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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
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。
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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
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。
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公开(公告)号：US5272737A
公开(公告)日：1993-12-21
申请号：US760968
申请日：1991-09-17
申请人： Tadashi Fujii , Yoshiyuki Kataoka , Tohru Fukui , Masataka Hidaka , Toshitsugu Nakao , Shigeo Hatamiya , Hiroaki Suzuki , Masanori Naitoh , Isao Sumida , Kenji Tominaga , Tsuyoshi Niino
发明人： Tadashi Fujii , Yoshiyuki Kataoka , Tohru Fukui , Masataka Hidaka , Toshitsugu Nakao , Shigeo Hatamiya , Hiroaki Suzuki , Masanori Naitoh , Isao Sumida , Kenji Tominaga , Tsuyoshi Niino
CPC分类号： G21C15/18 , G21C13/00 , G21C9/004 , G21Y2002/206 , G21Y2004/305 , G21Y2004/402 , Y02E30/40
摘要： There is disclosed a nuclear reactor installation. An accumulator-type emergency core cooling system, a gravity-driven core cooling system and an equalizing system for submerging a reactor core are provided within a primary containment vessel containing a reactor pressure vessel in which the reactor core is disposed. These cooling systems are automatically operated sequentially in accordance with the pressure in the reactor pressure vessel without the need for any particular powered source. The primary containment vessel is made of steel, and the interior of this containment vessel is divided into a space containing the reactor pressure vessel and a space containing an operation floor in such a manner that the two spaces are isolated from each other. An opening device is provided between the two spaces so as to communicate the two spaces with each other in the event of an accident, the upper portion of the primary containment vessel being air-cooled while the lower portion of this containment vessel being water-cooled.
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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
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。
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公开(公告)号：US5021212A
公开(公告)日：1991-06-04
申请号：US522033
申请日：1990-05-11
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.
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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
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。
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公开(公告)号：US4992231A
公开(公告)日：1991-02-12
申请号：US587525
申请日：1984-03-08
摘要： An emergency core cooling system for spraying cooling water onto a nuclear reactor core of a nuclear reactor includes at least one header disposed in the nuclear reactor and arranged at an upper and outer circumferential position with respect to the reactor core. A plurality of spray nozzles are mounted on the at least one header for spraying cooling water onto the reactor core. The spray nozzles have a center axis and at least one of the plurality of spray nozzles is mounted on the at least one header so that the center axis thereof extends upwardly with respect to a horizontal axis whereas at least one of the remaining plurality of spray nozzles has the center axis thereof extending downwardly with respect to the horizontal axis. Cooling water is conducted to the at least one header for enabling spraying of the water in the emergency situation.
摘要翻译： 用于将冷却水喷射到核反应堆的核反应堆核心上的应急芯冷却系统包括至少一个设置在核反应堆中并且相对于反应堆堆芯的上外周位置设置的集管。 多个喷嘴安装在至少一个集管上，用于将冷却水喷射到反应堆堆芯上。 喷嘴具有中心轴线，并且多个喷嘴中的至少一个安装在至少一个集管上，使得其中心轴线相对于水平轴线向上延伸，而剩余的多个喷嘴中的至少一个喷嘴 其中心轴线相对于水平轴线向下延伸。 冷却水被引导到至少一个头部，以便在紧急情况下喷洒水。
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8.发明授权
公开(公告)号：US4877574A
公开(公告)日：1989-10-31
申请号：US162987
申请日：1988-03-02
申请人： Hiroaki Suzuki , Yoshiyuki Kataoka , Michio Murase , Kotaro Inoue , Isao Sumida , Shozo Yamanari , Masaki Matsumoto , Satoshi Miura , Koji Hashimoto
发明人： Hiroaki Suzuki , Yoshiyuki Kataoka , Michio Murase , Kotaro Inoue , Isao Sumida , Shozo Yamanari , Masaki Matsumoto , Satoshi Miura , Koji Hashimoto
IPC分类号： G21C7/32
摘要： A natural circulation reactor includes a reactor pressure vessel, a cylindrical shroud disposed within the reactor pressure vessel to surround a reactor core and to extend to a position above the reactor core, and a coolant descending passage defined between the reactor pressure vessel and the shroud for allowing the coolant discharged from the top of the reactor core to be again supplied to the bottom of the reactor core. In such a natural circulation reactor, a liquid level of coolant in the coolant descending passage is adjusted on the basis of a reactor power request signal at a position below a liquid level of coolant in the shroud, and thus reactor power is controlled so that it may reach a predetermined reactor power by adjusting the liquid level of coolant in the coolant descending passage.
