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    • 1. 发明授权
    • Ingot-casting apparatus using uranium deposits
    • 使用铀矿床的铸造设备
    • US08127823B2
    • 2012-03-06
    • US12625134
    • 2009-11-24
    • Yoon Sang LeeHan Soo Lee
    • Yoon Sang LeeHan Soo Lee
    • B22D7/00B22D7/06B22D41/00
    • B22D35/04B22C9/00B22D7/00
    • A casting apparatus includes a hermetically sealed chamber, wherein the chamber includes: a melt-heating portion to melt external uranium deposits, the melt-heating portion being tiltable to allow the resulting liquid molten material to be discharged to the outside, an ingot-forming portion to receive the molten material discharged from the melt-heating portion and to cool-solidify the molten material, and a salt-capturing portion provided on the melt-heating portion, to solidify a salt gas produced when the uranium deposits are molten, and thereby recover the salt gas, wherein the ingot-forming portion includes: a horizontal turn-table rotated by an operating means, and a plurality of molds mounted on the edge of the turn-table, each containing the molten material, which is then cooled.
    • 铸造装置包括密封室,其中所述室包括:熔融加热部分,用于熔化外部铀沉积物,所述熔融加热部分可倾斜以允许所得液体熔融材料排出到外部,铸锭形成 接收从熔融加热部分排出的熔融材料并冷却熔融材料的部分,以及设置在熔融加热部分上的盐捕获部分,以固化当铀沉积物熔融时产生的盐气;以及 从而回收盐气,其中锭形成部分包括:由操作装置旋转的水平转台,以及安装在转台的边缘上的多个模具,每个模具包含熔融材料,然后冷却 。
    • 8. 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
    • 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
    • US20070036261A1
    • 2007-02-15
    • US11269104
    • 2005-11-08
    • Chang Kyu KimEun JungYoon Sang LeeHo Ryu
    • Chang Kyu KimEun JungYoon Sang LeeHo Ryu
    • G21C3/00
    • G21C3/02Y02E30/40
    • 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.
    • 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。