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    Reactor containment vessel
    1.
    发明授权
    Reactor containment vessel 失效
    反应堆安全壳

    公开(公告)号：US5096659A

    公开(公告)日：1992-03-17

    申请号：US436194

    申请日：1989-11-14

    申请人： Masataka Hidaka ,  Shigeo Hatamiya ,  Terufumi Kawasaki ,  Toru Fukui ,  Hiroaki Suzuki ,  Yoshiyuki Kataoka ,  Ryuhei Kawabe ,  Michio Murase ,  Masanori Naitoh

    发明人： Masataka Hidaka ,  Shigeo Hatamiya ,  Terufumi Kawasaki ,  Toru Fukui ,  Hiroaki Suzuki ,  Yoshiyuki Kataoka ,  Ryuhei Kawabe ,  Michio Murase ,  Masanori Naitoh

    IPC分类号： G21C9/004 ,  G21C15/18

    CPC分类号： G21C15/18 ,  Y02E30/40

    摘要： A reactor containment vessel comprises typically a reactor pressure vessel housed in a dry well of the reactor containment vessel, a vent passage through which steam in the dry well is introduced into coolant accommodated in a pressure suppression chamber of the reactor containment vessel, a closed space formed at a position lower than the level of the normal liquid surface of the coolant, a first passage having an inlet opened into the pressure suppression chamber at a level higher than that of the normal liquid surface of the coolant and an outlet opened into the closed space, and a second passage communicating between the closed space and the dry well through a counter flow preventing arrangement for checking the flow directed toward the closed space, and therefore, noncondensable gas and liquid accumulated in the pressure suppression chamber are discharged into the dry well the pressure in which is higher than that in the pressure suppression chamber by making use of a difference in water head increased due to increase of the liquid while allowing fluid to be condensed to newly flow into the pressure suppression chamber from the dry well so as to be condensed, over a long cooling period after the occurrence of an accident of piping fracture in the reactor containment vessel. Owing to condensation, the pressure in the reactor containment vessel can be reduced, and moreover, fluid can make a natural circulation in a closed circuit passing through the dry well, the pressure suppression chamber and the closed space in order without flowing outside the circuit.

    摘要翻译： 反应堆容纳容器通常包括容纳在反应堆容纳容器的干燥井中的反应堆压力容器，将干井中的蒸汽引入容纳在反应堆容纳容器的压力抑制室中的冷却剂的通气通道，封闭空间 形成在低于冷却剂的正常液面的水平的位置处，具有以比冷却剂的通常液面高的水平方向通向压力抑制室的入口的第一通道和敞开的冷却剂出口 空间，以及第二通道，通过用于检查朝向封闭空间的流动的逆流防止装置在封闭空间和干井之间连通，因此积聚在压力抑制室中的不凝结气体和液体被排放到干井中 通过利用差i，其压力高于压力抑制室中的压力 n水头由于液体的增加而增加，同时允许流体冷凝，从干井中新流入压力抑制室，以便在发生管道破裂事故之后的长时间冷却期间冷凝 反应堆安全壳。 由于冷凝，可以减少反应堆容纳容器内的压力，而且，流体可以在通过干井，压力抑制室和封闭空间的闭路中自然循环，而不会流过电路外。

    Reactor containment vessel
    2.
    发明授权
    Reactor containment vessel 失效
    反应堆安全壳

    公开(公告)号：US5211906A

    公开(公告)日：1993-05-18

    申请号：US615921

    申请日：1990-11-20

    申请人： Shigeo Hatamiya ,  Masanori Naitoh ,  Yoshiyuki Kataoka ,  Hiroaki Suzuki ,  Isao Sumida ,  Toshitsugu Nakao ,  Kanehiro Ochiai ,  Tsuyoshi Niino ,  Masataka Hidaka ,  Tohru Fukui ,  Ryuhei Kawabe