摘要翻译： 自然循环反应器包括反应堆压力容器，设置在反应堆压力容器内以围绕反应堆堆芯并延伸到反应堆堆芯上方位置的圆柱形护罩，以及在反应堆压力容器和护罩之间限定的冷却剂下降通道， 允许将从反应堆堆芯顶部排出的冷却剂再次供应到反应堆堆芯的底部。 在这样的自然循环反应器中，根据在护罩中的冷却剂液面以下的位置的反应堆功率要求信号来调节冷却剂下降通道中的冷却剂液面，从而控制反应堆功率 可以通过调节冷却剂下降通道中的冷却剂的液位来达到预定的反应堆功率。
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公开(公告)号：US4859401A
公开(公告)日：1989-08-22
申请号：US896256
申请日：1986-08-14
IPC分类号： G21C15/18
摘要： The emergency core cooling structure according to the present invention is provided with a water storage container which holds therein emergency cooling water to be supplied to a core region in a nuclear reactor in case of an emergency, for example, when the primary cooling water flows out from a reactor vessel, so as to maintain the temperature of the emergency cooling water in the upper portion of the water storage container in a level higher than the level of that of the emergency cooling water in the lower portion thereof, the lower portion of the water storage container, which is filled with the low-temperature cooling water, being communicated at all times with the core of the nuclear reactor by a means which has substantially no movable member. When the primary cooling water flows out, so that the pressure in a reactor vessel decreases, the emergency cooling water in the high-temperature region is boiled to expand to cause the low-temperature emergency cooling water in the lower portion of the water storage container to be raised, the resultant low-temperature emergency cooling water being supplied to the core region.
摘要翻译： 根据本发明的应急芯冷却结构设置有储水容器，其在紧急情况下容纳供应到核反应堆中的核心区域的应急冷却水，例如当主冷却水流出时 从反应堆容器中将储水容器上部的应急冷却水的温度保持在比其下部的应急冷却水的高度高的水平， 填充有低温冷却水的蓄水容器通过基本上不具有可移动构件的装置始终与核反应堆的核心连通。 当主冷却水流出时，反应堆容器内的压力降低，高温区域的应急冷却水沸腾而膨胀，从而使储水容器下部的低温应急冷却水 要升高，所得到的低温应急冷却水被供给到核心区域。
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10.发明授权Cooling system for primary containment vessel in nuclear power plant and component for use in said cooling system 失效用于核电站的初级安全壳的冷却系统和用于所述冷却系统的部件
公开(公告)号：US5491730A
公开(公告)日：1996-02-13
申请号：US177723
申请日：1994-01-05
CPC分类号： G21C15/18 , G21Y2002/201 , G21Y2002/206 , G21Y2004/302 , Y02E30/40
摘要： Pipes are mounted horizontally on an outlet portion of a gas vent pipe in a condenser-type heat removal system, and have-openings which are formed only in a portion below a horizontal plane in which axes of these pipes lie, thereby enlarging a region where uncondensed steam is mixed with water in a suppression pool. With this arrangement, a surface portion of the water of the suppression pool is prevented from becoming hot, and the temperature of this pool water is uniformed. As a result, the temperature of the water surface of the suppression pool is lowered, thereby decreasing the pressure within a primary containment vessel. This enhances the reliability of the primary containment vessel, and reduces a design strength of the primary containment vessel.
摘要翻译： 管道水平地安装在冷凝器型除热系统中的排气管的出口部分上，并且具有仅在这些管的轴线所在的水平面下方形成的开口，从而扩大了 未冷凝的蒸汽与抑制池中的水混合。 通过这种布置，可以防止抑制池的水的表面部分变热，并且使该池水的温度均匀。 结果，抑制池的水面的温度降低，从而降低主要容纳容器内的压力。 这增强了主要容纳容器的可靠性，并且降低了主要容纳容器的设计强度。
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