利索-全球专利检索

  1. 登录
  2. 注册

搜索结果

14 条记录 (耗时 0.013 秒)

    Alkaline-permanganate process
    2.
    发明授权
    Alkaline-permanganate process 失效
    碱性高锰酸盐工艺

    公开(公告)号：US5278743A

    公开(公告)日：1994-01-11

    申请号：US979716

    申请日：1992-11-20

    申请人： Thomas G. Bengel ,  John F. Remark

    发明人： Thomas G. Bengel ,  John F. Remark

    IPC分类号： C23G1/00 ,  G21F9/00 ,  G21C19/42

    CPC分类号： C23G1/00 ,  G21F9/004

    摘要： An alkaline-permanganate process for chemically decontaminating oxidized metal surfaces wetted by primary water circulating in cooling loops of nuclear reactors maintains permanganate-containing primary water at a temperature of about 90.degree. C. and at a pH of 9-12 to oxidize the wetted surfaces. Oxalic acid is then added to the water and the oxalic acid-containing primary water is maintained at a temperature of at least about 90.degree. C. and at a pH of about 5-7 while it is circulated to destroy the permanganate ions and manganese dioxide.

    摘要翻译： 用于对在核反应堆的冷却回路中循环的初级水润湿的氧化金属表面进行化学去污的碱性高锰酸盐方法在约90℃的温度和9-12的pH下保持含高锰酸盐的初级水以氧化润湿表面 。 然后将草酸加入到水中，并且含草酸的一次水保持在至少约90℃的温度和约5-7的pH，同时循环以破坏高锰酸盐离子和二氧化锰 。

    System and method for cleaning the inner surface of tubular members
    3.
    发明授权
    System and method for cleaning the inner surface of tubular members 失效
    用于清洁管状构件内表面的系统和方法

    公开(公告)号：US5046289A

    公开(公告)日：1991-09-10

    申请号：US307103

    申请日：1989-02-06

    申请人： Thomas G. Bengel ,  Edward A. Ray ,  Phillip E. Miller ,  Frank I. Bauer ,  James Sejvar

    发明人： Thomas G. Bengel ,  Edward A. Ray ,  Phillip E. Miller ,  Frank I. Bauer ,  James Sejvar

    IPC分类号： B24C3/32 ,  G21F9/00

    CPC分类号： G21F9/005 ,  B24C3/325

    摘要： System and method for abrading radioactive contaminants from the inside surface of a pipe. The system includes a nozzle block capable of mixing a liquid and an abrasive grit into a suitable liquid-abrasive grit cleaning composition and impinging the cleaning composition against the inside surface of the pipe. The system further includes an inflatable torus-shaped seal for confining the liquid-abrasive grit cleaning composition to a predetermined portion of the inside surface of the pipe so that substantially all of the contaminants and cleaning composition can be suitably vacuumed from the surface.

    摘要翻译： 从管内表面研磨放射性污染物的系统和方法。 该系统包括能够将液体和磨料砂粒混合到合适的液体磨料砂粒清洁组合物中并将清洁组合物抵靠在管的内表面上的喷嘴块。 该系统还包括一个可膨胀的环形密封件，用于将液体磨料砂粒清洁组合物限制在管子内表面的预定部分，使得基本上所有的污染物和清洁组合物都可以从表面被适当地抽真空。

    Reactor coolant pump seal test decontamination housing
    5.
    发明授权
    Reactor coolant pump seal test decontamination housing 失效
    反应器冷却液泵密封试验去污室

    公开(公告)号：US5465279A

    公开(公告)日：1995-11-07

    申请号：US303901

    申请日：1994-09-09

    申请人： Thomas G. Bengel

    发明人： Thomas G. Bengel

    IPC分类号： G21C17/00

    CPC分类号： G21C17/00 ,  G21Y2002/204 ,  G21Y2004/30 ,  G21Y2004/302

    摘要： An arrangement of reactor coolant pump seals arranged in a generally annular stack with a plurality of stacking spacers in a test housing for emplacement in a chemical decontamination test loop enables a variety of flow characteristics to be simulated by varying the detailed arrangement of the RCP seals and supporting structure in the test housing. By adjusting parameters such as fluid chemistry, gross flow, pressure, and temperature in a controlled manner with systems incorporated into the test loop, additional information can be obtained regarding the feasibility of any specific decontamination process. The magnitude of process fluid flow across particular surfaces of one or more RCP seal components can be predetermined by selecting the placement, number and dimensions of penetrations in a flow distribution tube through which the process fluid enters the housing. The penetrations feed the process fluid to channels in selected stacking spacers, thereby directing the process fluid flow to selected seal surfaces. The arrangement of the stacked seal assembly also assures that each of the seal components will experience a process fluid flow similar to what would be experienced in an in situ decontamination procedure in an RCP.

