-
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。
-
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.
-
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。
-
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.
-
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。
-
公开(公告)号：US4822557A
公开(公告)日：1989-04-18
申请号：US19600
申请日：1987-02-26
摘要： An emergency reactor core cooling structure comprises a flow passage provided on an upper core plate so as to extend downward therefrom into the core. The flow passage has an orifice member at a lower portion thereof. The orifice member has such a portion that the cross-sectional area of the flow passage is made minimal at the orifice member. The flow passage causes the cooling water held on the upper plate by vapor flowing up on an accident to flow down therethrough, whereby the core is cooled rapidly.
摘要翻译： 应急堆芯冷却结构包括设置在上芯板上以从其向下延伸到芯中的流动通道。 流动通道在其下部具有孔部件。 孔口部件具有这样的部分，使得流道的横截面积在孔口部件处被制成最小。 流动通道使得由于蒸汽在事故中向上流动而保持在上板上的冷却水向下流动，由此芯体被快速冷却。
-
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。
-
公开(公告)号：US4734249A
公开(公告)日：1988-03-29
申请号：US652460
申请日：1984-09-20
CPC分类号： G21C7/00 , G21Y2002/201 , G21Y2004/302 , G21Y2004/40 , Y02E30/31 , Y02E30/39
摘要： A nuclear reactor start-up method of starting up a boiling water reactor which is in the cold shut-down state. The method includessetting a subcooled temperature of a coolant in a reactor core inlet to a range smaller than a critical subcooled temperature which is determined by the condition whereby the coolant starts boiling in the reactor core and the condition whereby the instability due to a periodic variation of buoyancy begins,thereafter starting an increase of power of the reactor.
摘要翻译： 启动处于冷关闭状态的沸水反应堆的核反应堆起动方法。 该方法包括将反应堆芯入口中的冷却剂的过冷温度设定为小于由冷却剂在反应堆堆芯中开始沸腾的条件确定的临界过冷温度的范围以及由于周期性变化引起的不稳定性的条件 的浮力开始，之后开始反应堆的功率的增加。
-
-
-
-
-
-
-
搜索结果
8 条记录 (耗时 0.051 秒)
