![]() Cooling device for molten core material
专利摘要:
The cooling device (100) for a molten core material, comprises: two or more containers of cooling material (120) arranged under a reactor vessel (110), comprising a nuclear reactor core (112), and comprising a cooling material; a first grid (130) disposed under the two or more containers of cooling material (120) and having two or more first through holes (132); and a second grid (140) disposed under the first grid (130) and comprising two or more second through holes (142). The average size of the two or more first through holes (132) is greater than the average size of the two or more second through holes (142). Figure for the abstract: Fig 3 公开号:FR3085532A1 申请号:FR1905850 申请日:2019-06-03 公开日:2020-03-06 发明作者:Sung-Jae Yi;Hyun Sik Park;Rae-Joon Park;Ki Yong CHOI;Kwang Soon Ha;Seong-Wan HONG 申请人:Korea Atomic Energy Research Institute KAERI; IPC主号:
专利说明:
Description Title of the invention: Cooling device for molten core material REFERENCE TO PREVIOUS APPLICATIONS This application claims priority and benefit from Korean patent application No. 10-2018-0104724 filed with the Korean Intellectual Property Office on September 3, 2018. BACKGROUND OF THE INVENTION (a) Field of the Invention [0002] The invention provides a cooling device for molten core material. (b) Description of the State of the Art A nuclear reactor system is a system which generates steam using the heat of a heart which is a heating element and produces electricity using l energy of steam. Since a nuclear reactor operates in a very hot environment and since components such as a nuclear fuel rod and the like used in the nuclear reactor are highly radioactive materials, the environment around the reactor is likely to be seriously damaged in the event that a problem occurs with the reactor, without immediate countermeasures being taken. [0004] To prevent such damage from occurring, various safety systems can be provided for cooling the heat generated in a nuclear reactor core, when problems such as loss of cooling material and problems similar occur. For example, there is a security system that comes in a form where the lost cooling material is supplemented, or a security system that comes in a form where the heat generated in the nuclear reactor is absorbed and the heat generated is dissipated to a heat sink to promote cooling. However, in the event of a serious accident during which a reactor vessel melts under the effect of the heat generated in the core of the nuclear reactor and is damaged, a cooling device for cooling a molten material of the nuclear reactor core is required, in conjunction with the safety systems described above. The publication of Japanese patent No. 2017-187370 open to public inspection discloses a nuclear reactor confinement comprising a plurality of mass bodies in which a fluid such as water or a similar fluid is hermetically sealed for l possibility of a core meltdown accident. Korean Patent No. 1,546,317 discloses a mechanism for forming a porous molten core material, by which a molten core material hardens so as to have a porous structure. The above indications set out in this background section are intended only to improve the understanding of the background of the invention and may therefore contain indications which are not part of the state of the art already known in this country by those skilled in the art. Summary of the Invention An exemplary embodiment of the present invention can provide a cooling device for molten core material which has the advantage of stably and efficiently cooling molten core material when a serious accident occurs. On the other hand, an exemplary embodiment of the present invention can provide a cooling device for a molten core material which has the advantage of increasing the cooling speed and the cooling efficiency of a material. of melted heart. Furthermore, an exemplary embodiment of the present invention can provide a cooling device for a molten core material which has the advantage of preventing the formation of an agglomerate of a molten core material and of dispersing largely the molten core material. Furthermore, an exemplary embodiment of the present invention can provide a cooling device for a molten core material which has the advantage of achieving savings in terms of costs and space, when used for installation of the existing nuclear reactor. An exemplary embodiment of the present invention provides a cooling device for a molten core material, comprising: two or more containers of cooling material arranged under a reactor vessel, comprising a nuclear reactor core, and comprising a cooling material; a first grid disposed under the two or more containers of cooling material and comprising two or more first through holes; and a second grid disposed under the first grid and comprising two or more second through holes, the average size of the two or more first through holes being greater than the average size of the two or more second through holes. Brief description of the drawings [fig.lA] is a view schematically showing a general system of nuclear reactor of the loop type. [Fig. IB] is a view schematically representing a general integrated nuclear reactor system. [Fig.2A] [fig.2B] [0017] [fig.2C] are views illustrating the progress of a meltdown accident at the heart of a nuclear reactor. [Fig.3] is a view showing a cross section of a cooling device for a molten core material according to one embodiment. [Fig.4A] [fig.4B] are views illustrating an operating mode of the cooling device for a molten core material according to Figure 3. [Fig.5] is a view showing a cross section of a cooling device for a molten core material according to one embodiment. [Fig.6A] [Fig.6B] are views showing examples of a container of cooling material according to one embodiment. [Fig.7A] [Fig.7B] are views showing an example of a container of cooling material and a connection structure of containers according to one embodiment. [Fig.8A] [Fig.8B] are views showing an example of a first grid according to one embodiment. [Fig.9] is a view showing an example of a first grid, a second grid and a third grid according to one embodiment. DETAILED DESCRIPTION OF THE EMBODIMENTS The present invention can be implemented in different forms and is not limited to the embodiments described here. Identical or similar elements are designated by identical references throughout the description. Well-known techniques will not be described in detail. In the drawings described below, the thicknesses are exaggerated in order to clearly represent several layers and regions. It should be noted that when an element such as a layer, film, region or substrate is designated as being "on" another element, it may be "directly on" another element or there may be have an intermediate element between them. Furthermore, when an element is designated as being "directly on" another element, there are no intermediate elements. Likewise, it should be noted that when an element such as a layer, a film, a region or a substrate is designated as being "under" another element, it can be located "directly under" another element or well there may be an intermediate element between them. Furthermore, when an element is designated as being “directly below” another element, there are no intermediate elements. A cooling device for a molten core material according to the embodiments is a device preventing the development of a serious accident, by dispersing and effectively cooling a molten core material, in the event of an accident. severe in which the core of a nuclear reactor melts and the molten core material escapes to the outside of the nuclear reactor. Figure IA is a view schematically illustrating a general loop type nuclear reactor system, and Figure IB is a view schematically showing a general integrated nuclear reactor system. With reference to FIGS. 1A and 1B, a nuclear reactor system 10 comprises a reactor vessel 110 comprising a core 112, pressurizers 22 and 32, steam lines 23 and 33, steam generators 24 and 34, supply water pipes 25 and 35, circulation pumps for heat transfer material 26 and 36, and similar devices. A schematic mode of operation of the nuclear reactor system 10 will be described below. First, an enormous amount of thermal energy is produced by the nuclear fission of the nuclear fuel from the core 112 located in the reactor vessel 110, and the thermal energy produced is transferred to the steam generators 24 and 34, by l intermediary of a heat transfer material (for example water) which is a heat exchange fluid circulated by the circulation pumps of heat transfer material 26 and 36. Next, the phase of the water in the generators steam 24 and 34 is changed so that high temperature, high pressure steam is produced. A turbine (not shown) is rotated by the high temperature and high pressure steam produced which is supplied to the turbine (not shown) by the steam lines 23 and 33, and a generator (not shown) connected to the turbine (not shown) rotates at the same time, so that electricity can be produced. The vapor from which energy is lost due to the rotation of the turbine (not shown) undergoes the phase change and test converted into water. The water is again brought to the steam generators 24 and 34 by the supply water lines 25 and 35. The pressurizers 22 and 32 can release the pressure of the system. In a nuclear reactor system 10 of this type, when, for example, the reactor vessel 110 is damaged or the cooling breaks down, the circulation of the heat transfer material does not take place and so on, and a a serious accident can occur, during which the reactor vessel 110 begins to melt under the effect of the heat produced in the heart 112, and there can be deterioration. Figures 2A to 2C are views which show the evolution of a melting accident at the heart of a nuclear reactor. Referring to Figures 2A to 2C, when the reactor vessel 110 containing the heart 112 is damaged, the heat transfer material contained in the reactor vessel 110 is transformed into vapor and can escape to a damaged