    摘要翻译： 布置在通常环形堆叠中的反应堆冷却剂泵密封件的布置在测试壳体中的多个堆叠间隔件中，用于放置在化学去污测试环路中，使得可以通过改变RCP密封件的详细布置来模拟各种流动特性， 支撑结构在试验室。 通过使用结合到测试回路中的系统以受控的方式调整诸如流体化学，总流量，压力和温度的参数，可以获得关于任何特定去污过程的可行性的附加信息。 可以通过选择流量分配管中的渗透物的位置，数量和尺寸来确定过程流体流过一个或多个RCP密封部件的特定表面的大小，通过该流量分配管中的过程流体进入壳体。 穿透物将工艺流体供给到所选择的堆叠间隔件中的通道，从而将工艺流体流引导到选定的密封表面。 堆叠的密封组件的布置还确保每个密封部件将经历类似于在RCP中的原位去污程序中将经历的过程流体流。

    Process for decontaminating a nuclear reactor coolant system
    6.
    发明授权
    Process for decontaminating a nuclear reactor coolant system 失效
    净化核反应堆冷却剂系统的过程

    公开(公告)号：US5305360A

    公开(公告)日：1994-04-19

    申请号：US18138

    申请日：1993-02-16

    申请人： John F. Remark ,  Thomas G. Bengel

    发明人： John F. Remark ,  Thomas G. Bengel

    IPC分类号： G21C17/022 ,  G21C19/307 ,  G21D1/00 ,  G21C19/28

    CPC分类号： G21C17/0225 ,  G21C19/307 ,  G21D1/003 ,  G21Y2002/303 ,  G21Y2004/403

    摘要： High velocity reactor coolant water in a boiling water reactor or a pressurized water reactor transports radioactive ions and particles from a nuclear reactor vessel to the balance of the reactor coolant system where they deposit on chromium (III) oxide-containing surfaces. These radioactive deposits are removed in a dilute chemical decontamination process wherein permanganate ion-containing reactor coolant water is circulated throughout a reactor coolant system to oxidize chromium (III) oxide surfaces of the system to chromium (IV) oxide. Formic acid is added to the permanganate ion-containing reactor coolant water and then the formic acid-containing water is circulated throughout the reactor coolant system to reduce unreacted permanganate ions in the reactor coolant water to manganous ions.

    摘要翻译： 沸水反应堆或加压水反应堆中的高速反应堆冷却水将放射性离子和颗粒从核反应堆运输到反应堆冷却剂系统的平衡，其中它们沉积在含铬（III）氧化物的表面上。 这些放射性沉积物在稀释的化学去污过程中被除去，其中含高锰酸盐离子的反应堆冷却水循环通过反应堆冷却剂系统，以将体系的氧化铬（III）表面氧化成氧化铬（IV）。 将甲酸加入到含高锰酸盐离子的反应堆冷却水中，然后含甲酸的水在整个反应堆冷却剂系统中循环，以将反应堆冷却水中的未反应的高锰酸盐离子还原成二价锰离子。

    Crack propagation test specimen
    7.
    发明授权
    Crack propagation test specimen 失效
    裂纹传播试样

    公开(公告)号：US5292481A

    公开(公告)日：1994-03-08

    申请号：US015962

    申请日：1993-02-08

    申请人： Robert G. Aspden ,  Thomas G. Bengel

    发明人： Robert G. Aspden ,  Thomas G. Bengel

    IPC分类号： G01N3/00 ,  G01N17/00 ,  G01N17/04

    CPC分类号： G01N17/00 ,  G01N3/00 ,  G01N2203/0066

    摘要： A crack propagation test specimen has a base metal and a clad metal. The base metal has an upper surface and a bottom surface with a hole extending from the bottom surface toward the upper surface. The cladding metal is supported on the upper surface of the base metal and has a first slot cut therethrough which is in fluid flow communication with the hole in the base metal. A second slot is cut in the cladding metal adjacent to the first slot for receiving a wedge. The first slot and the second slot define a wall which closes over the first slot when a wedge is forced into the second slot to simulate a hairline crack. A mechanically deformed metal sample is disposed in the hole in the base metal to simulate a stressed base metal supporting a cladding metal subject to hairline cracking.

