Control rod for nuclear reactor
    1.
    发明授权
    Control rod for nuclear reactor 失效
    核反应堆控制棒

    公开(公告)号:US6041091A

    公开(公告)日:2000-03-21

    申请号:US906243

    申请日:1997-08-04

    IPC分类号: G21C7/113 G21C7/00

    CPC分类号: G21C7/113 Y02E30/31 Y02E30/39

    摘要: A control rod for a nuclear reactor is composed of a center structural member, a plurality of wings each composed of a sheath member of long plate structure having a U-shaped cross section and secured to the center structural member, a front end structural member secured to a front end side of the wing in a wing inserting direction in a reactor core, a terminal end structural member secured to a terminal end side of the wing, a plurality of integral type neutron absorbing elements each having a plate structure accommodated in each of the sheaths in a row in a longitudinal direction thereof and each being formed in plate shape by integrating one or more neutron absorbing plates, and a plurality of load supporting members for supporting weights of the integral type neutron absorbing elements. A length in the sheath longitudinal direction of at least one set of the integral type neutron absorbing elements accommodated in the wing is reduced, and the reduced integral type neutron absorbing elements are supported to the U-shaped sheath by the load supporting members to thereby reduce a local load applied to the U-shaped sheath.

    摘要翻译: 用于核反应堆的控制杆由中心结构件,多个翼构成,每个翼由具有U形横截面的长板结构的护套构件组成,并且固定到中心构件,前端结构件固定 在机翼的翼端插入方向上的前端侧,固定到机翼的末端侧的终端结构构件,多个整体型中子吸收元件,每个都具有容纳在每个中的板结构 其纵长方向排成一列,通过集成一个以上的中子吸收板而形成为板状,并具有用于支撑整体型中子吸收元件的重量的多个负载支承部件。 容纳在机翼中的至少一组集成型中子吸收元件的护套纵向方向上的长度减小,并且减小的积分型中子吸收元件由负载支撑构件支撑在U形护套上,从而减少 施加到U形护套的局部载荷。

    Core-control assembly with a fixed fuel support
    4.
    发明授权
    Core-control assembly with a fixed fuel support 失效
    具有固定燃料支架的核心控制组件

    公开(公告)号:US5241570A

    公开(公告)日:1993-08-31

    申请号:US896085

    申请日:1992-06-08

    申请人: Roy C. Challberg

    发明人: Roy C. Challberg

    摘要: In a boiling-water nuclear reactor, a core-control assembly comprises a control rod, a fuel support, a control-rod guide tube, a control-rod drive, and a control-rod-drive housing. The fuel support is welded to the control-rod guide tube. To remove the control-rod drive, the reactor vessel can be opened and the adjacent fuel bundles removed from the fuel support. Then the control-rod can be rotated after clearing the fuel support. The control rod is then rotated to decouple its bayonet connection to the control-rod drive. The control rod can then be lifted out of the reactor. This arrangement allows a control rod to be replaced without handling of the fuel support. In addition, the fuel support can be more securely installed since it does not need to be removed.

    Control rod for nuclear reactors
    5.
    发明授权
    Control rod for nuclear reactors 失效
    核反应堆控制棒

    公开(公告)号:US5225151A

    公开(公告)日:1993-07-06

    申请号:US795482

    申请日:1991-11-21

    IPC分类号: G21C7/10 G21C7/113 G21C7/24

    摘要: In a control rod for nuclear reactors with elongated channels for boron carbide or other neutron-absorbing material which swells upon neutron irradiation, the neutron-absorbing material (20a), in at least some of the channels (18b), is provided with projecting portions (20a') or arranged in a casing with portions projecting towards the channel walls. Further, the projecting portions are adapted to form between them and the channel walls unfilled spaces (40) for taking up swelling neutron-absorbing material.