part. Consequently, in the case where the excessive heat produced in the core 112 is not reduced and the temperature of the core 112 exceeds the melting point, the evolution of the melting of the core 112 can cause the material of the core 114 to melt. Since the temperature of the molten core material 114 is very high, the reactor vessel 110 may melt and the molten core material 114 may enter the bottom of the reactor vessel 110 and flow out of the tank 110. This type of accident is a very serious accident. A general nuclear reactor system 10 is provided with a safety system by which the reaction of the core 112 is stopped and the heat-transfer material is rapidly completed in order to lower the temperature of the core 112 before the molten core material 114 s escapes to the outside of the reactor vessel 110, but in some cases it may be difficult to prevent leakage of the molten core material 114. In the event of leakage of the molten core material 114, it is important to cool the this molten material 114 as quickly as possible. The cooling device for a molten core material according to the embodiments is a device for cooling the molten core material 114 as quickly as possible. Figure 3 is a view showing a cross section of a cooling device for a molten core material, according to an embodiment, and Figures 4A and 4B are views illustrating an operating mode of the device cooling for a molten core material according to Figure 3. On the other hand, Figure 5 is a view showing a cross section of a cooling device for a molten core material according to one embodiment. Figures 6A and 6B are views showing examples of a container of cooling material according to one embodiment, Figures 7A and 7B are views of an example of a container of cooling material and a structure of connection of containers according to one embodiment, FIGS. 8A and 8B are views illustrating an example of a first grid according to an embodiment, and FIG. 9 is a view illustrating an example of a first grid, of a second grid and a third grid of the cooling device for a molten core material according to one embodiment. A cooling device 100 for a molten core material comprises: two or more containers of cooling material 120 disposed under the reactor vessel 110, enclosing the core 112, and containing a cooling material; a first grid 130 disposed under the two or more containers of cooling material 120 and comprising two or more first through holes 132; and a second grid 140 arranged under the first grid 130 and comprising two or more second through holes 142. In addition, the cooling device 100 for a molten core material comprises a third grid 150 disposed under the second grid 140 and comprising two or more several third through holes 152. The case in which the cooling device 100 for a molten core material comprises three grids 130, 140 and 150 is illustrated in Figures 3 to 5 to facilitate explanations, but the cooling device 100 for a core material Fade according to the embodiments can include two or four or more grids. The cooling device 100 for a molten core material is basically included in a support structure for molten core material 160. This support structure for molten material 160 is immersed in a coolant tank 170 containing a liquid. cooler 172, and coolant 172 can be introduced into the molten material support structure 160, if necessary. The container of cooling material 120 has an outer wall 122 and contains a cooling material. The cooling material may include a cooling fluid 124 such as water or the like (see Figure 6A) and may include boron 126 and non-condensable gas 128 (see Figure 6B). On the other hand, although it is not shown, the cooling material may include the coolant 124 and the non-condensable gas 128. When the molten core material 114 escapes to the outside of the reactor vessel 110 and is in contact with the containers of cooling material 120, the cooling material expands and explodes, which has the effect that the molten core material 114 is ground and fragmented, so that fragments 116 of molten core material are formed. In the case where the cooling material comprises boron 126 and the non-condensable gas 128, the boron 126 prevents a chain reaction of the molten core material 114 comprising a nuclear material. The explosive force is increased by the non-condensable gas 128, so that the molten core material 114 can be efficiently ground and the fragments of the molten core material can be dispersed over a wide radius. Here, the non-condensable gas 126 may include nitrogen (N 2 ) or an inert gas, without being limited thereto. Even in the case where the cooling material comprises the cooling fluid 124 and the non-condensable gas 128, the explosive force is increased by the non-condensable gas 128, so that the molten core material 114 can be ground from efficient manner. The outer wall 122 of the container of cooling material 120 can comprise a metallic material, a non-metallic material or the like and can have different thicknesses and resistances in a range in which the container of