Doppler reactivity augmentation device

    公开(公告)号:US12046380B2

    公开(公告)日:2024-07-23

    申请号:US17151012

    申请日:2021-01-15

    申请人: TerraPower, LLC

    摘要: A fast neutron nuclear reactor contains a nuclear reactor core having an array of device locations. Some device locations in the nuclear reactor core contain fissile and fertile nuclear fuel assembly devices. One or more other device locations in the nuclear reactor core contain Doppler reactivity augmentation devices that amplify the negativity of the Doppler reactivity coefficient within the nuclear reactor core. In some implementations, a Doppler reactivity augmentation device can also reduce the coolant temperature coefficient within the nuclear reactor core. Accordingly, a Doppler reactivity augmentation device contributes to a more stable nuclear reactor core.

    TRAVELLING WAVE REACTOR FOR SPACE EXPLORATION

    公开(公告)号:US20220246316A1

    公开(公告)日:2022-08-04

    申请号:US17630507

    申请日:2021-06-07

    发明人: Po HU

    IPC分类号: G21C7/06 G21C1/02 G21C5/18

    摘要: The present invention relates to a travelling wave reactor for a space exploration. A reactor core of the travelling wave reactor is dispersed into several modules in a travelling wave direction; a new reactor is sequentially provided with a starting source module and a plurality of new fuel modules at zero burnup; all the modules are coaxially assembled in the travelling wave direction by means of an assembling parts, and each module further includes a heat pipe; during assembly, the heat pipe in each module positioned at a front part sequentially passes through all the modules positioned at a rear portion thereof and extends out of the module at a rear end; and after a period of time of burn-up, the reactor core of the travelling wave reactor is provided with the starting source module, a spent fuel module, a critical fuel module and the new fuel module sequentially in the travelling wave direction.

    Method for prediction of light water reactor fuel defects using a fuel condition index
    6.
    发明授权
    Method for prediction of light water reactor fuel defects using a fuel condition index 有权
    使用燃料条件指数预测轻水反应堆燃料缺陷的方法

    公开(公告)号:US09472311B2

    公开(公告)日:2016-10-18

    申请号:US14259955

    申请日:2014-04-23

    申请人: AREVA Inc.

    IPC分类号: G21C17/07 G21C7/06

    CPC分类号: G21C7/06 G21C17/06

    摘要: A method to assess light water reactor fuel integrity is presented having the steps of granting access in a nuclear reactor fuel pool to at least one of a discharged fuel rod and a nuclear fuel assembly, calculating an operating flux for the fuel rod, measuring a thickness of CRUD on the fuel rod, measuring a thickness of oxide on the fuel rod, calculating a maximized flux for the at least one fuel rod for a position of the one fuel rod in a nuclear reactor, calculating a maximized deposit for the fuel rod, calculating a maximized oxide thickness for the fuel rod, calculating a fuel condition index of the fuel rod, comparing the fuel condition index to an index constant, and removing the fuel rod from operation when the fuel condition index is greater than the index constant.

    摘要翻译: 提出了一种评估轻水反应堆燃料完整性的方法,其具有以下步骤:在核反应堆燃料池中进入至排放的燃料棒和核燃料组件中的至少一个,计算燃料棒的工作流量,测量厚度 在燃料棒上测量燃料棒上的氧化物的厚度,计算用于核反应堆中一个燃料棒的位置的至少一个燃料棒的最大通量,计算燃料棒的最大沉积物, 计算燃料棒的最大化氧化物厚度,计算燃料棒的燃料条件指数,将燃料条件指数与指数常数进行比较,以及当燃料条件指数大于指标常数时将燃料棒从操作中去除。

    Nuclear reactor internal hydraulic control rod drive mechanism assembly
    8.
    发明授权
    Nuclear reactor internal hydraulic control rod drive mechanism assembly 有权
    核反应堆内部液压控制杆驱动机构总成

    公开(公告)号:US08953732B2

    公开(公告)日:2015-02-10

    申请号:US13314506

    申请日:2011-12-08

    IPC分类号: G21C7/06 G21C7/16 H02K33/00

    CPC分类号: G21C7/16 H02K33/00 Y02E30/39

    摘要: A control rod drive system for a nuclear reactor that employs hydraulic cylinders to operate a conventional plunger/gripper drive system to incrementally move control rods into and out of the core of a reactor. The pressure differential for driving hydraulic pistons within the cylinders is obtained from the difference in pressure between the outside and inside of the core barrel of the reactor and control of the pistons is obtained from external solenoids attached to the reactor control system. The external solenoids regulate a charging pump feed to Poppet valves that control the hydraulic feed to the cylinders. A hydraulic piston/cylinder drive is also provided for the shutdown rods which operate in either an all in or out of the core condition.

