Underground nuclear power station using self-regulating heat-pipe
controlled reactors
    51.
    发明授权
    Underground nuclear power station using self-regulating heat-pipe controlled reactors 失效
    地下核电站采用自调节热管式反应堆

    公开(公告)号:US4851183A

    公开(公告)日:1989-07-25

    申请号:US194772

    申请日:1988-05-17

    申请人: Viktor E. Hampel

    发明人: Viktor E. Hampel

    摘要: A nuclear reactor for generating electricity is disposed underground at the bottom of a vertical hole that can be drilled using conventional drilling technology. The primary coolant of the reactor core is the working fluid in a plurality of thermodynamically coupled heat pipes emplaced in the hole between the heat source at the bottom of the hole and heat exchange means near the surface of the earth. Additionally, the primary coolant (consisting of the working flud in the heat pipes in the reactor core) moderates neutrons and regulates their reactivity, thus keeping the power of the reactor substantially constant. At the end of its useful life, the reactor core may be abandoned in place. Isolation from the atmosphere in case of accident or for abandonment is provided by the operation of explosive closures and mechanical valves emplaced along the hole. This invention combines technology developed and tested for small, highly efficient, space-based nuclear electric power plants with the technology of fast-acting closure mechanisms developed and used for underground testing of nuclear weapons. This invention provides a nuclear power installation which is safe from the worst conceivable reactor accident, namely, the explosion of a nuclear weapon near the ground surface of a nuclear power reactor.

    摘要翻译: 用于发电的核反应堆位于可以使用常规钻井技术钻孔的垂直孔的底部的地下。 反应堆堆芯的主要冷却剂是位于孔底部的热源和靠近地球表面的热交换装置之间的孔中的多个热力学耦合的热管中的工作流体。 此外,主冷却剂(由反应堆堆芯中的热管中的工作流体组成)可缓和中子并调节其反应性,从而保持反应堆的功率基本恒定。 在其使用寿命结束时,反应堆堆芯可能被放弃到位。 在发生事故或放弃的情况下,大气中的隔离是通过沿着孔放置的爆炸封闭物和机械阀的操作提供的。 本发明结合了针对小型,高效率,基于空间的核电站开发和测试的技术,开发并用于核武器地下试验的快速闭合机制技术。 本发明提供了一种核能装置,它是从最可能想到的反应堆事故中安全的,即核动力堆反应堆地面附近的核武器爆炸。

    Thermally activated trigger device
    52.
    发明授权
    Thermally activated trigger device 失效
    热启动触发装置

    公开(公告)号:US4762662A

    公开(公告)日:1988-08-09

    申请号:US793501

    申请日:1985-10-31

    摘要: A thermally activated trigger device 10 comprises a pressurized closed vessel 11 with a piston 12 slideably mounted in it to divide it into two compartments 14 and 16. A fluid such as an inert gas is contained within the compartments at substantially the same pressure. One end of one of the compartments has venting means 24, such as a normally closed pipe which vents the fluid from the compartment once the pipe becomes open by rupture or melting at an elevated temperature. The resulting pressure difference between the compartments on venting of the fluid moves the piston which is connected to an actuator means for performing a desired control or safety shut-down function. The trigger device is useful for performing many control and safety shut-down functions, particularly for rendering a nuclear space reactor subcritical upon reentry to the earth's atmosphere.

    摘要翻译: 热活化触发装置10包括加压密闭容器11,活塞12可滑动地安装在其中以将其分成两个隔室14和16.在基本上相同的压力下,隔室内容纳诸如惰性气体的流体。 一个隔室的一端具有通风装置24,例如常闭管,一旦管道通过断裂或在升高的温度下熔化而使管道开放,则将其从隔室排出。 在流体排出之间的隔室之间产生的压力差移动连接到致动器装置的活塞,以执行期望的控制或安全关闭功能。 触发装置对于执行许多控制和安全关闭功能是有用的,特别是在重新进入地球大气层时使核空间反应堆亚临界。

    Nuclear engine flow reactivity shim control
    53.
    发明授权
    Nuclear engine flow reactivity shim control 失效
    核发动机流量反应性控制

    公开(公告)号:US3778344A

    公开(公告)日:1973-12-11

    申请号:US71513268

    申请日:1968-03-21

    发明人: WALSH J

    IPC分类号: G21D5/02 G21C7/28

    CPC分类号: G21D5/02

    摘要: A nuclear engine control system is provide which automatically compensates for reactor reactivity uncertainties at the start of life and reactivity losses due to core corrosion during the reactor life in gas-cooled reactors. The coolant gas flow is varied automatically by means of specially provided control apparatus so that the reactor control drums maintain a predetermined steady state position throughout the reactor life. This permits the reactor to be designed for a constant drum position and results in a desirable, relatively flat temperature profile across the core.

    Nuclear reactor control with reflector and absorber means
    54.
    发明授权
    Nuclear reactor control with reflector and absorber means 失效
    具有反射器和吸收装置的核反应堆控制

    公开(公告)号:US3660228A

    公开(公告)日:1972-05-02

    申请号:US3660228D

    申请日:1967-11-06

    申请人: TELEDYNE INC

    发明人: MAGLADRY ROBERT E

    摘要: A nuclear reactor of the metal hydride control type. Metal hydride is in two portions, one in the core and the other exterior of the core, and means are provided for permitting flow of hydrogen between the two portions. Control of reactivity is obtained by providing heating means in one or both portions, the heating being responsive to a neutron sensor.

    摘要翻译: 金属氢化物控制型核反应堆。 金属氢化物分为两部分,一个在芯部的另一个外部,并且提供用于允许两个部分之间的氢气流动的装置。 通过在一个或两个部分中提供加热装置来获得反应性的控制,加热响应于中子传感器。

    Nuclear reactor
    55.
    发明授权

    公开(公告)号:US3623946A

    公开(公告)日:1971-11-30

    申请号:US3623946D

    申请日:1965-06-22

    摘要: A nuclear reactor comprising: AN ELONGATED CYLINDRICAL CORE LONGITUDINALLY DIVIDED INTO QUADRANTS, EACH CORE QUADRANT BEING NEUTRONICALLY SUBCRITICAL; MEANS FOR FLEXIBLY FASTENING TOGETHER TWO DIAMETRICALLY OPPOSED QUADRANTS AT ONE END OF SAID CORE AND FOR RETAINING THE REMAINING TWO QUADRANTS IN A FIXED POSITION; MEANS FOR DRIVING THE FREE ENDS OF SAID FLEXIBLY FASTENED QUADRANTS APART AND FOR RETURNING THEM TOGETHER; MEANS FOR CONTROLLING THE REACTIVITY OF SAID REACTOR CORE; AND, MEANS FOR REMOVING THE ENERGY GENERATED BY SAID REACTOR CORE.

    REFLECTORS FOR MOLTEN CHLORIDE FAST REACTORS

    公开(公告)号:US20210343431A1

    公开(公告)日:2021-11-04

    申请号:US17368576

    申请日:2021-07-06

    申请人: TerraPower, LLC

    摘要: A reflector assembly for a molten chloride fast reactor (MCFR) includes a support structure with a substantially cylindrical base plate, a substantially cylindrical top plate, and a plurality of circumferentially spaced ribs extending between the base plate and the top plate. The support structure is configured to encapsulate a reactor core for containing nuclear fuel. The MCFR also includes a plurality of tube members disposed within the support structure and extending axially between the top plate and the bottom plate. The plurality of tube members are configured to hold at least one reflector material to reflect fission born neutrons back to a center of the reactor core.