cooling material can explode when the material of cooling contained in the container of cooling material 120 expands by thermal transfer. The cross section of the container of cooling material 120 can be oval or polygonal and can have different sizes. The coolant containers 120 can be installed randomly and can be arranged in a predefined form. For example, the container of cooling material 120 can have a spherical or cubic shape and can be arranged in a multilayer structure comprising at least two layers, without being limited to this configuration. The containers of cooling material 120 which are adjacent to each other can be connected together by structures for connecting containers 129. The containers of cooling material 120 which are arranged in the same layer and are adjacent to each other to the others can be linked together by the container connection structures 129 (see FIG. 7A). The containers of cooling material 120 which are arranged in different layers and are adjacent to each other can be interconnected by the container connecting structures 129 (see Figure 7B). The specific density of the molten core material 114 is much higher than that of the container of cooling material 120. Consequently, when the molten core material 114 leaks out of the reactor vessel 110 and is in contact with the containers of cooling material 120, the containers 120 may suddenly begin to float (move upwards). This can result in the escaping molten core material 114 not being effectively ground. The phenomenon where the containers of cooling material 120 suddenly begin to float can be reduced to a minimum by the container connection structures 129. As a result, the molten core material 114 which has escaped can be effectively fragmented. The container connection structure 129 may for example comprise the same material as the outer wall 122 of the container of cooling material 120, but not limited to, and may include different materials. On the other hand, if necessary, the container connection structure 129 can have different lengths, diameters or thicknesses. The fragments of molten core material 116 can be dispersed widely and uniformly over the first grid 130, the second grid 140, the third grid 150 and a lower surface of the support structure for molten core material 160 and can be cooled by the coolant 172 introduced from the coolant reservoir 170. The molten core material 114 can be agglomerated because of its weight and its viscosity. However, in the case where the cooling device 100 for a molten core material according to the embodiment is applied to the nuclear reactor system, the molten core material 114 is crushed by the containers of cooling material 120 and two or more grids 130, 140 and 150, and the fragments of molten core material 116 are widely dispersed, so as to minimize the phenomenon of agglomeration. Furthermore, as the molten core material 114 is ground, its surface area is increased. This increases the speed and cooling efficiency of the molten core material 114. In order to more widely disperse the fragments of molten core material 116 which have been fragmented by the containers of cooling material 120, two or more grids 130, 140 and 150 can be placed under the containers of cooling material 120. These grids 130, 140 and 150 respectively comprise two or more through holes 132, 142 and 152. These through holes 132, 142 and 152 can be designed so that the average size of each of the holes 132, 142 and 152 decreases in the direction going from top to bottom. For example, the first grid 130, the second grid 140 and the third grid 150 may be arranged one after the other under the containers of cooling material 120, in the direction from top to bottom. . The average size of two or more first through holes 132 may be greater than the average size of two or more second through holes 142, and the average size of two or more second through holes 142 may be greater than the average size of two or more third through holes 152. In the case where the size of the fragment of molten core material 116 becomes smaller than that of the first through hole 132 of the first grid 130, the fragment of molten core material 116 can pass through the second grid 140. On the other On the other hand, in the case where the size of the fragment of molten core material 116 becomes greater than that of the second through hole 142 of the second grid 140, the fragment of molten core material 116 can be placed on the second grid 140. Furthermore , in the case where the size of the fragment of molten core material 116 becomes smaller than that of the second through hole 142 of the second grid 140, the fragment of molten core material 116 can pass through the second through hole 142. Similarly, after passing through the second through hole 142, the fragments of molten core material 116 can pass through the third through hole 152 of the third grid 150, or b ien they may not cross it (see Figure 4A). Consequently, the average size of the fragments of molten core material 116 arranged on the