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1.发明申请FREE DROP TESTER FOR ALLOWING A FREE FALL IMPACT TEST OF NUCLEAR FUEL PELLET AT ADJUSTABLE ANGLE 审中-公开免费降落试验机，用于允许在可调角度下进行核燃料颗粒的自由落体试验公开(公告)号：US20150292998A1
公开(公告)日：2015-10-15
申请号：US14323045
申请日：2014-07-03
发明人： Tae Sik JEONG , Seung Jae Lee , Yong Kyoon Mok , Yoon Ho Kim , Chung Yong Lee , Yeon Soo Na , Min Young Choi , Dae Gyun Ko , Jae Ik Kim
IPC分类号： G01N3/303
CPC分类号： G01N3/303
摘要： Disclosed herein is a free drop tester wherein an angle of a test piece can be freely adjusted, a weight can fall on the exact spot, and an impulse of the weight can be controlled, and provides a free drop tester comprising a vertical guide disposed perpendicularly to the ground, a support body for supporting the vertical guide against the floor, a weight of which falling path is guided by the vertical guide, a test piece holder disposed under the bottom surface of the vertical guide, a horizontal rotation shaft of which one end is connected to a test piece holder, a power transmission unit connected to the other end of the horizontal rotation shaft, a test piece angle adjuster including a driving unit for supplying power to the power transmission unit, and a means for adjusting the height of the weight.
摘要翻译： 本文公开了一种自由落体试验机，其中可以自由地调节试件的角度，重量可以落在准确的位置上，并且可以控制重量的冲击，并且提供一种自由落体试验机，其包括垂直布置的垂直导向件 支撑体，用于将垂直引导件支撑在地板上，下垂轨道的重量由垂直引导件引导;设置在垂直引导件的底表面下方的测试片保持器，水平旋转轴，其中一个 连接到测试片保持器，连接到水平旋转轴的另一端的动力传递单元，测试片角度调节器，包括用于向动力传递单元供电的驱动单元，以及用于调节动力传递单元的高度的装置 重量。
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2.发明授权Zirconium alloy composition having low hydrogen pick-up rate and high hydrogen embrittlement resistance and method of preparing the same 有权具有低吸氢率和高耐氢脆性的低合金组成的锆合金组合物及其制备方法公开(公告)号：US09481921B2
公开(公告)日：2016-11-01
申请号：US14301405
申请日：2014-06-11
发明人： Yeon Soo Na , Yong Kyoon Mok , Yoon Ho Kim , Chung Yong Lee , Min Young Choi , Tae Sik Jeong , Jung Ho Shin , Seung Jae Lee , Jung Min Suh
摘要： Disclosed herein are zirconium alloy compositions having a low hydrogen pick-up rate and high hydrogen embrittlement resistance. This zirconium alloy composition can be usefully used as a nuclear fuel components in a nuclear power plant because it has a very low hydrogen pick-up rate and high hydrogen embrittlement resistance under operation environments of nuclear power plant.
摘要翻译： 本文公开了具有低吸氢速率和高耐氢脆性的锆合金组合物。 这种锆合金组合物可以有用地用作核电厂的核燃料组分，因为它在核电厂的操作环境下具有非常低的吸氢速率和高耐氢脆性。
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公开(公告)号：US11424042B2
公开(公告)日：2022-08-23
申请号：US16929614
申请日：2020-07-15
发明人： Yeon Soo Na , Kwang Young Lim , Tae Sik Jung , Min Jae Ju , Yoon Ho Kim , Seung Jae Lee
摘要： Provided is a nuclear-fuel sintered pellet based on oxide in which a plate-type fine precipitate material in a base of a sintered pellet of uranium dioxide, used as nuclear fuel in nuclear power plants, is uniformly dispersed in a matrix of uranium dioxide fuel thereof so as to form a donut-shaped precipitate cluster, and to a method of manufacturing the same. The plate-type fine precipitate material is uniformly precipitated in a tissue thereof or forms a donut-shaped precipitate cluster having a two-dimensional structure through dispersion to improve thermal and physical performance of the nuclear-fuel sintered pellet of uranium dioxide, whereby the creep deformation rate and thermal conductivity of the sintered pellet are improved. The nuclear-fuel sintered pellet based on oxide can reduce the Pellet-Clad Interaction (PCI) failure and the core temperature of nuclear fuel when an accident occurs, thereby significantly improving the safety of a nuclear reactor.
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4.发明授权公开(公告)号：US11195628B2
公开(公告)日：2021-12-07
申请号：US16677904
申请日：2019-11-08
发明人： Min Young Choi , Yong Kyoon Mok , Yoon Ho Kim , Yeon Soo Na , Chung Yong Lee , Hun Jang , Tae Sik Jung , Dae Gyun Go , Sung Yong Lee , Seung Jae Lee , Jae Ik Kim
摘要： A method of manufacturing a zirconium alloy for a nuclear fuel cladding tube includes melting a mixture of 0.5 wt % of Nb, 0.4 wt % of Mo, 0.1 to 0.15 wt % of Cu, 0.15 to 0.2 wt % of Fe, and a balance of zirconium to prepare a melted ingot; heat treating the melted ingot at 1,000 to 1,050° C. for 30 to 40 min. followed by quenching in water to prepare a heat-treated ingot; preheating the heat-treated ingot at 630 to 650° C. for 20 to 30 min. to prepare a preheated ingot followed by hot rolling the preheated ingot at a reduction ratio of 60 to 65% to provide a hot-rolled material; thrice performing vacuum annealing followed by cold-rolling; and vacuum annealing a third cold-rolled material in a final vacuum annealing at 510 to 520° C. for 7 to 9 hrs. to provide the zirconium alloy as a cold-rolled material.
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公开(公告)号：US20210202115A1
公开(公告)日：2021-07-01
申请号：US16929614
申请日：2020-07-15
发明人： Yeon Soo Na , Kwang Young Lim , Tae Sik Jung , Min Jae Ju , Yoon Ho Kim , Seung Jae Lee
摘要： Provided is a nuclear-fuel sintered pellet based on oxide in which a plate-type fine precipitate material in a base of a sintered pellet of uranium dioxide, used as nuclear fuel in nuclear power plants, is uniformly dispersed in a matrix of uranium dioxide fuel thereof so as to form a donut-shaped precipitate cluster, and to a method of manufacturing the same. The plate-type fine precipitate material is uniformly precipitated in a tissue thereof or forms a donut-shaped precipitate cluster having a two-dimensional structure through dispersion to improve thermal and physical performance of the nuclear-fuel sintered pellet of uranium dioxide, whereby the creep deformation rate and thermal conductivity of the sintered pellet are improved. The nuclear-fuel sintered pellet based on oxide can reduce the Pellet-Clad Interaction (PCI) failure and the core temperature of nuclear fuel when an accident occurs, thereby significantly improving the safety of a nuclear reactor.
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