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1. 发明授权

US4717527A Fuel assembly 失效
标题翻译：燃油组件
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
IPC分类号： G21C3/32 , G21C3/328 , G21C7/27 , G21C1/06 , G21C7/22 , G21C15/02 , G21C19/28
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。

2. 发明授权

US4661306A Fluid moderator control system reactor internals distribution system 失效
标题翻译：流体调节器控制系统反应堆内部配送系统
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
IPC分类号： G21C5/00 , G21C7/27 , G21C7/06 , G21C7/32
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。

3. 发明授权

US5414742A Leak-detection system and method for detecting a leaking container 失效
标题翻译：泄漏检测系统和泄漏容器检测方法
公开(公告)号：US5414742A
公开(公告)日：1995-05-09
申请号：US150710
申请日：1993-11-10
申请人： Leonard P. Hornak , Ralph W. Tolino , Robert B Salton
发明人： Leonard P. Hornak , Ralph W. Tolino , Robert B Salton
IPC分类号： G21C17/07 , G21C17/00
CPC分类号： G21C17/07 , G21Y2002/201 , G21Y2004/302 , G21Y2004/40
摘要： Leak-detection system and method for detecting a leaking container. The system includes an enclosure defining a cavity therein surrounding the container, which container may be a nuclear fuel rod having fission products leaking through a breach in the exterior surface of the fuel rod. The fission products are capable of adhering to the exterior surface of the fuel rod as the fission products leak through the breach in the fuel rod. A radiation detector is in communication with the cavity for detecting the fission products leaking through the breach. Moreover, a gas injector is in communication with the cavity for injecting a multiplicity of carrier gas bubbles into the cavity to remove any fission products adhering to the exterior surface of the fuel rod and to carry the fission products removed thereby to the radiation detector. In this manner, the detector detects the leaking fission products even though they may tend to adhere to the exterior surface of the fuel rod. In addition, an elevator is connected to the fuel assembly for elevating the fuel assembly in the cavity, so that the external pressure acting against the exterior surface of the fuel rods is reduced in order to relieve the internal pressure in the fuel rods. As the fuel assembly is elevated, any fission products tending to "hide-out" in the fuel rods expand and migrate through the breach. As the fission products migrate through the breach, they are carried by the carrier gas bubbles to the radiation detector where they are detected by the radiation detector. In this manner, otherwise undetectable leaking fuel rods become detectable.
摘要翻译：泄漏检测系统和泄漏容器检测方法。该系统包括围绕容器限定空腔的外壳，该容器可以是具有通过燃料棒的外表面中的破裂泄漏的裂变产物的核燃料棒。当裂变产物通过燃料棒中的破裂泄漏时，裂变产物能够附着在燃料棒的外表面上。辐射探测器与空腔通信，用于检测通过漏气泄漏的裂变产物。此外，气体注入器与空腔连通，用于将多个载气气体注入空腔中以除去粘附到燃料棒的外表面的任何裂变产物，并将从其移除的裂变产物携带到辐射探测器。以这种方式，检测器检测泄漏的裂变产物，即使它们可能倾向于附着到燃料棒的外表面。此外，电梯连接到燃料组件以将燃料组件升高到空腔中，从而降低了作用在燃料棒的外表面上的外部压力，以便减轻燃料棒中的内部压力。随着燃料组件的升高，燃料棒中倾向于“隐藏”的任何裂变产物都会通过破裂扩展和迁移。当裂变产物通过裂缝迁移时，它们被载气气体携带到辐射检测器，在那里它们被辐射检测器检测到。以这种方式，否则不可检测的泄漏的燃料棒变得可检测。

4. 发明授权

US4904442A Permanent cavity seal ring for a nuclear reactor containment arrangement 失效
标题翻译：用于核反应堆安全壳的永久性腔密封环
公开(公告)号：US4904442A
公开(公告)日：1990-02-27
申请号：US270878
申请日：1988-11-14
申请人： Kenneth J. Swidwa , Robert B. Salton , James R. Marshall
发明人： Kenneth J. Swidwa , Robert B. Salton , James R. Marshall
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.

