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    Decay Heat Removal System for Liquid Metal Reactor
    61.
    发明申请
    Decay Heat Removal System for Liquid Metal Reactor 失效
    液态金属反应器衰变除热系统

    公开(公告)号：US20080219397A1

    公开(公告)日：2008-09-11

    申请号：US11926219

    申请日：2007-10-29

    申请人： Yoon Sub Sim ,  Seong O. Kim ,  Won Dae Jeon

    发明人： Yoon Sub Sim ,  Seong O. Kim ,  Won Dae Jeon

    IPC分类号： G21C15/00

    CPC分类号： G21C15/18 ,  G21Y2002/201 ,  G21Y2002/202 ,  G21Y2002/50 ,  G21Y2004/30 ,  Y02E30/35

    摘要： A decay heat removal system for a liquid metal reactor in which a decay heat exchanger (DHX) is installed concentrically with an intermediate heat exchanger (IHX) in the same cylinder which separates the DHX and IHX from the reactor pool fluid, and serves to remove the reactor core decay heat. The cylinder surrounds the IHX and DHX, and has an open top portion protruding out of the level of the fluid in a hot pool, a bottom portion connected to a cold pool and a guide pipe for allowing the passage of the fluid from the hot pool into the IHX. The decay heat removal system can remove decay heat immediately after occurrence of an accident, thereby improving the safety of a nuclear plant.

    摘要翻译： 用于液态金属反应器的衰变除热系统，其中衰减热交换器（DHX）与在相同气缸中的中间热交换器（IHX）同心地安装，其将DHX和IHX与反应池池液体分离，并用于除去 反应堆核心衰变热。 气缸围绕IHX和DHX，并且具有从热池中的流体水平面突出的开口顶部部分，连接到冷库的底部部分和用于允许来自热池的流体通过的引导管 进入IHX。 腐蚀除热系统可以在事故发生后立即消除腐蚀热，从而提高核电厂的安全性。

    Preparation method of uranium metal and apparatus thereused
    62.
    发明申请
    Preparation method of uranium metal and apparatus thereused 有权
    铀金属及其设备的制备方法

    公开(公告)号：US20070158196A1

    公开(公告)日：2007-07-12

    申请号：US11649407

    申请日：2007-01-03

    申请人： Young-Ho Kang ,  Jong-Hyeon Lee ,  Sung-Chan Hwang ,  Joon-Bo Shim ,  Eung-Ho Kim ,  Sung-Won Park

    发明人： Young-Ho Kang ,  Jong-Hyeon Lee ,  Sung-Chan Hwang ,  Joon-Bo Shim ,  Eung-Ho Kim ,  Sung-Won Park

    IPC分类号： C25C3/34

    CPC分类号： C25C3/34 ,  C25C7/025

    摘要： Disclosed herein is a method of preparing uranium metal by electrorefining uranium metal, comprising: applying a predetermined current to an anode electrode included in an anode basket receiving fuel segments made of uranium metal and a cathode electrode of carbon material; electrodepositing uranium on the cathode electrode in accordance with the reaction initiated by the applied current; and collecting the electrodeposited uranium by self-weight. An apparatus for electrorefining uranium metal used in the method according to the present invention, comprises: an anode basket (6) receiving fuel segments made of uranium metal and comprising an anode electrode; and a reactor including a cathode electrode (5) made of carbon material and a uranium collector (10) therein. According to the method of the present invention having the above mentioned constitution and the apparatus thereof, it is possible to separate only pure uranium metal with a high capability from the spent metal nuclear fuels conveniently and economically.

    摘要翻译： 本文公开了一种通过电解铀金属制备铀金属的方法，包括：将预定电流施加到阳极柱中，所述阳极电极包括接收由铀金属制成的燃料段的阳极筐和碳材料的阴极电极; 根据施加电流引发的反应，在阴极上电沉积铀; 并通过自重收集电沉积的铀。 在本发明的方法中使用的用于电解铀金属的装置包括：阳极筐（6），其容纳由铀金属制成并包括阳极电极的燃料段; 以及包括由碳材料制成的阴极电极（5）和铀收集器（10）的反应器。 根据具有上述结构的本发明的方法及其装置，可以方便和经济地将仅具有高性能的纯铀金属与废金属核燃料分开。

