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14 条记录 (耗时 0.018 秒)

    Method and system for maintaining pressure in a nuclear power plant primary loop during startup or shutdown
    1.
    发明授权
    Method and system for maintaining pressure in a nuclear power plant primary loop during startup or shutdown 失效
    在启动或关闭期间维持核电厂主回路压力的方法和系统

    公开(公告)号：US5491731A

    公开(公告)日：1996-02-13

    申请号：US270273

    申请日：1994-07-05

    申请人： Gary J. Corpora ,  Thomas G. Bengel ,  Elwyn L. Cranford, III

    发明人： Gary J. Corpora ,  Thomas G. Bengel ,  Elwyn L. Cranford, III

    IPC分类号： G21C1/09 ,  G21C7/00

    CPC分类号： G21C1/09 ,  G21Y2002/205 ,  G21Y2002/501 ,  G21Y2004/401 ,  Y02E30/40

    摘要： An automated method for maintaining pressure within a nuclear power plant primary loop during either startup or shutdown, the method comprises the steps of partially filling a portion of a pressurizer vessel, in fluid communication with the primary loop, with a liquid for maintaining pressure in the primary loop; circulating a primary coolant through the primary loop; automatically injecting an inert gas by a first automated device, operatively connected to the pressurizer, into the pressurizer vessel when the pressure in the pressurizer vessel is less than a first predetermined pressure; and automatically venting the gas by a second automated device, operatively connected to the pressurizer, from the pressurizer vessel when the pressure in the pressurizer vessel is greater than a second predetermined pressure.

    摘要翻译： 一种用于在启动或关闭期间保持核电厂初级回路内的压力的自动化方法，该方法包括以下步骤：将与主回路流体连通的一部分加压容器部分地填充以保持压力在 主回路; 使主冷却剂循环通过初级回路; 当加压容器中的压力小于第一预定压力时，通过可操作地连接到加压器的第一自动装置自动地将惰性气体注入加压器容器中; 并且当加压器容器中的压力大于第二预定压力时，通过可操作地连接到加压器的第二自动装置从加压器容器自动排出气体。

    Clean-up system for the chemical decontamination of a nuclear reactor primary system
    2.
    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。

    Method of decontaminating a PWR primary loop
    3.
    发明授权
    Method of decontaminating a PWR primary loop 失效
    对PWR主回路进行净化的方法

    公开(公告)号：US5517539A

    公开(公告)日：1996-05-14

    申请号：US356820

    申请日：1994-12-15

    申请人： Gary J. Corpora ,  Phillip E. Miller ,  Thomas G. Bengel ,  David R. Peffer

    发明人： Gary J. Corpora ,  Phillip E. Miller ,  Thomas G. Bengel ,  David R. Peffer

    IPC分类号： G21C19/30 ,  G21C19/42

    CPC分类号： G21C19/30 ,  G21Y2002/303 ,  G21Y2004/40

    摘要： In a method of decontaminating a primary loop of a pressurized water reactor, including a steam generator, reactor coolant pump and hot and cold legs in the loop, the primary loop is isolated from a nuclear reactor vessel by closing hot leg and cold leg loop stop valves. Decontamination process water is circulated from one side of the steam generator channel head to the other side of the channel head via a bypass pipe extending between the cold leg and the hot leg without bypassing the water through steam generator tubes extending between the sides of the channel head. The level of the decontamination water in the steam generator is maintained at two to three feet in the tubes.

    摘要翻译： 在对包括蒸汽发生器，反应堆冷却剂泵以及回路中的冷热腿的压水反应堆的主回路进行净化的方法中，通过闭合热腿和冷腿循环停止将主回路与核反应堆隔离 阀门 净化处理水通过在冷腿和热腿之间延伸的旁通管而从蒸汽发生器通道头的一侧循环到通道头的另一侧，而不会通过在通道的两侧之间延伸的蒸汽发生器管绕过水 头。 蒸汽发生器中去污水的水平保持在管中2-3英尺处。

    System for qualification of chemical decontamination methods for decontamination of nuclear reactor systems
    5.
    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。

    Alkaline-permanganate process
    7.
    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
    8.
    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。