    摘要翻译: 一种用于核反应堆的控制杆驱动系统,其使用液压缸来操作常规的柱塞/夹具驱动系统,以将控制棒逐渐地移动到反应器的芯中并将其移出。 用于驱动气缸内的液压活塞的压力差是从反应堆的芯筒的外部和内部之间的压力差获得的,而活塞的控制由连接到反应器控制系统的外部螺线管获得。 外部螺线管调节充气泵进给到提升阀,控制液压进给气缸。 还提供了用于关闭杆的液压活塞/气缸驱动器,其操作在内部或外部的核心状态。

    Structure for suppressing flow vibration of instrumentation guide tube
    9.
    发明授权
    Structure for suppressing flow vibration of instrumentation guide tube 有权
    用于抑制仪表导管流动振动的结构

    公开(公告)号:US08903032B2

    公开(公告)日:2014-12-02

    申请号:US12527484

    申请日:2008-02-22

    摘要: An upper hole 37A and a lower hole 37B are provided at two positions, namely, upper and lower portions, of a side surface of a guide tube 27, and a thimble tube 22 is pressed against an inner circumferential surface of the guide tube 27, by a differential pressure between coolant inside and outside the upper hole 37A and the lower hole 37B. It is preferable that an upper pressure adjustment hole and a lower pressure adjustment hole are provided at two positions, namely, upper and lower portions, of a side surface of an upper core support column 21, and a coolant flowing into the guide tube from an upper end of the guide tube flows out to the outside from inside the guide tube through a gap between the thimble tube and the upper hole, and also flows out to the outside from inside the upper core support column through the upper pressure adjustment hole, and a coolant flowing into the guide tube from a lower end of the guide tube flows out to the outside from inside the guide tube through a gap between the thimble tube and the lower hole, and also flows out to the outside from inside the upper core support column through the lower pressure adjustment hole.

    摘要翻译: 在引导管27的侧面的两个位置,即上下部分设置有上孔37A和下孔37B,并且将套管22压靠在引导管27的内周面上, 通过上部孔37A和下部孔37B的内部和外部的冷却剂之间的压力差。 优选的是,上压力调节孔和下压力调节孔设置在上芯支撑柱21的侧表面的两个位置,即上部和下部,以及从上部芯支撑柱21的侧表面流入导管的冷却剂 引导管的上端通过引导管和上孔之间的间隙从导管的内部流出到外部,并且还通过上压力调节孔从上芯支撑柱的内部流出到外部,并且 从引导管的下端流入引导管的冷却剂通过引导管和下孔之间的间隙从引导管的内部流出到外部,并且还从上部芯支撑体内部流出到外部 柱通过下压力调节孔。

    Reactor core of liquid metal cooled reactor
    10.
    发明授权
    Reactor core of liquid metal cooled reactor 失效
    液态金属冷却反应堆的反应堆芯

    公开(公告)号:US08711997B2

    公开(公告)日:2014-04-29

    申请号:US13361543

    申请日:2012-01-30

    IPC分类号: G21C7/06 G21C7/00

    摘要: A reactor core is immersed in a liquid metal coolant in a core barrel of a liquid metal cooled reactor. The reactor core includes a plurality of fuel assemblies contained in the core barrel, a neutron absorber that absorbs a neutron in the reactor core, and a neutron moderator that moderates a neutron therein so as to control a reactivity of the reactor core. The neutron absorber and the neutron moderator constitute a mixture contained in reactivity control assemblies of the reactor core in the liquid metal coolant prior to immersion of the reactor core. The neutron moderator is composed of zirconium hydride.

    摘要翻译: 将反应堆芯浸入液态金属冷却反应器的芯筒中的液态金属冷却剂中。 反应堆堆芯包括在核心筒中包含的多个燃料组件,吸收反应堆芯中的中子的中子吸收器和缓和其中的中子以控制反应堆芯的反应性的中子减速剂。 中子吸收器和中子慢化剂构成在反应堆芯浸入之前液态金属冷却剂中的反应堆芯的反应性控制组件中所含的混合物。 中子减速剂由氢化锆组成。