    摘要翻译： 裂纹扩展试样具有贱金属和复合金属。 贱金属具有从底面向上表面延伸的孔的上表面和底面。 包层金属被支撑在基底金属的上表面上，并且具有穿过其中切割的第一槽，其与母材中的孔流体流动连通。 在与第一槽相邻的包层金属中切割第二槽以接收楔。 当楔形物被迫进入第二槽以模拟发际裂纹时，第一槽和第二槽限定了封闭在第一槽上的壁。 机械变形的金属样品设置在基底金属的孔中，以模拟支撑受发丝破裂的包层金属的应力基底金属。

    System for qualification of chemical decontamination methods for decontamination of nuclear reactor systems
    8.
    发明授权
    System for qualification of chemical decontamination methods for decontamination of nuclear reactor systems 失效
    核反应堆系统去污化学去污方法资格制度

    公开(公告)号：US5126100A

    公开(公告)日：1992-06-30

    申请号：US633888

    申请日：1990-12-26

    申请人： Thomas G. Bengel ,  Gary J. Corpora ,  Robert M. Roidt ,  James S. Schlonski

    发明人： Thomas G. Bengel ,  Gary J. Corpora ,  Robert M. Roidt ,  James S. Schlonski

    IPC分类号： G21C17/00

    CPC分类号： G21C17/00

    摘要： A unique and optimal method for assessing the feasibility of employing chemical decontamination processes to remove crud from nuclear reactor primary systems without adversely affecting the integrity of the system components or piping during further reactor operation is disclosed. Materials used to construct such components and piping are exposed to several cycles of simulated decontamination processing with a test loop constructed to simulate a range of full system decontamination process conditions. The material specimens are then removed and tested to assure that the particular decontamination processing system has no adverse effects on the materials used.

    摘要翻译： 公开了一种独特和最佳的方法，用于评估在进一步的反应器操作期间使用化学去污过程从核反应堆主系统中除去原油而不会不利地影响系统部件或管道的完整性的可行性。 用于构建这种组分和管道的材料暴露于几个循环的模拟去污处理，其中建立了用于模拟一系列完全系统去污工艺条件的测试回路。 然后将材料样品取出并进行测试，以确保特定的去污处理系统对所用材料没有不利影响。

    Clean-up system for the chemical decontamination of a nuclear reactor primary system
    10.
    发明授权
    Clean-up system for the chemical decontamination of a nuclear reactor primary system 失效
    核反应堆主要系统的化学除污清理系统

    公开(公告)号：US5325410A

    公开(公告)日：1994-06-28

    申请号：US983503

    申请日：1992-11-30

    申请人： Gary J. Corpora ,  Frank I. Bauer ,  Thomas G. Bengel ,  Phillip E. Miller

    发明人： Gary J. Corpora ,  Frank I. Bauer ,  Thomas G. Bengel ,  Phillip E. Miller

    IPC分类号： G21C19/307 ,  G21F9/12 ,  G21C19/42

    CPC分类号： G21F9/12 ,  G21C19/307 ,  G21Y2002/201 ,  G21Y2004/305

    摘要： A chemical decontamination clean-up system for use on-line in a nuclear reactor primary system includes a pump arrangement within the nuclear reactor primary system for pumping primary system fluids to a cleaning system located directly downstream from the pump assembly. The cleaning system includes a plurality of first demineralizer banks arranged in a predetermined flow pattern for receiving the primary system fluids. Each of the first demineralizer banks comprises at least two individual, resin-filled demineralizers arranged in parallel wherein primary system fluids are demineralized. Each of the demineralizer banks includes valving for selectively directing the primary system fluids from the pump arrangement to selected demineralizer banks in the plurality of the first demineralizer banks. A second demineralizer bank receives the primary system fluids from the plurality of first demineralizer banks. The second demineralizer bank includes at least two individual, resin-filled demineralizers arranged in parallel wherein primary system fluids are "finish" demineralized. A return system receives the primary system fluids from the second demineralizer bank and directs the fluids back to the nuclear reactor primary system. The return system includes at least one trap for receiving the primary system fluids from the second demineralizer bank and operable to remove resin suspended in the primary system fluids, and at least one filter downstream from the trap for removing solids suspended in the primary system fluids prior to the return of the fluids to the nuclear reactor primary system.

    摘要翻译： 在核反应堆主系统中在线使用的化学净化清理系统包括在核反应堆主系统内的泵装置，用于将初级系统流体泵送到位于泵组件正下游的清洁系统。 清洁系统包括以预定的流动方向布置的用于接收主要系统流体的多个第一去矿化剂组。 每个第一脱盐剂组包括平行布置的至少两个单独的充满树脂的脱盐装置，其中主系统流体被软化。 每个软化器组包括阀，用于将主系统流体从泵装置选择性地引导到多个第一脱盐剂组中的选定的脱盐剂组。 一个第二脱盐机组从多个第一脱盐机组接收主系统流体。 第二脱盐器组包括平行布置的至少两个单独的树脂充填的软化器，其中主系统流体被“完成”去矿物质。 返回系统接收来自第二脱盐器组的主系统流体并将流体引导回到核反应堆主系统。 返回系统包括至少一个用于从第二脱盐剂组接收主要系统流体的捕集器，并可操作以移除悬浮在主系统流体中的树脂，以及至少一个过滤器下游的过滤器，用于去除悬浮在主系统流体中的固体 将流体返回到核反应堆主要系统。