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1.发明授权
公开(公告)号：US4904442A
公开(公告)日：1990-02-27
申请号：US270878
申请日：1988-11-14
IPC分类号： G21C11/02 , G21C13/00 , G21C13/02 , G21C13/028
CPC分类号： G21C13/028 , Y02E30/40
摘要： A nuclear reactor containment arrangement has a permanent cavity ring seal extending across an annular expansion gap between a reactor pressure vessel and a containment wall to provide a water tight seal therebetween. The annular ring seal has a support ring with an inner downwardly extending cylindrical section resting on the reactor flange and an outer downwardly extending cylindrical section resting on a shelf in the containment wall. A vertically extending, L-shaped, seal extends between an inner end of the support ring while a vertically extending, L-shaped, seal extends between the outer cylindrical section and the containment wall shelf. Neutron shielding material is suspended, by support rods, within the annular expansion gap while thermal insulation is provided therebelow. Manways and ports in the support ring are sealed by hatches and provide access to the annular expansion gap and, while open, provide for flow of cooling air from the annular expansion gap through the support ring.
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2.发明授权
公开(公告)号：US4905260A
公开(公告)日：1990-02-27
申请号：US270879
申请日：1988-11-14
IPC分类号： G21C11/02 , G21C13/00 , G21C13/02 , G21C13/028
CPC分类号： G21C13/028 , Y02E30/40
摘要： An annular seal ring between a reactor pressure vessel and a containment wall is disposed in an annular expansion gap therebetween, having a support ring and inner and outer upwardly extending cylindrical sections. The inner cylindrical section is disposed below a flange on the reactor and has a flexible seal therebetween, while the outer cylindrical section terminates substantially parallel and spaced from a shelf in the containment wall with a flexible seal therebetween. The annular seal ring is supported by radial support beams, while support rods depending from the support ring position neutron shielding material in the annular expansion gap. Manways and ports provide access to the gap and thermal insulation is provided below the neutron shielding material to direct cooling air from the annular gap up through opened manway and port.
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公开(公告)号：US4919881A
公开(公告)日：1990-04-24
申请号：US215116
申请日：1988-07-05
摘要： A remotely operated device which attaches to an existing internals lifting rig to safely lift and transport nuclear reactor internals structures. The device includes a grapple assembly uniquely formed to maximize the effective bearing surface of an annular shoulder disposed on the grapple assembly to engage the internal structure. The annular shoulder comprises a first outer diameter, the annular shoulder defining a second outer diameter disposed thereabove. The grapple assembly comprises a plurality of fingers circumferentially disposed about an actuator rod which has a diameter essentially equal to a first inner diameter of the grapple assembly. The lower end of the grapple assembly has a second inner diameter smaller than the first and axially adjacent to the annular shoulder. In order to maximize the bearing surface, the fingers of the grapple assembly are formed such that the first inner and outer diameters are machined with respect to a first axis, whereas the second inner and outer diameters are formed with respect to a second axis parallel to the first. These machining axes are offset from each other by a distance which is equal to the desired amount of radial expansion of the fingers. This uniquely formed grapple device thus has a bearing surface 30 to 40 percent greater than that achieved by prior art devices.
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公开(公告)号：US4834934A
公开(公告)日：1989-05-30
申请号：US152285
申请日：1988-02-04
IPC分类号： G21C19/19 , G21C19/105
CPC分类号： G21C19/105 , Y10S294/906
摘要： A thimble grip fuel assembly handling tool (20) for transporting fully loaded fuel assemblies (52) is disclosed. The tool (20) comprises an elongated mast (23) slidingly disposed within an elongated cylinder (113), the cylinder being of a length less than the mast (23) such that the tool defines a mast fill-up position (126) and a mast full-down position (128). A cage (110) assembly acts to protect the gripping means (32) when the tool is transported in the mast full-up position (126). The gripping means (32) is comprised of a plurality of gripping members (49) which grip the inside diameter of control rod guide thimbles (50). The load path is distributed in the tool such that when the fuel assembly (52) secured to the gripping means (32) is raised, the weight of the fully loaded fuel assembly (52) acts to increase the gripping force on the fuel assembly. A number of indicators on the tool act to indicate to an operator: when the tool is in the mast full-down position; when the gripping members (49) have been fully actuated; and if there is any slipping of the gripping members within the fuel assemblies. The tool also includes a secondary gripping mechanism which engages the top nozzle of the fuel assembly.
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公开(公告)号：US4717527A
公开(公告)日：1988-01-05
申请号：US626847
申请日：1984-07-02
申请人： Robert K. Gjertsen , Elmer A. Bassler , Edgar A. Huckestein , Robert B. Salton , Stephen N. Tower
发明人： Robert K. Gjertsen , Elmer A. Bassler , Edgar A. Huckestein , Robert B. Salton , Stephen N. Tower
CPC分类号： G21C3/328 , G21C7/27 , G21Y2002/201 , G21Y2004/30 , Y02E30/38 , Y02E30/39
摘要： A fuel assembly for a pressurized water nuclear reactor incorporating fluid moderator spectral shift control means. During the first part of the fuel cycle when there is excess reactivity, neutron moderation may be decreased by replacing a portion of the water within the core with a less effective moderator such as heavy water. During the life of the fuel, the heavy water is gradually replaced with regular water. The fuel assembly incorporates the necessary means and apparatus to effectuate such control.
