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    • 3. 发明授权
    • Nuclear radiation actuated valve
    • 核辐射致动阀
    • US4493812A
    • 1985-01-15
    • US340621
    • 1982-01-19
    • David W. ChristiansenDixon P. Schively
    • David W. ChristiansenDixon P. Schively
    • G21C15/02F16K31/00G21C3/322G21C15/06G21C7/32
    • G21C3/322F16K31/00Y02E30/38
    • A nuclear radiation actuated valve for a nuclear reactor. The valve has a valve first part (such as a valve rod with piston) and a valve second part (such as a valve tube surrounding the valve rod, with the valve tube having side slots surrounding the piston). Both valve parts have known nuclear radiation swelling characteristics. The valve's first part is positioned to receive nuclear radiation from the nuclear reactor's fuel region. The valve's second part is positioned so that its nuclear radiation induced swelling is different from that of the valve's first part. The valve's second part also is positioned so that the valve's first and second parts create a valve orifice which changes in size due to the different nuclear radiation caused swelling of the valve's first part compared to the valve's second part. The valve may be used in a nuclear reactor's core coolant system.
    • 用于核反应堆的核辐射致动阀。 阀具有阀第一部分(例如具有活塞的阀杆)和阀第二部分(例如围绕阀杆的阀管,阀管具有围绕活塞的侧槽)。 两个阀门部件都有已知的核辐射膨胀特性。 阀门的第一部分定位为接收来自核反应堆燃料区域的核辐射。 阀的第二部分定位成使其核辐射引起的膨胀与阀的第一部分不同。 阀的第二部分也被定位成使得阀的第一和第二部分形成阀口,其由于不同的核辐射导致阀的第一部分与阀的第二部分相比膨胀而改变尺寸。 阀门可用于核反应堆的核心冷却剂系统。
    • 4. 发明授权
    • Nuclear reactor fuel assembly duct-tube-to-handling-socket attachment
system
    • 核反应堆燃料组件管 - 管 - 处理 - 插座连接系统
    • US4366116A
    • 1982-12-28
    • US240676
    • 1981-03-05
    • David W. ChristiansenBob G. Smith
    • David W. ChristiansenBob G. Smith
    • G21C3/33G21C3/334G21C3/06
    • G21C3/334G21C3/33Y02E30/40
    • A reusable system for removably attaching the upper end 10of a nuclear reactor duct tube to the lower end 30 of a nuclear reactor fuel assembly handling socket. A transition ring 20, fixed to the duct tube's upper end 10, has an interior-threaded section 22 with a first locking hole segment 24. An adaptor ring 40, fixed to the handling socket's lower end 30 has an outside-threaded section 42 with a second locking hole segment 44. The inside 22 and outside 42 threaded sections match and can be joined so that the first 24 and second 44 locking hole segments can be aligned to form a locking hole. A locking ring 50, with a locking pin 52, slides over the adaptor ring 40 so that the locking pin 52 fits in the locking hole. A swage lock 60 or a cantilever finger lock 70 is formed from the locking cup collar 26 to fit in a matching groove 54 or 56 in the locking ring 50 to prevent the locking ring's locking pin 52 from backing out of the locking hole.
    • 一种用于将核反应堆管道管的上端10可拆卸地连接到核反应堆燃料组件处理插座的下端30的可重复使用的系统。 固定到管道管上端10的过渡环20具有带有第一锁定孔段24的内螺纹部分22.固定到处理插座下端30的适配环40具有外螺纹部分42, 第二锁定孔段44.内部22和外部42螺纹部分匹配并且可以被接合,使得第一24和第二锁定孔段可以对准以形成锁定孔。 具有锁定销52的锁定环50在适配环40上滑动,使得锁定销52装配在锁定孔中。 锁定锁60或悬臂手指锁70由锁定杯套26形成,以装配在锁定环50中的匹配槽54或56中,以防止锁定环的锁定销52从锁定孔中退出。
    • 5. 发明授权
    • Nuclear fuel spacer grid
    • 核燃料间隔网格
    • US4239597A
    • 1980-12-16
    • US891792
    • 1978-03-30
    • David W. Christiansen
    • David W. Christiansen
    • G21C3/332G21C3/30
    • G21C3/332Y02E30/40
    • A typical embodiment of the invention provides structural support for the grids in a nuclear reactor fuel assembly. Illustratively, the external surfaces of water rods or instrument tubes in a fuel assembly are provided with annular recesses. A spacer grid retainer is engaged within the recesses by means of spring loaded fingers on the retainer, in which the spring loading forces are greater than anticipated vibration forces to reduce fretting corrosion. Notches formed in the retainer secure the grid to the retainer, all in a manner that simplifies fuel assembly construction and restricts grid movement at lower cost.
    • 本发明的典型实施例为核反应堆燃料组件中的格栅提供结构支撑。 说明性地,燃料组件中的水棒或仪器管的外表面设置有环形凹部。 间隔网格保持器通过弹簧加载的指状物接合在凹部内,保持器上的弹簧加载力大于预期的振动力,以减少微动腐蚀。 在保持器中形成的凹口将格栅固定到保持器,所有这些都简化了燃料组件结构并以较低的成本限制了电网移动。
    • 10. 发明授权
    • Nuclear reactor spacer grid and ductless core component
    • 核反应堆隔板和无管芯组件
    • US4818479A
    • 1989-04-04
    • US784277
    • 1985-10-04
    • David W. ChristiansenRichard A. Karnesky
    • David W. ChristiansenRichard A. Karnesky
    • G21C3/34G21C3/322G21C3/352
    • G21C3/322G21C3/352Y02E30/38
    • The invention relates to a nuclear reactor spacer grid member for use in a liquid cooled nuclear reactor and to a ductless core component employing a plurality of these spacer grid members. The spacer grid member is of the egg-shell type and is constructed so that the walls of the cell members of the grid member are formed of a single thickness of metal to avoid tolerance problems. Within each cell member is a hydraulic spring which laterally constrains the nuclear material bearing rod which passes through each cell member against a hardstop in response to coolant flow through the cell member. This hydraulic spring is also suitable for use in a water cooled nuclear reactor. A core component constructed of, among other components, a plurality of these spacer grid members, avoids the use of a full length duct by providing spacer sleeves about the sodium tubes passing through the spacer grid members at locations between the grid members, thereby maintaining a predetermined space between adjacent grid members.
    • 本发明涉及一种用于液冷核反应堆的核反应堆间隔网格构件和采用多个间隔网格构件的无管芯组件。 间隔网格构件为蛋壳型,并且构造成使得栅格构件的单元构件的壁由单一金属厚度形成以避免公差问题。 在每个电池构件内是液压弹簧,其液压弹簧横向地约束穿过每个电池构件的核材料轴承杆,以响应于通过电池构件的冷却剂流而抵抗硬停止。 该液压弹簧也适用于水冷核反应堆。 除了其他部件之外,构成多个这些间隔网格构件的芯部件避免了通过在电栅部件之间的位置处通过间隔栅格部件的钠管提供间隔套筒来避免使用全长管道,从而保持 相邻网格构件之间的预定空间。