-
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：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。
-
-
-
搜索结果
64 条记录 (耗时 0.023 秒)