摘要翻译： 一种包含流体调节剂光谱变换控制装置的加压水核反应堆的燃料组件。 在燃料循环的第一部分，当存在过量的反应性时，通过用较不有效的减速剂（例如重水）代替芯中的一部分水可以减少中子调节。 在燃料的使用寿命期间，重水逐渐被普通的水替代。 燃料组件包括实现这种控制的必要手段和装置。
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公开(公告)号：US4661306A
公开(公告)日：1987-04-28
申请号：US626943
申请日：1984-07-02
申请人： Howard F. Fensterer , William E. Klassen , Luciano Veronesi , David E. Boyle , Robert B. Salton
发明人： Howard F. Fensterer , William E. Klassen , Luciano Veronesi , David E. Boyle , Robert B. Salton
CPC分类号： G21C7/27 , Y02E30/39 , Y10T137/85938
摘要： Apparatus is disclosed for introducing a low neutron moderating fluid into the reactor vessel of a spectral shift pressurized water nuclear reactor and for distributing the moderating fluid through the lower core support plate into the fuel assemblies in the core.
摘要翻译： 公开了用于将低中子调节流体引入光谱变换加压水核反应堆的反应器容器中并用于将调节流体通过下芯支撑板分配到芯中的燃料组件中的装置。
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公开(公告)号：US5061083A
公开(公告)日：1991-10-29
申请号：US368459
申请日：1989-06-19
申请人： Noel P. Grimm , Frank I. Bauer , Thomas G. Bengel , Richard E. Kothmann , Robert S. Mavretish , Phillip E. Miller , Raymond J. Nath , Robert B. Salton
发明人： Noel P. Grimm , Frank I. Bauer , Thomas G. Bengel , Richard E. Kothmann , Robert S. Mavretish , Phillip E. Miller , Raymond J. Nath , Robert B. Salton
摘要： A temperature monitoring device for measuring the temperature at a surface of a body, composed of: at least one first thermocouple and a second thermocouple; support members supporting the thermocouples for placing the first thermocouple in contact with the body surface and for maintaining the second thermocouple at a defined spacing from the body surface; and a calculating circuit connected to the thermocouples for receiving individual signals each representative of the temperature reading produced by a respective one of the first and second thermocouples and for producing a corrected temperature signal having a value which represents the temperature of the body surface and is a function of the difference between the temperature reading produced by the first thermocouple and a selected fraction of the temperature reading provided by the second thermocouple.
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公开(公告)号：US4693862A
公开(公告)日：1987-09-15
申请号：US626846
申请日：1984-07-02
摘要： A method and apparatus for extending the life of a core of a water moderated nuclear reactor by spectral shift comprising the displacement of a portion of the moderator in the core by a gas having a low neutron cross-section during the initial stage of the life of the core and displacing the gas and replacing it with moderator during the latter part of the life of the core.
摘要翻译： 一种用于通过光谱偏移延长水慢化核反应堆的核心的寿命的方法和装置，包括通过具有低中子横截面的气体在核心中的一部分慢化剂的位移，在初始阶段期间 核心和替代气体，并在核心的后期部分用主持人取代。
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公开(公告)号：US4781882A
公开(公告)日：1988-11-01
申请号：US49494
申请日：1987-05-14
CPC分类号： G21C19/16
摘要： An apparatus for loading and unloading a fuel assembly in a nuclear reactor has a bridge and trolley for positioning the fuel assembly and a pair of concentric inner and outer masts with the inner mast vertically movable in the outer mast and guide means to concentrically position the inner mast within the outer mast during such vertical movement. The guide means comprises inner members on the inner mast which cooperate with outer members on the outer mast, the outer members pivotally mounted on a framework on the outer mast for movement towards or away from the inner members. An alignment device is provided to precisely align superimposed outer members and provide vertical alignment therebetween, with an adjustment device provided to aid in the precise alignment of the same.
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公开(公告)号：US4433828A
公开(公告)日：1984-02-28
申请号：US229362
申请日：1981-01-29
申请人： Stanley R. Spiegelman , Robert B. Salton , Robert W. Beer , Louis J. Malandra , Michael L. Cognevich
发明人： Stanley R. Spiegelman , Robert B. Salton , Robert W. Beer , Louis J. Malandra , Michael L. Cognevich
CPC分类号： B25B29/02
摘要： A quick-acting stud tensioner tool for enabling the loosening or tightening of a stud nut on a reactor vessel stud. The tool engages the vessel stud by closing a gripper mechanism around an upper end of the vessel stud upon a transfer of the mass of the tool from a hoist to a support structure surrounding the vessel stud. After the stud has been elongated, the gripper mechanism releases the vessel stud when the mass of the tool is transferred from the support structure surrounding the vessel stud to the hoist.
摘要翻译： 一种快速作用的螺柱张紧器工具，用于使反作用器螺柱上的螺柱螺母松动或拧紧。 当工具的质量从起重机转移到围绕容器螺柱的支撑结构时，该工具通过在容器螺柱的上端周围闭合夹持机构来接合容器螺柱。 在螺栓已经伸长之后，当工具的质量从围绕容器螺柱的支撑结构转移到起重机时，夹具机构释放容器螺柱。
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