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    • 1. 发明授权
    • Control system for a small fission reactor
    • 小型裂变反应堆的控制系统
    • US4568515A
    • 1986-02-04
    • US699887
    • 1985-02-08
    • James P. BurelbachWilliam J. KannJames G. Saiveau
    • James P. BurelbachWilliam J. KannJames G. Saiveau
    • G21C7/11G21C7/10
    • G21C7/11G21Y2002/301G21Y2004/30G21Y2004/40Y02E30/39
    • A system for controlling the reactivity of a small fission reactor includes an elongated, flexible hollow tube in the general form of a helical coiled spring axially positioned around and outside of the reactor vessel in an annular space between the reactor vessel and a surrounding cylindrical-shaped neutron reflector. A neutron absorbing material is provided within the hollow tube with the rate of the reaction controlled by the extension and compression of the hollow tube, e.g., extension of the tube increases reactivity while its compression reduces reactivity, in varying the amount of neutron absorbing material disposed between the reactor vessel and the neutron reflector. Conventional mechanical displacement means may be employed to control the coil density of the hollow tube as desired. In another embodiment, a plurality of flexible hollow tubes each containing a neutron absorber are positioned adjacent to one another in spaced relation around the periphery of the reactor vessel and inside the outer neutron reflector with reactivity controlled by the extension and compression of all or some of the coiled hollow tubes. Yet another embodiment of the invention envisions the neutron reflector in the form of an expandable coil spring positioned in an annular space between the reactor vessel and an outer neutron absorbing structure for controlling the neutron flux reflected back into the reactor vessel.
    • 用于控制小型裂变反应堆的反应性的系统包括细长的柔性中空管,螺旋形螺旋弹簧的一般形式,轴向位于反应器容器的周围和外部,位于反应器容器与周围的圆柱形 中子反射器 在中空管内设置中子吸收材料,其反应速率由中空管的延伸和压缩控制,例如,管的延伸增加反应性,同时其压缩降低反应性,改变设置的中子吸收材料的量 在反应堆容器和中子反射器之间。 可以根据需要使用常规的机械位移装置来控制中空管的线圈密度。 在另一个实施例中,每个包含中子吸收器的多个柔性中空管以间隔开的方式邻近反应器容器的周边并且在外部中子反射器的内部以相反的方式定位,其反应性受到所有或一些 螺旋中空管。 本发明的另一个实施例设想了位于反应器容器和外部中子吸收结构之间的环形空间中的可膨胀螺旋弹簧形式的中子反射器,用于控制反射回到反应器容器中的中子通量。
    • 3. 发明授权
    • Hanging core support system for a nuclear reactor
    • 悬挂核反应堆核心支援体系
    • US4645638A
    • 1987-02-24
    • US604200
    • 1984-04-26
    • James P. BurelbachWilliam J. KannYen-Cheng PanJames G. SaiveauRalph W. Seidensticker
    • James P. BurelbachWilliam J. KannYen-Cheng PanJames G. SaiveauRalph W. Seidensticker
    • G21C5/10G21C17/00G21C13/00
    • G21C5/10Y02E30/40
    • For holding the reactor core in the confining reactor vessel, a support is disclosed that is structurally independent of the vessel, that is dimensionally accurate and stable, and that comprises tandem tension linkages that act redundantly of one another to maintain stabilized core support even in the unlikely event of the complete failure of one of the linkages. The core support has a mounting platform for the reactor core, and unitary structure including a flange overlying the top edge of the reactor vessels, and a skirt and box beams between the flange and platform for establishing one of the linkages. A plurality of tension rods connect between the deck closing the reactor vessel and the platform for establishing the redundant linkage. Loaded Belleville springs flexibly hold the tension rods at the deck and separable bayonet-type connections hold the tension rods at the platform. Motion or radiation sensing detectors can be provide at the lower ends of the tension rods for obtaining pertinent readings proximate the core.
    • 为了将反应堆芯保持在限制反应堆容器中,公开了在结构上独立于容器的支架,其尺寸精确和稳定,并且包括彼此冗余地起作用以保持稳定的核心支撑件的串联张力连接,即使在 其中一个联系完全失败的可能性不大。 核心支撑件具有用于反应堆芯的安装平台,并且包括覆盖反应堆容器的顶部边缘的凸缘的整体结构以及用于建立其中一个连接件的凸缘和平台之间的裙部和箱梁。 多个张力杆连接在关闭反应堆容器的甲板和用于建立冗余连杆的平台之间。 装载的Belleville弹簧灵活地将张力杆保持在甲板上,可分离的卡口式连接将张力杆固定在平台上。 可以在拉杆的下端设置运动或辐射感测检测器,以获得靠近核心的相关读数。
    • 4. 发明授权
    • Continuous process electrorefiner
    • 连续工艺电抛光
    • US07097747B1
    • 2006-08-29
    • US10637088
    • 2003-08-05
    • Joseph E. HercegJames G. SaiveauLubomir Krajtl
    • Joseph E. HercegJames G. SaiveauLubomir Krajtl
    • C25C7/00C25C7/06C25C7/08C25C3/34
    • C25C7/08C25C3/34C25C7/005
    • A new device is provided for the electrorefining of uranium in spent metallic nuclear fuels by the separation of unreacted zirconium, noble metal fission products, transuranic elements, and uranium from spent fuel rods. The process comprises an electrorefiner cell. The cell includes a drum-shaped cathode horizontally immersed about half-way into an electrolyte salt bath. A conveyor belt comprising segmented perforated metal plates transports spent fuel into the salt bath. The anode comprises the conveyor belt, the containment vessel, and the spent fuel. Uranium and transuranic elements such as plutonium (Pu) are oxidized at the anode, and, subsequently, the uranium is reduced to uranium metal at the cathode. A mechanical cutter above the surface of the salt bath removes the deposited uranium metal from the cathode.
    • 通过从废燃料棒分离未反应的锆,贵金属裂变产物,超铀元素和铀,为废金属核燃料中的铀电解精炼提供了新的装置。 该方法包括电学​​纯化器电池。 该电池包括一个水平浸入电解质盐浴一半的鼓形阴极。 包括分段穿孔金属板的输送带将废燃料输送到盐浴中。 阳极包括输送带,安全壳和废燃料。 铀和铀元素如钚(Pu)在阳极被氧化,随后铀在阴极被还原成铀金属。 在盐浴表面上的机械切割机从阴极去除沉积的铀金属。