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    Process for the Accurate Characterization of Low Level Nuclear Waste
    3.
    发明申请
    Process for the Accurate Characterization of Low Level Nuclear Waste 审中-公开
    准确表征低级核废料的过程

    公开(公告)号：US20160203881A1

    公开(公告)日：2016-07-14

    申请号：US14186536

    申请日：2014-02-21

    申请人： David W James ,  Tom Kalinowski

    发明人： David W James ,  Tom Kalinowski

    IPC分类号： G21C17/00 ,  G21F9/12 ,  G21C17/022 ,  G21F9/00

    CPC分类号： G21C17/002 ,  G21C17/022 ,  G21C19/307 ,  G21F9/12

    摘要： A method of accurately determining and quantifying the presence and concentration of various regulated radionuclides present in the filter material used to remove contaminants from the cooling water of a nuclear reactor. Multiple samples of the reactor cooling water are taken and the presence and concentration of directly measurable fission produced radionuclides and their related isotopes are determined. The release rate of radioactivity from the reactor as a function of the removal rate of the filter material is determined at equilibrium. The presence and the concentration of difficult to detect fission produced regulated isotopes as a function of release rates of the directly measurable fission produced isotopes are then calculated. The total concentration of activation produced regulated isotopes is based on measured surrogate isotopes. A running total of the concentration of the directly and difficult to detect fission produced regulated isotopes and of the activation produced regulated isotopes accumulated in the filter material is calculated and retained over a defined period of time. The contribution of any regulated radionuclides from secondary sources such as a spent fuel pool can also be measured and added to the total of the fission and activation produced radionuclides in the filter material.

    摘要翻译： 准确地确定和定量存在于用于从核反应堆的冷却水中除去污染物的过滤材料中的各种调节放射性核素的存在和浓度的方法。 采取反应堆冷却水的多个样品，并确定直接可测量裂变的存在和浓度产生放射性核素及其相关同位素。 在平衡时确定作为过滤材料去除速率的函数的来自反应器的放射性的释放速率。 然后计算难以检测裂变的存在和浓度产生的调节同位素作为可直接测量的裂变产生的同位素的释放速率的函数。 产生调节同位素的总活化浓度是基于测量的替代同位素。 直接和难以检测裂变的浓度的运行总计在过滤材料中累积的调节同位素和激活产生的调节同位素的计算和保留在一段确定的时间内。 任何受调节的放射性核素来自次级来源（如乏燃料池）的贡献也可以被测量并添加到过滤材料中产生的放射性核素的裂变和活化的总和中。

    Radiation exposure reduction method
    4.
    发明授权
    Radiation exposure reduction method 有权
    辐射曝光减少法

    公开(公告)号：US08798225B2

    公开(公告)日：2014-08-05

    申请号：US13127503

    申请日：2009-11-04

    申请人： Yumi Yaita ,  Seiji Yamamoto ,  Hajime Hirasawa ,  Yutaka Uruma

    发明人： Yumi Yaita ,  Seiji Yamamoto ,  Hajime Hirasawa ,  Yutaka Uruma

    IPC分类号： G21C19/30 ,  G21C7/06 ,  G21C19/00 ,  G21C7/00

    CPC分类号： G21F1/106 ,  G21C19/307 ,  G21D3/08 ,  Y02E30/40

    摘要： A radiation exposure reduction method includes the steps of: injecting iron into a coolant which flows from the reactor cooling system to the reactor core in a nuclear power plant; and ferritizing and fixing radionuclides or parent nuclides thereof, which are contained in the coolant, on the surface of a reactor core structure, wherein an iron citrate which is soluble organic iron, or iron oxalate or iron fumarate which has a particle diameter of 3 μm or less, is used as the iron to be injected into the coolant.

    摘要翻译： 放射线曝光降低方法包括以下步骤：将铁注入从反应堆冷却系统流到核电站中的反应堆堆芯的冷却剂中; 并且将包含在冷却剂中的放射性核素或其母体核素铁氧化并固定在反应堆芯结构的表面上，其中可溶性有机铁的柠檬酸铁或草酸铁或富马酸铁具有3μm的粒径 或更少，被用作要注入冷却剂的铁。

    ENHANCED NUCLEAR SUMP STRAINER SYSTEM
    5.
    发明申请
    ENHANCED NUCLEAR SUMP STRAINER SYSTEM 有权
    增强型核压力系统

    公开(公告)号：US20130208847A1

    公开(公告)日：2013-08-15

    申请号：US13396396

    申请日：2012-02-14

    申请人： CARL PRATHER ,  Denis Grob ,  Claes Lemcke

    发明人： CARL PRATHER ,  Denis Grob ,  Claes Lemcke

    IPC分类号： G21C19/00

    CPC分类号： G21C19/307 ,  B01D29/27 ,  B01D29/52 ,  B01D29/58 ,  B01D35/30 ,  G21C15/18

    摘要： In accordance with the present invention, there is provided a strainer system for use in a nuclear sump. The strainer system of the present invention includes at least one primary strainer module which defines a primary strainer/filter surface. In the strainer system, the primary strainer surface of the primary strainer module has a debris interceptor which is cooperatively engaged thereto, and may be outfitted with one or more pressure released or activated membranes. In a loss of coolant accident, the debris interceptor, alone or in combination with the pressure activated membrane(s), is adapted to reduce the differential pressure experienced across the strainer system in nuclear power plants with medium to high fiber loads.

