Fully passive decay heat removal system for sodium-cooled fast reactors that utilizes partially immersed decay heat exchanger
    1.
    发明授权
    Fully passive decay heat removal system for sodium-cooled fast reactors that utilizes partially immersed decay heat exchanger 有权
    用于采用部分浸入式衰变热交换器的钠冷快堆的完全被动衰变除热系统

    公开(公告)号:US08670518B2

    公开(公告)日:2014-03-11

    申请号:US12572851

    申请日:2009-10-02

    IPC分类号: G21C9/00 G21C15/18 G21C15/00

    CPC分类号: G21C15/18 G21C1/03 Y02E30/34

    摘要: Disclosed herein is a fully passive decay heat removal system utilizing a partially immersed heat exchanger, the system comprising: a hot pool; an intermediate heat exchanger which heat-exchanges with the sodium of the hot pool; a cold pool; a support barrel extending vertically through the boundary between the hot pool and the cold pool; a sodium-sodium decay heat exchanger received in the support barrel; a sodium-air heat exchanger provided at a position higher than the sodium-sodium decay heat exchanger; an intermediate sodium loop connecting the sodium-sodium decay heat exchanger with the sodium-air heat exchanger; and a primary pump, wherein a portion of the effective heat transfer tube of the sodium-sodium decay heat exchanger is immersed in the cold pool, particularly in a normal operating state, and the surface of the lower end of a shroud for the sodium-sodium decay heat exchanger, the lower end being immersed in the sodium of the cold pool, has perforated holes.

    摘要翻译: 本文公开了一种利用部分浸没的热交换器的完全被动的衰变热去除系统,该系统包括:热水池; 与热水池的钠进行热交换的中间热交换器; 一个冷水池 一个垂直穿过热水池和冷水池边界的支撑桶; 接收在支撑筒中的钠钠衰变热交换器; 设置在高于钠钠衰变热交换器的位置的钠空气热交换器; 将钠钠衰变热交换器与钠空气热交换器连接的中间钠环路; 和主泵,其中钠钠衰变换热器的有效传热管的一部分浸入冷库中,特别是在正常运行状态下,并且钠 - 钠衰变换热器,下端浸入冷库钠中,具有穿孔。

    Passive safety-grade decay-heat removal method and decay-heat removal system for LMR with pool direct heat cooling process

    公开(公告)号:US20050135544A1

    公开(公告)日:2005-06-23

    申请号:US10677941

    申请日:2003-10-01

    IPC分类号: G21C1/02 G21C9/00 G21C15/18

    摘要: Dis0closed herein is a direct pool cooling type passive safety grade decay heat removal method and system for removing core decay heat in a pool type liquid metal reactor when a normal heat removal system breaks down. In the liquid metal reactor comprising a reactor vessel, the interior of which is partitioned into a hot pool above a core and a cold pool around the core so that liquid level difference between the hot pool and the cold pool is maintained by a primary pumping head under normal steady-state conditions, is disposed at least one circular vertical tube in such a manner that the sodium in the circular vertical tube is maintained with the same liquid level as the liquid level of the sodium in the cold pool. In the circular vertical tube is disposed a sodium-sodium heat exchanger, which is connected to a sodium-air heat exchanger mounted above a reactor building via a heat removing sodium loop, in such a manner that it is placed at the position higher than a liquid level of the sodium in the cold pool under the normal steady-state conditions. Under transient conditions, for example, when the normal heat removal system breaks down, the primary pump is automatically tripped, and accordingly the liquid level of the cold pool rises with the result that the liquid level difference between the hot pool and the cold pool is eliminated. Consequently, the sodium-sodium heat exchanger makes direct contact with the hot sodium so that core decay heat is discharged into a final heat sink, for example, the atmosphere. In this way, the decay heat removal system of the present invention is operated on the basis of a completely passive concept with improved operational reliability. Heat loss incurred by the decay heat removal system is minimized under normal steady-state conditions, whereby economical efficiency is maximized. The decay heat removal system of the present invention can effectively remove core decay heat under transient conditions. Moreover, the decay heat removal system of the present invention provides an additional heat removal capacity obtained by the passive vessel cooling system, whereby the decay heat removal system of the present invention can be easily applied to a large thermal rated liquid metal reactor.