5. 发明授权

US4781882A Guide roller assembly for nuclear reactor refueling apparatus 失效
标题翻译：用于核反应堆加油装置的导向辊总成
公开(公告)号：US4781882A
公开(公告)日：1988-11-01
申请号：US49494
申请日：1987-05-14
申请人： Robert B. Salton , Leonard P. Hornak
发明人： Robert B. Salton , Leonard P. Hornak
IPC分类号： G21C19/16 , G21C19/20
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.

6. 发明授权

US4433828A Reactor vessel stud closure system 失效
标题翻译：反应器容器螺栓封闭系统
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
IPC分类号： B25B21/00 , B23P19/06 , B25B29/02 , G21C13/02 , G21C19/20 , E21B19/00
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。

7. 发明授权

US4919881A Reactor internals through-hole grapple 失效
标题翻译：反应堆内部通孔抓斗
公开(公告)号：US4919881A
公开(公告)日：1990-04-24
申请号：US215116
申请日：1988-07-05
申请人： Michael F. Hankinson , Kenneth J. Swidwa , Robert B. Salton
发明人： Michael F. Hankinson , Kenneth J. Swidwa , Robert B. Salton
IPC分类号： G21C19/02 , G21C19/10
CPC分类号： G21C19/10 , G21C19/02
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.

8. 发明授权

US4905260A Nuclear reactor containment arrangement with permanent cavity seal ring 失效
标题翻译：具有永久性腔密封环的核反应堆遏制装置
公开(公告)号：US4905260A
公开(公告)日：1990-02-27
申请号：US270879
申请日：1988-11-14
申请人： Kenneth J. Swidwa , Robert B. Salton , James R. Marshall
发明人： Kenneth J. Swidwa , Robert B. Salton , James R. Marshall
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.

9. 发明授权

US4834934A Thimble grip fuel assembly handling tool 失效
标题翻译：套管夹紧燃油组件处理工具
公开(公告)号：US4834934A
公开(公告)日：1989-05-30
申请号：US152285
申请日：1988-02-04
申请人： Robert B. Salton , Leonard P. Hornak , James R. Marshall , Robert E. Meuschke
发明人： Robert B. Salton , Leonard P. Hornak , James R. Marshall , Robert E. Meuschke
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.

10. 发明授权

US4692296A Mechanical spectral shift reactor 失效
标题翻译：机械光谱变换反应堆
公开(公告)号：US4692296A
公开(公告)日：1987-09-08
申请号：US946111
申请日：1986-12-24
申请人： Donald G. Sherwood , John F. Wilson , Robert B. Salton , Howard F. Fensterer
发明人： Donald G. Sherwood , John F. Wilson , Robert B. Salton , Howard F. Fensterer
IPC分类号： G21C7/26 , G21C7/27
CPC分类号： G21C7/27 , G21C7/26 , Y02E30/39
摘要： The mechanical spectral shift reactor comprises apparatus for inserting and withdrawing water displacer elements from the reactor core for selectively changing the water-moderator volume in the core thereby changing the reactivity of the core. The apparatus may include drive mechanisms for moving the displacer elements relative to the core and guide mechanisms for guiding the displacer rods through the reactor vessel. An array of tubes may be disposed between the guide mechanisms and the fuel assemblies for guidance and minimization of flow induced vibrations of the displacer elements.
摘要翻译：机械光谱变换反应器包括用于从反应堆核心插入和取出水置换元件的装置，用于选择性地改变芯体中的水慢化剂体积，从而改变芯的反应性。该装置可以包括用于相对于芯移动置换器元件的驱动机构和用于引导置换棒通过反应器容器的引导机构。一组管可以设置在引导机构和燃料组件之间，用于引导和最小化置换器元件的流动引起的振动。

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