    摘要翻译: 在用于具有用于碳化硼或其他中子吸收材料的细长通道的核反应堆的控制棒中,其在中子照射时溶胀,至少一些通道(18b)中的中子吸收材料(20a)设置有突出部分 (20a')或布置在具有朝向通道壁突出的部分的壳体中。 此外,突出部分适于在它们之间形成用于吸收溶胀中子吸收材料的通道壁未填充空间(40)。

    Boiling water reactor with expanded core diameter
    6.
    发明授权
    Boiling water reactor with expanded core diameter 失效
    具有膨胀核心直径的沸腾水反应器

    公开(公告)号:US5213756A

    公开(公告)日:1993-05-25

    申请号:US694526

    申请日:1991-05-01

    申请人: Larry E. Fennern

    发明人: Larry E. Fennern

    摘要: An expanded reactor core capacity is achieved within the constraints imposed by the diametric extent of the current advanced boiling reactor (ABWR). This enhanced core capacity is achieved through the utilization of a scalloped shroud structure in conjunction with modified control rod designs. The core diameter is expanded toward the reactor vessel interior wall to establish a minimum distance therebetween representing a minimum value thereof avoiding neutron fluence induced vessel embrittlement. The control rods servicing peripheral fuel assemblies are configured having either a T-shaped blade configuration or an L-shaped blade configuration depending upon the parallel orientations of the peripheral fuel assemblies.

    Control rod
    7.
    发明授权

    公开(公告)号:US4929412A

    公开(公告)日:1990-05-29

    申请号:US336941

    申请日:1989-04-11

    IPC分类号: G21C7/113

    摘要: An apparatus and process for control rod assembly and construction for a nuclear reactor is disclosed wherein the control rod is of cruciform configuration having a plurality of and preferably four flat planar members. Each planar member is made up with an assembly of square cross sectioned tubular members. Each square cross sectioned tubular member includes a defined cylindrical center and a constant thickness surrounding tubular metallic shell to provide the contained neutron absorbing materials in a cylindrically shaped pressure vessel. The constant thickness surrounding tubular shell constituting the cylindrical shaped pressure vessel has four corner sections added to generate a modified square exterior profile. These added four corner sections comprise an addition to the tubular side wall thickness of the shell. Appropriate chamfers and rounding are provided to the square profile to impart both stress relief and convenient points for automated welding between side-by-side square sections. The square cross sectioned tubular members when welded together extend axially and longitudinally the length of the control rod in the direction of control rod movement and fluid flow. The square cross sectioned tubular members are filled with a neutron absorbing material, plugged at both ends, and fastened by welding in side-by-side relation to form the planar control rod members of the required cruciform shape. These square cross sectioned tubular members as welded in side-by-side relation are in integral portion of the longitudinal support structure of the control rod and fasten and interconnect the handle at the top of the control rod and a conventional velocity limiting device at the bottom of the control rod. The fastening of the handles and velocity limiting device at the respective top and bottom provides a secondary and supplemental seal to primary plugs containing the neutron absorbing material. If needed for enhanced life, provision is made for the incorporation of a hafnium plate in a rectangular sectioned tube adjacent the handle at upper end of the control rod, this tip being variable in length dependent upon individual control rod requirements. Thus square sectioned tubular members form an improved poison containing cylindrical volume for providing resultant improved control rod worth and increased in service life time in moderating and shutting down nuclear reactions. Consequently, the disclosed construction can be used both for conventional control rods as well as for control rod configured for control cell locations.

