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1.发明申请公开(公告)号：US20160358675A1
公开(公告)日：2016-12-08
申请号：US14550900
申请日：2014-11-21
发明人： Wenchi Yu , Xiaoming Chen , Xianfeng Lv , Weicai Li , Yuemin Zhou , Yahong Hu , Shilei Li
CPC分类号： G21C3/331 , G21C3/322 , G21C5/06 , G21Y2002/30 , G21Y2004/30 , Y02E30/38
摘要： A nuclear core component hold-down assembly includes a hollow spring guide in which an instrumentation insertion channel is formed; a base plate which has a center hole formed through a center thereof, and several water flow holes formed around the center hole; a lower end of the spring guide connecting and mating with an upper end of the base plate, the instrumentation insertion channel communicating with the center hole, and the base plate locating above the adapter plate and pressing against it directly; a hold-down bar slidably mounted on an upper end of the spring guide and locating above the base plate; and a spring element configured between the hold-down bar and the base plate, by which the hold-down bar pushes the base plate to cause the base plate to press against the adapter plate. The structure is stable and reliable.
摘要翻译： 核芯部件压紧组件包括中空弹簧引导件，其中形成有仪表插入通道; 具有形成在其中心的中心孔的基板和形成在中心孔周围的若干水流孔; 弹簧引导件的下端与基板的上端连接并配合，与中心孔连通的仪表插入通道和位于适配器板上方的基板直接按压; 可滑动地安装在弹簧引导件的上端并定位在基板上方的压紧杆; 以及弹簧元件，其构造在所述压紧杆和所述基板之间，所述压紧杆通过所述弹簧元件推动所述基板，以使所述基板压靠所述适配器板。 结构稳定可靠。
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公开(公告)号：US09767929B2
公开(公告)日：2017-09-19
申请号：US13783426
申请日：2013-03-04
发明人： Wenchi Yu , Yuemin Zhou , Weicai Li , Xiaoming Chen , Zhengzheng Pang , Jingwen Yan , Yan Guo
CPC分类号： G21C3/336 , G21C3/352 , G21C2003/3432 , Y02E30/40
摘要： A new, improved grid spacer for a nuclear fuel assembly is provided, comprising several straps which intersect each other alternatively to form a plurality of grid cells and fuel rods reside in some of the grid cells; the grid spacer further comprises mixing elements set at the corner of the grid cells in which the fuel rods have resided; wherein the mixing element comprises a mixing vane stretching towards the direction of the fuel rod and a flow funnel set on the bended edge of the mixing vane continuously and extending towards adjacent grid cells; the mixing vane and the flow funnel set across two sides of two adjacent grid cells respectively, and the flow funnel introduces the coolant in the grid cell at its side to the mixing vane, then the mixing vane introduces the coolant to the grid cell at its own side.
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3.发明申请NUCLEAR POWER PLANT CONTAINMENT COOLING SYSTEM AND SPRAY FLOW CONTROL METHOD THEREFOR 审中-公开核电厂容量冷却系统及喷雾流量控制方法公开(公告)号：US20160372218A1
公开(公告)日：2016-12-22
申请号：US15111480
申请日：2014-01-13
发明人： Jiang Yang , Ting Wang , Jun Tao , Jun Cui , Xianghui Lu , Zhengfeng Shang , Chengjun Zhuang , Weiqing Lin , Jianshu Lin
IPC分类号： G21C15/18
摘要： A nuclear power plant containment cooling system and a spray flow control method therefor. The system comprises a cooling system liquid tank (2) for storing cooling liquid, wherein the cooling system liquid tank (2) is provided at the top of a containment (1) and the cooling liquid is used for cooling the containment (1) through the gravity of the cooling liquid itself in the situation of an accident, and the cooling liquid is partially evaporated. The nuclear power plant containment cooling system further comprises an adjustment mechanism; wherein the adjustment mechanism is provided at a liquid outlet of the cooling system liquid tank (2), and the adjustment mechanism is used for controlling the flow at the liquid outlet according to buoyancy generated by a liquid level of the collected cooling liquid which is not evaporated.
摘要翻译： 一种核电厂遏制冷却系统及其喷流控制方法。 该系统包括用于存储冷却液体的冷却系统液罐（2），其中冷却系统液罐（2）设置在容器（1）的顶部，冷却液用于冷却容纳物（1）通过 在事故情况下冷却液本身的重力，冷却液部分蒸发。 核电站安全壳冷却系统还包括调整机构; 其特征在于，所述调整机构设置在所述冷却系统液罐（2）的液体出口处，并且所述调节机构用于根据不是所述收集的冷却液体的液面产生的浮力来控制所述液体出口处的流量 蒸发
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公开(公告)号：US20160336080A1
公开(公告)日：2016-11-17
申请号：US15187176
申请日：2013-12-20
申请人： CHINA NUCLEAR POWER TECHNOLOGY RESEARCH INSTITUTE CO., LTD. , CHINA GRNERAL NUCLEAR POWER CO., LTD.