    Plate-type nuclear fuels having regularly arranged coarse spherical particles of U-Mo- or U-Mo-X alloy and fabrication method thereof
    63.
    发明申请
    Plate-type nuclear fuels having regularly arranged coarse spherical particles of U-Mo- or U-Mo-X alloy and fabrication method thereof 审中-公开
    具有规则排列的U-Mo-或U-Mo-X合金的粗球形颗粒的板式核燃料及其制造方法

    公开(公告)号：US20070036261A1

    公开(公告)日：2007-02-15

    申请号：US11269104

    申请日：2005-11-08

    申请人： Chang Kyu Kim ,  Eun Jung ,  Yoon Sang Lee ,  Ho Ryu

    发明人： Chang Kyu Kim ,  Eun Jung ,  Yoon Sang Lee ,  Ho Ryu

    IPC分类号： G21C3/00

    CPC分类号： G21C3/02 ,  Y02E30/40

    摘要： A plate-type nuclear fuel having regularly arranged coarse particles of a gamma-phase U—Mo or U—Mo—X alloy and a fabrication method thereof and, more particularly, to a plate-type nuclear fuel having coarse spherical particles of a stable gamma-phase U—Mo or U—Mo—X alloy arranged regularly on an aluminum cladding in at least one layer and a fabrication method thereof. Operation limit power, high temperature irradiation stability and performance are advantageously improved by preventing excessive reaction between a nuclear fuel and aluminum matrix through minimization of the area of interaction layers between the fuel and aluminum matrix, minimizing pores and swelling by restraining reaction layer formation of an intermetallic compound, and maintaining high thermal conductivity to transfer internal temperature of the nuclear fuel smoothly.

    摘要翻译： 具有规则排列的γ相U-Mo或U-Mo-X合金粗颗粒的板式核燃料及其制造方法，更具体地说，涉及具有稳定的粗球形颗粒的板式核燃料 γ相U-Mo或U-Mo-X合金在至少一层上规则地布置在铝包层上及其制造方法。 通过最小化燃料和铝基体之间的相互作用层的面积来防止核燃料和铝基体之间的过度反应，有利地提高了操作限制功率，高温照射稳定性和性能，通过抑制燃料和铝基体之间的反应层形成来最小化孔和膨胀 金属间化合物，并保持高导热性，平稳地转移核燃料的内部温度。

    Inhibition method of stress corrosion cracking of nuclear steam generator tubes by lanthanum boride
    64.
    发明授权
    Inhibition method of stress corrosion cracking of nuclear steam generator tubes by lanthanum boride 有权
    硼化镧核蒸汽发生器管应力腐蚀开裂的抑制方法

    公开(公告)号：US06885721B2

    公开(公告)日：2005-04-26

    申请号：US10102091

    申请日：2002-03-19

    申请人： Do Haeng Hur ,  Joung Soo Kim

    发明人： Do Haeng Hur ,  Joung Soo Kim

    IPC分类号： G21D1/00 ,  C23F11/18 ,  G21C17/022 ,  G21C19/00

    CPC分类号： C22C28/00 ,  C23F11/182 ,  G21C17/0225 ,  G21Y2002/103

    摘要： The present invention relates to a method for inhibiting stress corrosion cracking occurring on steam generator tubes in the secondary side of nuclear power plants and an inhibitor therefor. The method comprises supplying lanthanum boride as an inhibitor for stress corrosion cracking into the secondary feed water of the nuclear power plants. The method according to the present invention improves the resistance of stress corrosion cracking ten times or higher than no inhibitor, and five times or higher than the conventional inhibitor. In particular, the method according to the present invention shows a superior inhibiting effect in the lead-contaminated environment such that the complete inhibition of stress corrosion cracking can be achieved. As thus, the method can reduce the unexpected stop of operating nuclear power plants caused by the stress corrosion cracking on steam generator tubes, thereby reducing the cost required for maintaining and repairing the tubes.