    Control rod
    8.
    发明授权
    Control rod 失效
    控制杆

    公开(公告)号:US4902470A

    公开(公告)日:1990-02-20

    申请号:US31633

    申请日:1987-03-30

    IPC分类号: G21C7/113

    摘要: An apparatus and process for control rod assembly and construction for a nuclear reactor is disclosed wherein the control rod is of cruciform configuration having a plurality of and preferably four flat planar members. Each planar member is made up with an assembly of square cross sectioned tubular members. Each square cross sectioned tubular member includes a defined cylindrical center and a constant thickness surrounding tubular metallic shell to provide the contained neutron absorbing materials in a cylindrically shaped pressure vessel. The constant thickness surrounding tubular shell constituting the cylindrical shaped pressure vessel has four corner sections added to generate a modified square exterior profile. These added four corner sections comprise an addition to the tubular side wall thickness of the shell. Appropriate chamfers and rounding are provided to the square profile to impart both stress relief and convenient points for automated welding between side-by-side square sections. The square cross sectioned tubular members when welded together extend axially and longitudinally the length of the control rod in the direction of control rod movement and fluid flow. The square cross sectioned tubular members are filled with a neutron absorbing material, plugged at both ends, and fastened by welding in side-by-side relation to form the planar control rod members of the required cruciform shape. These square cross sectioned tubular members as welded in side-by-side relation are an integral portion of the longitudinal support structure of the control rod and fasten and interconnect the handle at the top of the control rod and a conventional velocity limiting device at the bottom of the control rod. The fastening of the handles and velocity limiting device at the respective top and bottom provides a secondary and supplemental seal to primary plugs containing the neutron absorbing material. If needed for enhanced life, provision is made for the incorporation of a hafnium plate in a rectangular sectioned tube adjacent the handle at upper end of the control rod, this tip being variable in length dependent upon individual control rod requirements. Thus square sectioned tubular members form an improved poison containing cylindrical volume for providing resultant improved control rod worth and increased in service life time in moderating and shutting down nuclear reactions. Consequently, the disclosed construction can be used both for conventional control rods as well as for control rod configured for control cell locations.

    Control rod for nuclear reactor
    9.
    发明授权
    Control rod for nuclear reactor 失效
    核反应堆控制棒

    公开(公告)号:US4655999A

    公开(公告)日:1987-04-07

    申请号:US622727

    申请日:1984-06-20

    IPC分类号: G21C7/113 G21C7/10

    摘要: A control rod for a nuclear reactor according to the present invention is such that neutron absorbing rods are surrounded with a second neutron absorber which differs in material from the neutron absorbing rods. In a case where the neutron absorbing rod is composed of boron carbide powder and a cladding for receiving the powder therein, the second neutron absorber is a sheet of a material having a neutron irradiation lifetime longer than that of boron carbide, for example, hafnium. In a case where the neutron absorbing rod is a round hafnium rod, the second neutron absorber having a neutron absorption worth higher than that of hafnium is located so as to surround the round hafnium rods. Thus, the neutron absorbing rods are effectively used, and the lifetime of the control rod can be prolonged in the former.

    摘要翻译: 根据本发明的用于核反应堆的控制棒是这样的,即中子吸收棒被与中子吸收棒材料不同的第二中子吸收器包围。 在中子吸收棒由碳化硼粉末和用于接收粉末的包层构成的情况下,第二中子吸收体是具有比碳化硼例如铪的中子照射寿命长的材料的片材。 在中子吸收棒是圆形铪棒的情况下,具有比铪高的中子吸收的第二中子吸收体被定位成围绕圆形铪棒。 因此,有效地使用中子吸收棒,并且可以在前者中延长控制棒的寿命。

    Control rod velocity limiter
    10.
    发明授权
    Control rod velocity limiter 失效
    控制杆速度限制器

    公开(公告)号:US4624826A

    公开(公告)日:1986-11-25

    申请号:US646761

    申请日:1984-09-04

    摘要: A velocity limiting device providing greater resistance to motion through a fluid in one direction than in the opposite direction. The device includes a toroidally shaped control member having a smooth generally conical surface on one side for low resistance movement through the fluid in the one direction. On its opposite side the control member is formed with at least one groove providing a concave surface spaced from which is an arrangement of vanes forming a jet for directing a stream of fluid into the groove upon movement in the opposite direction whereby the resultant increase in fluid turbulence increases resistance to rapid movement in this opposite direction.

    摘要翻译: 速度限制装置在一个方向上提供比在相反方向更大的阻力通过流体的阻力。 该装置包括环形控制构件,其在一侧具有平滑的大致圆锥形的表面,用于在一个方向上通过流体的低阻力运动。 在其相反侧,控制构件形成有至少一个凹槽,其提供间隔开的凹形表面,所述凹形表面是形成喷嘴的叶片布置,用于在相反方向上移动时将流体流引导到凹槽中,由此导致流体的增加 湍流增加了在相反方向快速运动的阻力。