ion source and ion transport system.

    Abstract translation: 该微型中子发生器用于使用可移动检测系统主动检测高浓缩铀。 它是一种体积小,重量轻,功耗低的中子发生器,易于操作和维护。 检测器基于简化的离子源和离子传输系统。

    ASSEMBLAGE POUR REACTEUR NUCLEAIRE COMPORTANT DU COMBUSTIBLE NUCLEAIRE SYSTEME DE DECLENCHEMENT ET D'INSERTION D'AU MOINS UN ELEMENT ABSORBANT NEUTRONIQUE ET/OU MITIGATEUR
    5.
    发明申请
    ASSEMBLAGE POUR REACTEUR NUCLEAIRE COMPORTANT DU COMBUSTIBLE NUCLEAIRE SYSTEME DE DECLENCHEMENT ET D'INSERTION D'AU MOINS UN ELEMENT ABSORBANT NEUTRONIQUE ET/OU MITIGATEUR 审中-公开
    组装核反应堆,包含核燃料和用于触发和插入至少一个中性吸收器和/或减震器元件的系统

    公开(公告)号:WO2013079662A1

    公开(公告)日:2013-06-06

    申请号:PCT/EP2012/074096

    申请日:2012-11-30

    CPC classification number: G21C3/326 G21C1/02 G21C1/06 G21C9/027 Y02E30/38

    Abstract: Assemblage porteur pour réacteur nucléaire comportant un boîtier (40), une zone fissile située en partie basse du boîtier (40), un volume libre situé en partie haute du boîtier (40), un espace libre (52) dans la zone fissile s'étendant sur la hauteur de la zone fissile à partir de son extrémité située du côté de la partie haute le long de l'axe longitudinal, un fourreau (54) bordant l'espace libre (52), et un système de déclenchement et d'insertion (SI), ledit système de déclenchement et d'insertion comportant une capsule (10) d'axe longitudinal, un ensemble absorbant (2) et/ou mitigateur suspendu dans la capsule et un dispositif de déclenchement et d'insertion (DI) apte à libérer ledit ensemble absorbant en cas d'état accidentel de l'assemblage, ladite capsule (10) étant insérée dans le fourreau (54) ledit système de déclenchement et d'insertion étant monté de manière amovible dans l'assemblage porteur.

    Abstract translation: 一种用于核反应堆的载体组件,包括:壳体(40); 位于壳体(40)的底部中的裂变区域; 位于所述壳体(40)的顶部的自由体积; 易裂变区域中的自由空间(52),沿着纵轴线从其位于顶部的端部的裂变区域的高度延伸; 与自由空间(52)接合的护套(54); 以及触发和插入系统(S1),所述触发和插入系统包括具有纵向轴线的胶囊(10),悬挂在胶囊中的吸收器和/或缓冲器构件(2),以及触发和插入装置(DI) 旨在在相对于组件发生意外情况的情况下释放吸收件。 胶囊(10)被插入护套(54)中,而触发和插入系统可拆卸地安装在托架组件中。

    PRESSURE-TUBE REACTOR WITH PRESSURISED MODERATOR
    6.
    发明申请
    PRESSURE-TUBE REACTOR WITH PRESSURISED MODERATOR 审中-公开
    带压缩调节器的压力管反应器

    公开(公告)号:WO2011130841A1

    公开(公告)日:2011-10-27

    申请号:PCT/CA2011/000459

    申请日:2011-04-21

    Abstract: A nuclear reactor can include a pressure vessel for containing a pressurized moderator at a first pressure. The nuclear reactor can also include a plurality of fuel channels for a coolant fluid at a second pressure. The plurality of fuel channels are fluidly connected at inlet ends thereof to a coolant supply conduit and are adapted to receive nuclear fuel bundles and to be mounted within the pressure vessel and surrounded by the moderator. The outlet ends of the fuel channels are fluidly connected to a coolant outlet conduit to enable the coolant fluid to circulate from the coolant supply conduit through the fuel channels to the coolant outlet conduit. The plurality of fuel channels maintain separation between the coolant fluid circulating within the fuel channels and the moderator.

    Abstract translation: 核反应堆可以包括用于在第一压力下容纳加压调节剂的压力容器。 核反应堆还可以包括用于在第二压力下的冷却剂流体的多个燃料通道。 多个燃料通道在其入口端处流体连接到冷却剂供应管道,并且适于接纳核燃料束并且被安装在压力容器内并被调节器包围。 燃料通道的出口端流体地连接到冷却剂出口导管,以使得冷却剂流体能够从冷却剂供应导管通过燃料通道循环到冷却剂出口导管。 多个燃料通道保持在燃料通道和调节器之间循环的冷却剂流体之间的分离。

    NUCLEAR REACTOR CORE ARCHITECTURE WITH ENHANCED HEAT TRANSFER AND SAFETY

    公开(公告)号:WO2021067903A1

    公开(公告)日:2021-04-08

    申请号:PCT/US2020/054190

    申请日:2020-10-04

    Abstract: An enhanced architecture for a nuclear reactor core includes several technologies: (1) nuclear fuel tiles (S-Block); and (2) a high-temperature thermal insulator and tube liners with a low-temperature solid-phase moderator (U-Mod) to improve safety, reliability, heat transfer, efficiency, and compactness. In S-Block, nuclear fuel tiles include a fuel shape designed with an interlocking geometry pattern to optimize heat transfer between nuclear fuel tiles and into a fuel coolant and bring the fuel coolant in direct contact with the nuclear fuel tiles. Nuclear fuel tiles can be shaped with discontinuous nuclear fuel lateral facets and have fuel coolant passages formed therein to provide direct contact between the fuel coolant and the nuclear fuel tiles. In U-Mod, tube liners with low hydrogen diffusivity retain hydrogen in the low-temperature solid- phase moderator even at elevated temperatures and the high-temperature thermal insulator insulates the solid-phase moderator from the nuclear fuel tiles.