    Decay heat removal system comprising heat pipe heat exchanger
    3.
    发明授权
    Decay heat removal system comprising heat pipe heat exchanger 有权
    包括热管换热器的衰变除热系统

    公开(公告)号:US08300759B2

    公开(公告)日:2012-10-30

    申请号:US12355088

    申请日:2009-01-16

    IPC分类号: G21C9/00

    CPC分类号: G21C15/18 Y02E30/40

    摘要: Disclosed herein is a decay heat removal system, including: a decay heat exchanger that absorbs decay heat generated by a nuclear reactor; a heat pipe heat exchanger that receives the decay heat from the decay heat exchanger through a sodium loop for heat removal and then discharges the decay heat to the outside; and a sodium-air heat exchanger that is connected to the heat pipe heat exchanger through the sodium loop and discharges the decay heat transferred thereto through the sodium loop to the outside. According to the decay heat removal system, a heat removal capability can be realized by the heat pipe heat exchanger at such a high temperature at which the safety of a nuclear reactor is under threat, and a cooling effect can be obtained through the sodium-air heat exchanger at a temperature lower than that temperature.

    摘要翻译: 本文公开了一种衰变除热系统,包括:衰变热交换器,其吸收由核反应堆产生的衰变热; 热管式热交换器,其通过钠回路接收来自衰变热交换器的衰减热,用于除热,然后将衰变热量排出到外部; 以及钠 - 空气热交换器,其通过钠回路连接到热管热交换器,并将通过钠回路传递到其的衰变热排出到外部。 根据衰变除热系统,在核反应堆的安全性受到威胁的高温下,热管换热器可以实现除热能力,通过钠空气可以获得冷却效果 热交换器的温度低于该温度。

    DECAY HEAT REMOVAL SYSTEM COMPRISING HEAT PIPE HEAT EXCHANGER
    4.
    发明申请
    DECAY HEAT REMOVAL SYSTEM COMPRISING HEAT PIPE HEAT EXCHANGER 有权
    包括热管换热器的减热装置

    公开(公告)号:US20090245453A1

    公开(公告)日:2009-10-01

    申请号:US12355088

    申请日:2009-01-16

    IPC分类号: G21C9/00

    CPC分类号: G21C15/18 Y02E30/40

    摘要: Disclosed herein is a decay heat removal system, including: a decay heat exchanger that absorbs decay heat generated by a nuclear reactor; a heat pipe heat exchanger that receives the decay heat from the decay heat exchanger through a sodium loop for heat removal and then discharges the decay heat to the outside; and a sodium-air heat exchanger that is connected to the heat pipe heat exchanger through the sodium loop and discharges the decay heat transferred thereto through the sodium loop to the outside. According to the decay heat removal system, a heat removal capability can be realized by the heat pipe heat exchanger at such a high temperature at which the safety of a nuclear reactor is under threat, and a cooling effect can be obtained through the sodium-air heat exchanger at a temperature lower than that temperature.

    摘要翻译: 本文公开了一种衰变除热系统,包括:衰变热交换器,其吸收由核反应堆产生的衰变热; 热管式热交换器,其通过钠回路接收来自衰变热交换器的衰减热,用于除热,然后将衰变热量排出到外部; 以及钠 - 空气热交换器,其通过钠回路连接到热管热交换器,并将通过钠回路传递到其的衰变热排出到外部。 根据衰变除热系统,在核反应堆的安全性受到威胁的高温下,热管换热器可以实现除热能力,通过钠空气可以获得冷却效果 热交换器的温度低于该温度。

    FULLY PASSIVE DECAY HEAT REMOVAL SYSTEM FOR SODIUM-COOLED FAST REACTORS THAT UTILIZES PARTIALLY IMMERSED DECAY HEAT EXCHANGER
    5.
    发明申请
    FULLY PASSIVE DECAY HEAT REMOVAL SYSTEM FOR SODIUM-COOLED FAST REACTORS THAT UTILIZES PARTIALLY IMMERSED DECAY HEAT EXCHANGER 有权
    用于冷却的快速反应器的完全被动衰减的热去除系统,其使用部分强制衰减热交换器