    摘要翻译： 根据本发明，提供了一种用于核储罐的过滤器系统。 本发明的过滤器系统包括限定一次过滤器/过滤器表面的至少一个主过滤器模块。 在过滤器系统中，主过滤器模块的主过滤器表面具有与其配合接合的碎屑拦截器，并且可以配备一个或多个压力释放或活化的膜。 在冷却剂事故的损失中，单独或与压力活化膜组合的碎片拦截器适于减少在具有中等至高纤维负载的核电厂中过滤器系统所经历的差压。

    Method of suppressing deposition of radioactive isotope
    7.
    发明授权
    Method of suppressing deposition of radioactive isotope 有权
    抑制放射性同位素沉积的方法

    公开(公告)号：US08259894B2

    公开(公告)日：2012-09-04

    申请号：US11768437

    申请日：2007-06-26

    申请人： Hideyuki Hosokawa ,  Makoto Nagase ,  Satoshi Morisawa ,  Motoaki Sakashita ,  Katsuo Yokota

    发明人： Hideyuki Hosokawa ,  Makoto Nagase ,  Satoshi Morisawa ,  Motoaki Sakashita ,  Katsuo Yokota

    IPC分类号： G21C9/00

    CPC分类号： G21C19/307 ,  G21Y2002/103 ,  G21Y2004/40

    摘要： A formic acid aqueous solution that contains Fe (II) ions is produced by dissolving metal iron in a formic acid aqueous solution. Nitrogen is supplied from a nitrogen supply device to a chemical liquid tank and then discharged from a discharge line to reduce the dissolved oxygen concentration in the aqueous solution. The chemical liquid tank is filled with the formic acid aqueous solution sealed with nitrogen, and transferred from a factory to a nuclear reactor building designated as radiation-controlled areas. Inside the nuclear reactor building, the chemical liquid tank is installed in a film deposition apparatus connected to a reactor water recirculation pipeline. The formic acid aqueous is supplied from the chemical liquid tank to the inside of the reactor water recirculation pipeline, and then a ferrite film is formed on the inner surface of the reactor water recirculation pipeline.

    摘要翻译： 含有Fe（II）离子的甲酸水溶液是通过将金属铁溶解在甲酸水溶液中制成的。 氮气从氮气供给装置供给到药液罐，然后从排出管路排出，以降低水溶液中的溶解氧浓度。 化学液体罐用氮气密封的甲酸水溶液填充，并从工厂转移到指定为辐射控制区的核反应堆。 在核反应堆建筑物内部，化学液体罐安装在连接到反应堆水再循环管道的成膜装置中。 甲酸水溶液从化学液体罐供应到反应器水循环管道的内部，然后在反应器水循环管道的内表面上形成铁氧体膜。

    METHOD OF INHIBITING ADHESION OF RADIOACTIVE SUBSTANCE AND APPARATUS INHIBITED FROM SUFFERING ADHESION THEREOF
    10.
    发明申请
    METHOD OF INHIBITING ADHESION OF RADIOACTIVE SUBSTANCE AND APPARATUS INHIBITED FROM SUFFERING ADHESION THEREOF 审中-公开
    抑制放射性物质粘附的方法及其抑制剂的抑制作用

    公开(公告)号：US20110122986A1

    公开(公告)日：2011-05-26

    申请号：US12674168

    申请日：2008-08-21

    申请人： Seiji Yamamoto ,  Masami Enda ,  Hiromi Aoi ,  Yutaka Uruma

    发明人： Seiji Yamamoto ,  Masami Enda ,  Hiromi Aoi ,  Yutaka Uruma

    IPC分类号： G21C9/00

    CPC分类号： G21C7/10 ,  G21C13/08 ,  G21C15/16 ,  G21C17/0225 ,  G21C19/02 ,  G21C19/307 ,  G21D1/00 ,  G21F9/00 ,  G21F9/28 ,  Y02E30/39

    摘要： The present invention relates to a method and an apparatus for suppressing adhesion of a radioactive substance, capable of suppressing adhesion of the radioactive substance onto the surface of a metallic material forming a structural member in a nuclear plant. On the surface of the metallic material forming the structural member in a nuclear power generation plant, e.g., a surface 32A of a pipe 32, an adhesion-suppressing substance 34 containing titanium oxide as a titanium compound is disposed, and a part on which the adhesion-suppressing substance 34 has been formed, is held at 80° C. or higher. The adhesion-suppressing substance 34 is formed on the surface 32A of the pipe 32 by spraying a solution or a suspension liquid of the substance.

    摘要翻译： 本发明涉及一种抑制放射性物质粘附的方法和装置，其能够抑制放射性物质粘附在形成核电站的结构构件的金属材料的表面上。 在核发电厂（例如管32的表面32A）的形成结构部件的金属材料的表面上，设置含有氧化钛作为钛化合物的粘合抑制物质34， 已经形成粘附抑制物质34，保持在80℃以上。 通过喷射物质的溶液或悬浮液，在管32的表面32A上形成粘合抑制物质34。