    HEAT EXCHANGE SYSTEM AND METHOD WITH PASSIVE REGULATION OF THE AMOUNT OF HEAT REMOVED
    9.
    发明申请
    HEAT EXCHANGE SYSTEM AND METHOD WITH PASSIVE REGULATION OF THE AMOUNT OF HEAT REMOVED 审中-公开
    热交换系统和方法被动移除的热量调节

    公开(公告)号:WO2015059672A1

    公开(公告)日:2015-04-30

    申请号:PCT/IB2014065591

    申请日:2014-10-24

    Abstract: A thermal exchange system (1) with passive regulation of the amount of heat removed, in particular for a nuclear reactor, comprises an evaporating-condensing circuit (3), in which a condensable secondary fluid (4) circulates via which heat is removed from a primary fluid (2) by means of evaporation and subsequent condensation of the secondary fluid (4) in a main heat exchanger (11) and an auxiliary heat exchanger (12) respectively; and a passive regulation device (5), configured so as to passively regulate the thermal power removed by condensation by the auxiliary heat exchanger (12), matching it with the thermal power removed from the primary fluid (2) by means of incondensable gas injection into the evaporating- condensing circuit (3). A thermal exchange system (1) with passive regulation of the amount of heat removed, in particular for a nuclear reactor, comprises an evaporating-condensing circuit (3), in which a condensable secondary fluid (4) circulates via which heat is removed from a primary fluid (2) by means of evaporation and subsequent condensation of the secondary fluid (4) in a main heat exchanger (11) and an auxiliary heat exchanger (12) respectively; and a passive regulation device (5), configured so as to passively regulate the thermal power removed by condensation by the auxiliary heat exchanger (12), matching it with the thermal power removed from the primary fluid (2) by means of incondensable gas injection into the evaporating- condensing circuit (3).

    Abstract translation: 特别是对于核反应堆,特别是对于核反应堆,被动调节热量的热交换系统(1)包括蒸发冷凝回路(3),其中可冷凝的第二流体(4)循环通过热量从其中被除去 主流体(2)分别通过蒸发和随后的二次流体(4)在主热交换器(11)和辅助热交换器(12)中冷凝; 以及被动调节装置(5),其被配置为被动地调节通过辅助热交换器(12)的冷凝除去的热功率,使其与通过不可冷凝气体注入从主流体(2)移除的热功匹配 进入蒸发冷凝回路(3)。 特别是对于核反应堆,特别是对于核反应堆,被动调节热量的热交换系统(1)包括蒸发冷凝回路(3),其中可冷凝的第二流体(4)循环通过热量从其中被除去 主流体(2)分别通过蒸发和随后的二次流体(4)在主热交换器(11)和辅助热交换器(12)中冷凝; 以及被动调节装置(5),其被配置为被动地调节通过辅助热交换器(12)的冷凝除去的热功率,使其与通过不可冷凝气体注入从主流体(2)移除的热功匹配 进入蒸发冷凝回路(3)。

    RADIAL NEUTRON REFLECTOR
    10.
    发明申请
    RADIAL NEUTRON REFLECTOR 审中-公开
    径向中子反射镜

    公开(公告)号:WO2013162662A3

    公开(公告)日:2013-12-19

    申请号:PCT/US2013023584

    申请日:2013-01-29

    CPC classification number: G21C11/06 G21C5/02 G21F3/04 Y02E30/40

    Abstract: A nuclear reactor core comprising fissile material is surrounded by a core former. The core former comprises one or more single-piece annular rings wherein each single-piece annular ring comprises neutron-reflecting material. In some embodiments the core former comprises a stack of two or more such single-piece annular rings. In some embodiments the stack of single-piece annular rings is self-supporting. In some embodiments the stack of single-piece annular rings does not include welds or fasteners securing adjacent single-piece annular rings together. A core basket may contain the nuclear reactor core and the core former, and in some embodiments an annular gap is defined between the core former and the core basket. In some embodiments the core former does not include welds and does not include fasteners.

    Abstract translation: 包含易裂变材料的核反应堆堆芯被堆芯成形器包围。 芯成形器包括一个或多个单件式圆环,其中每个单件式圆环包括中子反射材料。 在一些实施例中,芯成形器包括两个或更多个这种单件式圆环的堆叠。 在一些实施例中,单件式圆环的堆叠是自支撑的。 在一些实施例中,单件式圆环的堆叠不包括将相邻的单件式圆环固定在一起的焊接或紧固件。 核心篮可以容纳核反应堆堆芯和核心成形器,并且在一些实施例中,在核心成形器和核心筐之间限定环形间隙。 在一些实施例中,芯成形器不包括焊接并且不包括紧固件。

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