    发明人： Shigeo Hatamiya ,  Masanori Naitoh ,  Yoshiyuki Kataoka ,  Hiroaki Suzuki ,  Isao Sumida ,  Toshitsugu Nakao ,  Kanehiro Ochiai ,  Tsuyoshi Niino ,  Masataka Hidaka ,  Tohru Fukui ,  Ryuhei Kawabe

    IPC分类号： G21C13/00 ,  G21C15/18

    CPC分类号： G21C13/00 ,  G21C15/18 ,  Y02E30/40

    摘要： A pressure control chamber of a reactor containment vessel for receiving the atmosphere of the reactor containment vessel containing leakage steam developing in the event of an accident includes a pressure control pool, and a wet well disposed above the pressure control pool. The wet well is divided into an inner peripheral portion and an outer peripheral portion. The inner and outer peripheral portions are communicated with each other via the pressure control pool. An outlet port for flowing the atmosphere of the reactor containment vessel containing the leakage steam is provided at the inner peripheral side of the pressure control pool. When the atmosphere of the reactor containment vessel containing the leakage steam is introduced into the pressure control pool in the event of the accident, this atmosphere is condensed by the water in the pressure control pool, and the gas of this atmosphere not condensed is accumulated in the inner peripheral portion of the wet well. As a result, the pressure within the inner peripheral portion is increased to increase the water level of the pressure control pool at the outer peripheral portion, so that the area of contact of a reactor containment vessel wall with the pressure control pool water is increased, thereby enhancing a heat radiation performance of the reactor containment vessel.

    摘要翻译： 用于接收包含在发生事故的情况下发生的泄漏蒸汽的反应堆容纳容器的气氛的反应堆容纳容器的压力控制室包括压力控制池和设置在压力控制池上方的湿井。 湿井分为内周部和外周部。 内外周部经由压力控制池相互连通。 在压力控制池的内周侧设置有用于使含有泄漏蒸汽的反应堆容纳容器的气流流出的出口。 当发生事故时，含有泄漏蒸汽的反应堆容纳容器的气氛被引入压力池中，该压力控制池中的水被浓缩，而且未浓缩的该气氛气体被积聚在 湿井的内周部分。 结果，增加了内周部分内的压力，以增加外周部分的压力控制池的水位，从而增加了反应堆容器壁与压力控制池水的接触面积， 从而提高反应堆容纳容器的散热性能。

    Reactor containment facilities
    4.
    发明授权
    Reactor containment facilities 失效
    反应堆遏制设施

    公开(公告)号：US5295169A

    公开(公告)日：1994-03-15

    申请号：US775850

    申请日：1991-10-15

    申请人： Kenji Tominaga ,  Tetsuo Horiuchi ,  Tsuyoshi Niino ,  Shouichiro Kinoshita ,  Shozo Yamanari ,  Masanori Naitoh ,  Tohru Fukui ,  Michio Murase ,  Yoshiyuki Kataoka ,  Masataka Hidaka ,  Isao Sumida

    发明人： Kenji Tominaga ,  Tetsuo Horiuchi ,  Tsuyoshi Niino ,  Shouichiro Kinoshita ,  Shozo Yamanari ,  Masanori Naitoh ,  Tohru Fukui ,  Michio Murase ,  Yoshiyuki Kataoka ,  Masataka Hidaka ,  Isao Sumida

    IPC分类号： G21C9/004 ,  G21C15/18 ,  G21C9/00

    CPC分类号： G21C15/18 ,  G21C9/004 ,  G21Y2002/201 ,  G21Y2002/301 ,  G21Y2004/30 ,  Y02E30/40

    摘要： A reactor containment facility having a reactor pressure vessel containing a core; a dry well in which the reactor pressure vessel is arranged; a suppression chamber holding suppression-pool water and forming above the suppression-pool water a wet well; and a plurality of vent pipes allowing the dry well to communicate with the suppression-pool water; a steel wall which is in contact with the suppression-pool water of the suppression chamber and which surrounds at least the pool water so as to form a containment vessel which houses the dry well and the suppression chamber; and an outer peripheral pool containing cooling water in contact with the outer peripheral surface of the steel wall. The facility further includes: a dividing structure for dividing the wet well of the suppression chamber into a first space which is in contact with the water surface of the suppression-pool water and a second space which is not in contact therewith; a first passage which allows the first space to communicate with the second space and which has an area smaller than that of the dividing device; and a cooling device for keeping the second space at a temperature lower than that of the first space.