    公开(公告)号:US20100177860A1

    公开(公告)日:2010-07-15

    申请号:US12572851

    申请日:2009-10-02

    IPC分类号: G21C9/00

    CPC分类号: G21C15/18 G21C1/03 Y02E30/34

    摘要: Disclosed herein is a fully passive decay heat removal system utilizing a partially immersed heat exchanger, the system comprising: a hot pool; an intermediate heat exchanger which heat-exchanges with the sodium of the hot pool; a cold pool; a support barrel extending vertically through the boundary between the hot pool and the cold pool; a sodium-sodium decay heat exchanger received in the support barrel; a sodium-air heat exchanger provided at a position higher than the sodium-sodium decay heat exchanger; an intermediate sodium loop connecting the sodium-sodium decay heat exchanger with the sodium-air heat exchanger; and a primary pump, wherein a portion of the effective heat transfer tube of the sodium-sodium decay heat exchanger is immersed in the cold pool, particularly in a normal operating state, and the surface of the lower end of a shroud for the sodium-sodium decay heat exchanger, the lower end being immersed in the sodium of the cold pool, has perforated holes.

    摘要翻译: 本文公开了一种利用部分浸没的热交换器的完全被动的衰变热去除系统,该系统包括:热水池; 与热水池的钠进行热交换的中间热交换器; 一个冷水池 一个垂直穿过热水池和冷水池边界的支撑桶; 接收在支撑筒中的钠钠衰变热交换器; 设置在高于钠钠衰变热交换器的位置的钠空气热交换器; 将钠钠衰变热交换器与钠空气热交换器连接的中间钠环路; 和主泵,其中钠钠衰变换热器的有效传热管的一部分浸入冷库中,特别是在正常运行状态下,并且钠 - 钠衰变换热器,下端浸入冷库钠中,具有穿孔。

    Passive safety-grade decay-heat removal method and decay-heat removal system for LMR with pool direct heat cooling process
    8.
    发明授权
    Passive safety-grade decay-heat removal method and decay-heat removal system for LMR with pool direct heat cooling process 失效
    被动式安全级衰变热去除方法和具有池直接散热过程的LMR的衰减散热系统

    公开(公告)号:US07522693B2

    公开(公告)日:2009-04-21

    申请号:US10677941

    申请日:2003-10-01

    IPC分类号: G21C9/00

    摘要: A direct pool cooling type passive safety grade decay heat removal method and system for removing core decay heat in a pool type liquid metal reactor when a normal heat removal system breaks down. In the liquid metal reactor comprising a reactor vessel, the interior of which is partitioned into a hot pool above a core and a cold pool around the core so that liquid level difference between the hot pool and the cold pool is maintained by a primary pumping head under normal steady-state conditions, is disposed at least one circular vertical tube in such a manner that the sodium in the circular vertical tube is maintained with the same liquid level as the liquid level of the sodium in the cold pool. In the circular vertical tube is disposed a sodium-sodium heat exchanger, which is connected to a sodium-air heat exchanger mounted above a reactor building via a heat removing sodium loop, in such a manner that it is placed at the position higher than a liquid level of the sodium in the cold pool under the normal steady-state conditions.

    摘要翻译: 一种直接游泳池冷却型被动安全等级衰变除热方法和系统,用于在普通散热系统发生故障时,在池式液态金属反应器中去除核心衰变热。 在包括反应器容器的液态金属反应器中,其内部被分配在核心上方的热池和围绕核心的冷库,使得热池和冷库之间的液位差由主泵头保持 在正常稳态条件下,以这样的方式设置至少一个圆形垂直管,使得圆形垂直管中的钠保持与冷库中钠的液面相同的液面。 在圆形垂直管中设置钠钠热交换器,该钠钠热交换器通过除热钠环连接到安装在反应堆建筑物上方的钠空气热交换器,使得它被放置在高于 液态钠在冷库中处于正常稳态条件下。