first grid 130 can be greater than the average size of the fragments of molten core material 116 disposed on the second grid 140. The average size of the fragments of molten material molten core 116 arranged on the second grid 140 may be greater than that of the fragments of molten core material 116 disposed on the third grid 150. To summarize, the fragments of molten core material 116 crushed by the explosion of the containers cooling material 120 may be disposed on the first grid 130, on the second grid 140, on the third grid 150 and on an inner surface of the support structure of molten core material 160. Therefore, the molten core material 114 is separated into fragments of molten core material 116. These fragments 116 can be widely dispersed by the first grid 130, the second grid 140 and the third grid 150. Thus, since the contact area between the fragments of molten core material 116 and the coolant 172 becomes large as the coolant 172 is brought to the supporting structure of molten core material 160, through a coolant introduction passage 162, the speed and cooling efficiency of the molten core material 114 is further increased. The support structure of molten core material 160 is disposed under the third grid 150, and may comprise two or more passages for introducing coolant 162 into which the coolant 172 is introduced from the liquid reservoir. cooling 170. The maximum size of the first through hole 132 can be less than the minimum size of the container of cooling material 120. Therefore, the container of cooling material 120 can be arranged stably on the first grid. For example, the maximum size of the first through hole 132 may be less than about 10 cm. Two or more first through holes 132 may be the same size, two or more second through holes 142 may be the same size, and two or more third through holes 152 may be the same size (see Figure 8A). The first through hole 132, the second through hole 142 and the third through hole 152 may have different sizes. For example, any first through holes 132 among two or more first through holes 132 may have different sizes, any second through holes 142 from among two or more second through holes 142 may have different sizes, and any third through hole 152 of two or more third through holes 152 may have different sizes. In another example, the size of the first through hole 132 can be increased from the center of the first grid 130, towards the outside of the first grid 130 (see Figure 8B), the size of the second through hole 142 can be increased from the center of the second grid 140, toward the outside of the second grid 140, and the size of the third through hole 152 can be increased from the center of the third grid 150, by direction of the external part of the third grid 150. In FIG. 8B, only the first grid 130 is shown to facilitate the description, but the second through hole 142 and the third through hole 152 can have different sizes. For example, since a large relatively massive particle tends to move over a greater distance due to its mass of inertia, the sizes of the through holes 132, 142 and 152 of the grids 130, 140 and 150 can be gradually increased from the center of the grids 130, 140 and 150, respectively towards the outer part of the grids 130, 140 and 150, when the molten core material 114 is crushed by the expansion and explosion of the container of cooling material 120. In this way, the fragments of molten core material 116 can be dispersed widely and uniformly. The first through hole 132, the second through hole 142 and the third through hole 152 may have cross sections of different shapes. For example, the cross section of the first through hole 132, the cross section of the second through hole 142 and the cross section of the third through hole 152 may be designed respectively with a polygonal shape or an oval shape. Each of the first 130, second 140 and third 150 grids of the cooling device 100 for a molten core material can be parallel to a horizontal plane, or at least part of the first grid 130, of the second grid 140 and of the third grid 150 may have a shape inclined relative to the horizontal plane. Figures 3 to 4B illustrate the case where the cooling device 100 for a molten core material has grids 130, 140 and 150 which are parallel to the horizontal plane. FIG. 5 represents the case where the grids 130, 140 and 150 of the cooling device 100 for a molten core material each have an inclined shape (in the shape of a mountain). However, the cooling device 100 for a molten core material is not limited to the shape shown and can have any shape, insofar as it makes it possible to disperse the molten core material appropriately 114. Here , the horizontal plane designates a plane parallel to a first direction in FIGS. 3 and 5. The case in which the first grid 130, the second grid 140 and the third grid 150 all have the same inclination is shown in Figure 5. However, it is also possible to predict the case where the first grid 130 is parallel in the horizontal plane and the second grid 140 and