    摘要翻译： 一种具有含有核的反应堆压力容器的反应堆容纳设备; 设置反应堆压力容器的干井; 一个抑制池保持抑制池水，并在抑制池水上形成一个湿井; 以及允许干井与抑制池水连通的多个排气管; 与隔离室的抑制池水接触并且至少围绕池水的钢壁，以形成容纳干井和抑制室的容纳容器; 以及包含与钢壁的外周面接触的冷却水的外周池。 该设备还包括：分隔结构，用于将抑制室的湿井分为与抑制池水的水面接触的第一空间和与其不接触的第二空间; 第一通道，其允许所述第一空间与所述第二空间连通并且其面积小于所述分隔装置的面积; 以及用于将第二空间保持在低于第一空间的温度的冷却装置。

    Boiling water nuclear reactor and start-up process thereof
    5.
    发明授权
    Boiling water nuclear reactor and start-up process thereof 失效
    沸水核反应堆及其启动过程

    公开(公告)号：US5271044A

    公开(公告)日：1993-12-14

    申请号：US851198

    申请日：1991-03-14

    申请人： Masataka Hidaka ,  Michio Murase ,  Toshitsugu Nakao ,  Akihiko Minato ,  Shigeto Murata ,  Yoshiyuki Kataoka ,  Shoichiro Kinoshita

    发明人： Masataka Hidaka ,  Michio Murase ,  Toshitsugu Nakao ,  Akihiko Minato ,  Shigeto Murata ,  Yoshiyuki Kataoka ,  Shoichiro Kinoshita

    IPC分类号： G21D3/08 ,  G21C7/00

    CPC分类号： G21D3/08 ,  G21Y2002/202 ,  G21Y2002/207 ,  G21Y2004/403 ,  Y02E30/40

    摘要： In a boiling water nuclear reactor, a reactor primary cooling water line is filled with water at the start-up time, and the inside of a pressure vessel is pressurized by a pressurized tank and at the same time control rods are withdrawn to thereby heat cooling water in a state of single-phase flow to high temperature. Succeedingly, the pressurization is released and the pressure of the pressure vessel is gradually approximated to the saturation pressure corresponding to the cooling water temperature to thereby make the cooling water transit into a state of two-phase flow, and thereafter the cooling water is heated by nuclear reaction in the state of two-phase flow to thereby obtain predetermined reactor running temperature and pressure. This prevents the flow fluctuation and the reduction of stability of core due to occurrence of unstable phenomena of low temperature two-phase flow at the start-up time of the reactor to thereby make it possible to perform stable starting-up of the reactor and to shorten the start-up time of the reactor to thereby realize improvement in economy as well as reliability.

    摘要翻译： 在沸水核反应堆中，反应器一次冷却水管线在启动时由水填充，压力容器的内部由加压罐加压，同时将控制棒取出，从而加热冷却 水处于单相流向高温状态。 成功地释放加压，压力容器的压力逐渐接近对应于冷却水温度的饱和压力，从而使冷却水进入两相流动状态，之后将冷却水加热 核反应处于两相流状态，从而获得预定的反应器运行温度和压力。 由此，由于在反应器的起动时由于低温两相流的不稳定现象的发生而防止了芯的流动波动和稳定性的降低，从而能够稳定地起动反应器， 缩短反应堆的启动时间，从而实现经济性和可靠性的提高。