发明人： Wenchi Yu , Weical Li , Haixiang Hu , Jiayuan Wang
IPC分类号： G21C3/32
CPC分类号： G21C3/3206 , G21C3/32 , G21C3/3305 , Y02E30/40
摘要： A bottom nozzle includes a skirt, support blocks, transverse blades and longitudinal blades. The skirt is a hollow structure and a bottom thereof is provided with corner legs which are protruded downwards, a cavity is defined in the hollow structure, the transverse blades are configured in the cavity, the longitudinal blades are configured in the cavity, the transverse blades and longitudinal blades are firmly connected with the skirt, projections of the transverse blades and the longitudinal blades in a level plane are intersectant to form interleaved grids, and the support blocks run through and are fixed on the transverse blades and the longitudinal blades. In such a way, the bottom nozzle forms a three-dimensional gridded water passage, thereby improving the filter capacity and generating small water pressure drop.
摘要翻译： 底部喷嘴包括裙部，支撑块，横向叶片和纵向叶片。 裙部是中空结构，其底部设置有向下突出的角腿，空腔被限定在中空结构中，横向叶片构造在空腔中，纵向叶片构造在空腔中，横向叶片 并且纵向叶片与裙部牢固地连接，横向叶片的突出物和水平面中的纵向叶片相交，以形成交错的格栅，并且支撑块穿过并固定在横向叶片和纵向叶片上。 以这种方式，底部喷嘴形成三维网格水通道，从而提高过滤能力并产生小的水压降。
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公开(公告)号：US10418135B2
公开(公告)日：2019-09-17
申请号：US15187176
申请日：2013-12-20
申请人： China Nuclear Power Technology Research Institute Co., Ltd , China General Nuclear Power Co., Ltd
发明人： Wenchi Yu , Weicai Li , Haixiang Hu , Jiayuan Wang
摘要： A bottom nozzle includes a skirt, support blocks, transverse blades and longitudinal blades. The skirt is a hollow structure and a bottom thereof is provided with corner legs which are protruded downwards, a cavity is defined in the hollow structure, the transverse blades are configured in the cavity, the longitudinal blades are configured in the cavity, the transverse blades and longitudinal blades are firmly connected with the skirt, projections of the transverse blades and the longitudinal blades in a level plane are intersectant to form interleaved grids, and the support blocks run through and are fixed on the transverse blades and the longitudinal blades. In such a way, the bottom nozzle forms a three-dimensional gridded water passage, thereby improving the filter capacity and generating small water pressure drop.
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公开(公告)号：US20130230133A1
公开(公告)日：2013-09-05
申请号：US13783426
申请日：2013-03-04
发明人： Wenchi Yu , Yuemin Zhou , Weicai Ll , Xiaoming Chen , Zhengzheng Pang , Jingwen Yan , Yan Guo
IPC分类号： G21C3/336
CPC分类号： G21C3/336 , G21C3/352 , G21C2003/3432 , Y02E30/40
摘要： A new, improved grid spacer for a nuclear fuel assembly is provided, comprising several straps which intersect each other alternatively to form a plurality of grid cells and fuel rods reside in some of the grid cells; the grid spacer further comprises mixing elements set at the corner of the grid cells in which the fuel rods have resided; wherein the mixing element comprises a mixing vane stretching towards the direction of the fuel rod and a flow funnel set on the bended edge of the mixing vane continuously and extending towards adjacent grid cells; the mixing vane and the flow funnel set across two sides of two adjacent grid cells respectively, and the flow funnel introduces the coolant in the grid cell at its side to the mixing vane, then the mixing vane introduces the coolant to the grid cell at its own side.
摘要翻译： 提供了一种用于核燃料组件的新的改进的格栅间隔件，其包括多个彼此相交的带，以形成多个网格单元，并且燃料棒位于一些网格单元中; 栅格间隔物还包括设置在燃料棒所在的格栅单元角落处的混合元件; 其中所述混合元件包括朝向所述燃料棒的方向延伸的混合叶片和连续地设置在所述混合叶片的弯曲边缘上并朝向相邻格栅单元延伸的流道; 混合叶片和流动漏斗分别设置在两个相邻的格栅单元的两侧，流道将其侧面的格栅池中的冷却剂引入混合叶片，然后混合叶片将冷却剂引入其网格单元 自己的一面
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公开(公告)号：US20180350472A1
公开(公告)日：2018-12-06
申请号：US15527906
申请日：2015-07-03
发明人： Xiangang Fu
CPC分类号： G21C15/182 , G21C9/012 , Y02E30/40
摘要： A passive safe cooling system includes a water replenishing tank, an advanced safe injection tank, a built-in material replacing water tank, a pressure relief system, a passive emergency water supply system and a passive containment cooling system, the passive emergency water supply system is adapted for hermetically running through the containment and is configured correspondingly to a steam generator in the containment, and the passive containment cooling system is adapted for hermetically running through the containment to remove the heat from the containment. This system can effectively implement safety functions such as nuclear core reactivity control, residual heat removal and containment of radioactive material under a nuclear accident, ensure the reactor core to be effectively cooled down and maintain in a safe shutdown state, improve the safety of the nuclear power plant and greatly reduce the construction costs and operation and maintenance costs.
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