    摘要翻译： 本发明涉及一种用于抑制在核电站二次侧的蒸汽发生器管上发生的应力腐蚀开裂的方法及其抑制剂。 该方法包括将硼化镧作为应力腐蚀开裂的抑制剂供应到核电站的二次给水中。 根据本发明的方法提高了应力腐蚀开裂的10倍或更高的阻力，比常规抑制剂高5倍以上。 特别地，根据本发明的方法在铅污染环境中显示出优异的抑制作用，从而可以实现应力腐蚀开裂的完全抑制。 因此，该方法可以减少由蒸汽发生器管产生的应力腐蚀开裂引起的操作核电站的意外停止，从而降低维持和修复管所需的成本。

    Spacer grid with hybrid flow-mixing device for nuclear fuel assembly
    65.
    发明授权
    Spacer grid with hybrid flow-mixing device for nuclear fuel assembly 失效
    具有用于核燃料组装的混合流动混合装置的间隔栅格

    公开(公告)号：US06845138B2

    公开(公告)日：2005-01-18

    申请号：US10215997

    申请日：2002-08-07

    申请人： Taehyun Chun ,  Dongseok Oh ,  Wangkee In ,  Keenam Song ,  Hyungkyu Kim ,  Heungseok Kang ,  Kyungho Yoon ,  Younho Jung

    发明人： Taehyun Chun ,  Dongseok Oh ,  Wangkee In ,  Keenam Song ,  Hyungkyu Kim ,  Heungseok Kang ,  Kyungho Yoon ,  Younho Jung

    IPC分类号： G21C3/34 ,  G21C3/322 ,  G21C3/332

    CPC分类号： G21C3/332 ,  Y02E30/40

    摘要： A spacer grid with hybrid flow-mixing devices for nuclear fuel bundle is made up of an intersection of a plurality of thin straps at right angles to form a plurality of cells for receiving and supporting fuel rods. Each strap is composed of two types of strap units, called a primary strap unit and a secondary strap unit, which are alternately arranged along the strap. The primary strap unit is a strap section having a primary vane set, and a secondary strap unit is a strap section having a secondary vane set. The straps intersect such that, by primary and secondary strap units, each intersection forms a hybrid flow-mixing device around the top of each junction. The primary vane set, consisting of a trapezoidal primary vane stand and two bent primary mixing vanes on both sides, protrudes upwardly from the strap and is primarily for generating cross flow between channels. Meanwhile, the secondary vane set, consisting of a trapezoidal secondary vane stand and two bent primary mixing vanes on both sides, also protrudes upwardly from the strap, but is primarily for swirl flow generation within the channels. The hybrid flow-mixing device induces a complex but effective flow pattern in flow channels for fuel rod cooling.

    摘要翻译： 具有用于核燃料束的混合流动混合装置的间隔栅格由多个薄带的交叉点成直角形成用于接收和支撑燃料棒的多个单元。 每个条带由两种类型的带单元组成，称为主带单元和次级带单元，其沿着带交替布置。 主带单元是具有主叶片组的带部分，并且次级带单元是具有次级叶片组的带部分。 带子相交，使得通过初级和次级带单元，每个交叉点在每个结点的顶部周围形成混合流动混合装置。 主叶片组由梯形主叶片架和两侧的两个弯曲的初级混合叶片组成，从带子向上突出，主要用于在通道之间产生交叉流。 同时，由梯形二级叶片支架和两侧的两个弯曲的主要混合叶片组成的次级叶片组也从带子向上突出，但主要用于在通道内产生涡流。 混合流动混合装置在用于燃料棒冷却的流动通道中引起复杂但有效的流动模式。

    Method for decommissioning nuclear facilities
    69.
    发明授权
    Method for decommissioning nuclear facilities 有权

    公开(公告)号：US12002594B2

    公开(公告)日：2024-06-04

    申请号：US17437080

    申请日：2020-03-05

    申请人： KOREA HYDRO & NUCLEAR POWER CO., LTD.

    发明人： Young Hwan Hwang ,  Seok-Ju Hwang ,  Mi-Hyun Lee ,  Cheon-Woo Kim

    IPC分类号： G21D1/00

    CPC分类号： G21D1/003

    摘要： A method for decommissioning a nuclear facility includes: floating the nuclear reactor pressure vessel above the cavity; rotating the reactor pressure vessel so that the upper portion of the nuclear reactor pressure vessel is closer to the bio-protective concrete than the lower portion; mounting the upper portion of the nuclear reactor pressure vessel on the neighboring upper surface of the bio-protective concrete; and cutting and decommissioning the nuclear reactor pressure vessel mounted on the neighboring upper surface.