    Primary containment vessel with outer pool
    6.
    发明授权
    Primary containment vessel with outer pool 失效
    带外池的主容舱

    公开(公告)号：US5021212A

    公开(公告)日：1991-06-04

    申请号：US522033

    申请日：1990-05-11

    申请人： Yoshiyuki Kataoka ,  Isao Sumida ,  Masataka Hidaka ,  Masanori Naitoh

    发明人： Yoshiyuki Kataoka ,  Isao Sumida ,  Masataka Hidaka ,  Masanori Naitoh

    IPC分类号： G21C9/004 ,  G21C9/012 ,  G21C13/00 ,  G21C15/18

    CPC分类号： G21C15/18 ,  G21C9/012 ,  G21Y2002/206 ,  G21Y2004/302 ,  Y02E30/40

    摘要： A primary containment vessel, comprising a reactor pressure vessel in which a core is accommodated, a dry-well volume covering the upper portion of the reactor pressure vessel, a suppression chamber provided with a suppression pool surrounding an intermediate portion of the reactor pressure vessel, has a plurality of vent tubes establishing a connection between the dry-well volume and the suppression pool and an annular baffle plate disposed in the suppression pool along the side wall of the suppression chamber, having its top end positioned at a height between a free surface of the suppression pool and an outlet of the vent tube opened in the suppression pool and its lower end positioned at a height between the outlet and the bottom of the suppression pool. If a loss of coolant accident occurs, hot steam discharged into the dry-well volume is discharged into the suppression pool through the vent tube so as to heat water on the inside of the baffle plate. The water head difference generated by the water temperature difference between the inside and the outside portions of the baffle plate causes a vertical convection passing through the baffle plate to be created. Therefore, the heat accumulating characteristics of pool water and the heat radiation performance of the containment vessel are improved, allowing the size of the containment vessel to be reduced.

    Nuclear reactor
    7.
    发明授权
    Nuclear reactor 失效
    核反应堆

    公开(公告)号：US5513233A

    公开(公告)日：1996-04-30

    申请号：US272117

    申请日：1994-07-07

    申请人： Masataka Hidaka ,  Shinichi Kashiwai ,  Yoshinori Saito ,  Terufumi Kawasaki

    发明人： Masataka Hidaka ,  Shinichi Kashiwai ,  Yoshinori Saito ,  Terufumi Kawasaki

    IPC分类号： G21C15/02 ,  G21C15/00 ,  G21C3/322

    CPC分类号： G21C15/02 ,  G21Y2002/201 ,  G21Y2004/302 ,  Y02E30/40

    摘要： Improved operability and economy of a nuclear reactor can be obtained by attaining a mixing of the flows of coolant in the lower plenum of the fuel assemblies of the nuclear reactor, a high flow stability of the two-phase flow in the fuel assemblies and a small pressure loss in the core. To achieve this, there is provided a coolant guide tube 60 that communicates with the inside of the fuel support piece 12 inserted in the control rod guide tube and the passage 16, wherein there is formed a coolant guide passage 61 along which coolant descends in the area outside of the coolant guide tube in the fuel assemblies from opening 79. The coolant guide passage along which the coolant descends from the opening is formed in an area outside of the coolant guide tube in the fuel support piece.

    摘要翻译： 通过实现核反应堆的燃料组件的下部气室中的冷却剂流的混合，燃料组件中的两相流的高流动稳定性和小的燃料组件的小流量混合，可以获得核反应堆的可操作性和经济性的改善 核心压力损失。 为了实现这一点，提供了一种冷却剂引导管60，其与插入控制棒导管和通道16中的燃料支撑件12的内部连通，其中形成有冷却剂引导通道61，冷却剂引导管 燃料组件中的冷却剂引导管外部的开口79.冷却剂引导通道在冷却剂引导管的外侧形成在燃料支撑件的冷却剂导管的外侧。