the third grid 150 are inclined relative to the horizontal plane, just as it is possible to provide that only a part of the grids 130, 140 and 150 is inclined relative to the horizontal plane. The size or total area of the first grid 130, the size or total area of the second grid 140 and the size or total area of the third grid 150 may be different from each other. For example, the area of a cross section (cross section perpendicular to a second direction of Figures 3 and 5) of the second grid 140 located in front of the reactor vessel 110 may be greater than the area of a cross section (cross section perpendicular to the second direction of Figures 3 and 5) of the first grid 130 located opposite the reactor vessel 110. The area of a cross section (cross section perpendicular to the second direction of the Figures 3 and 5) of the third grid 150 located opposite the reactor vessel 110 may be greater than the area of the cross section (cross section perpendicular to the second direction of Figures 3 and 5) of the second grid 140 located in face of the reactor vessel 110. In this case, since the grids 130, 140 and 150 are arranged one after the other in increasing order of size or area, the fragments of molten core material 116 can be dispersed more stably as they move down. Referring to Figure 9, the first grid 130 may further include a first lateral surface grid 134, disposed on at least one side thereof, and a first hole emerging from the lateral surface 136. On the other hand, the second grid 140 may further comprise a second grid of lateral surface 144, disposed on at least one side thereof, and a second hole emerging from the lateral surface 146. And finally, the third grid 150 may further comprise a third lateral surface grid 154, disposed on at least one side of the latter, and a third through hole of lateral surface 156. For example, the first lateral surface grids 134 can be arranged on all the parts of the edges of the first grid 130, the second lateral surface grids 144 can be arranged on all the parts of the edges of the second grid 140, and the third lateral surface grids 154 can be arranged on all the parts of the edges of the third grid 150. In this case, the first grid 130, the second grid 140 and the third grid 150 can have the overall shape d 'a basket. When the grids of lateral surfaces 134, 144 and 154 exist, the fragments of molten core material 116 can be arranged on these grids 134, 144 and 154, and therefore the fragments of molten core material 116 can be dispersed more widely and the contact area between the fragments 116 and the coolant 172 can be further increased. As a result, the cooling rate and the cooling efficiency of the molten core material 114 can be further increased. Even when the grids of lateral surfaces 134, 144 and 154 are provided, as shown in FIG. 9, the total size of the second grid 140 may be greater than that of the first grid 130, and the total size of the third grid 150 may be greater than that of the second grid 140. The first grid 130, the second grid 140 and the third grid 150 may comprise a metallic material or an alloy material having a melting temperature greater than approximately 2000 ° C., which is the melting temperature of the core 112. For example, the first grid 130, the second grid 140 and the third grid 150 can comprise a material based on tungsten. The cooling device 100 for a molten core material according to the embodiment comprising the container of cooling material 120 and two or more grids 130, 140 and 150 can be used in the existing installation of a nuclear reactor . Therefore, it is possible to save costs and space, without the need for additional safety measures in terms of space, and to prepare for a serious accident with leaks from the molten core material, simply using the cooling device for molten core material in the existing installation of a nuclear reactor. Although the present invention has been described in relation to exemplary embodiments which are currently considered to be practicable, it should be noted that the invention is not limited to the embodiments exposed. <Description of some symbols> 10: Nuclear reactor system 22, 32: Pressurizer [0082] 23, 33: Steam line [0083] 24, 34: Steam generator [0084] 25, 35: Water line supply 26, 36: Cooling material circulation pump [0086] 110 [0087] 112 [0088] 114 [0089] 120 [0090] 122 [0091] 124 [0092] 126 [0093] 128 [0094] 130 [0095] 132 [0096] 140 [0097] 142 [0098] 150 [0099] 152 [0100] 160 [0101] 162 [0102] 170 [0103] 172 Reactor vessel Heart Molten core material Cooling material container Outer wall Coolant Boron Non-condensable gas First grid First through hole Second grid Second through hole Third grid Third through hole Support structure of molten core material Coolant introduction passage Coolant tank Cooling liquid
权利要求:
Claims (1) [1" id="c-fr-0001] Claims [Claim 1] Cooling device (100) for a molten core material (114), comprising:two or more containers of cooling material (120) disposed under a reactor vessel (110), having a nuclear reactor core (112), and having cooling material; a first grid (130) disposed under the two or more containers for cooling material (120) and comprising two or more first through holes (132); anda second grid (140) disposed under the first grid (130) and comprising two or more second through holes (142), in whichthe average size of the two or more first through holes (132) being greater than the average size of the two or more second through holes (142). [Claim 2] The cooling device (100) of claim 1, further comprising:a third grid (105) disposed under the second grid (140) and comprising two or more third through holes (152), the average size of the two or more second through holes (142) being greater than the average size of the two or more third holes through holes (152). [Claim 3] Cooling device (100) according to claim 2, in which:any two first through holes of the two or more first through holes (132) have different sizes, any second two holes from the two or more second through holes (142) have different sizes, or any two third through holes from the two or several third through holes (152) have different sizes. [Claim 4] Cooling device (100) according to claim 3, in which:the size of the first through holes (132) is increased from the center of the first grid (130) towards an outer portion of the first grid (130), the size of the second through holes (142) is increased from from the center of the second grid (140) towards of an outer part of the second grid (140), or the size of the third through holes (152) is increased from the center of the third grid (150) towards an external part of the third grid (150) . [Claim 5] Cooling device (100) according to claim 3, in which:the maximum size of the first through hole (132) is less than a minimum size of the container of cooling material (120). [Claim 6] Cooling device (100) according to claim 5, in which:the maximum size of the first through hole (132) is less than 10 [Claim 7] cm.Cooling device (100) according to claim 2, in which:each of a cross section of the first through hole (132), a cross section of the second through hole (142) and a cross section of the third through hole (152) have a polygonal or an oval shape. [Claim 8] Cooling device (100) according to claim 2, in which:the area of a cross section of the second grid (140) located in front of the reactor vessel (110) is greater than the area of a cross section of the first grid (130) located in front of the reactor vessel (110), and the area of a cross section of the third grid (150) located opposite the reactor vessel (110) is greater than the area of a cross section of the second grid (140) located opposite of the reactor vessel (110). [Claim 9] Cooling device (100) according to claim 2, in which:each of the grids among the first grid (130), the second grid (140) and the third grid (150) is parallel to a horizontal plane, or at least part of the first grid (130), of the second grid (140 ) and the third grid (150) is inclined relative to the horizontal plane. [Claim 10] Cooling device (100) according to claim 2, in which:the first grid (130) further comprises a first lateral surface grid (134), disposed on at least one side thereof, and a first side surface through hole (136) disposed in the first side surface grid (134), the second grid (140) further comprises a second side surface grid (144), disposed on at least one side thereof, and a second side surface through hole (146) disposed in the second lateral surface grid (144), and the third grid (150) further comprises a third lateral surface grid (154), disposed on at least one side thereof, and a third surface through hole lateral (156) disposed in the third lateral surface grid (154). [Claim 11] Cooling device (100) according to claim 1, further comprising: a container connecting structure (129) which connects the two or more containers of cooling material (120) adjacent to each other. [Claim 12] Cooling device (100) according to claim 2, further comprising: a support structure of molten core material (160), disposed under the third grid (150) and comprising two or more coolant introduction passages (162) into which a coolant (172) is introduced from a coolant tank (170).
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同族专利:
公开号 | 公开日 CN110875097A|2020-03-10| JP6664021B2|2020-03-13| US10991469B2|2021-04-27| KR102216695B1|2021-02-18| JP2020038186A|2020-03-12| US20200075183A1|2020-03-05| KR20200027128A|2020-03-12|
引用文献:
公开号 | 申请日 | 公开日 | 申请人 | 专利标题 US4116764A|1976-02-11|1978-09-26|The United States Of America As Represented By The United States Department Of Energy|Apparatus for controlling nuclear core debris| US4130459A|1976-03-29|1978-12-19|Westinghouse Electric Corp.|Poison and diluent system for nuclear power plants| USH91H|1983-03-04|1986-07-01|The United States Of America As Represented By The United States Department Of Energy|Safety apparatus for nuclear reactor to prevent structural damage from overheating by core debris| IT1228999B|1989-04-13|1991-07-12|Ente Naz Energia Elettrica|PROTECTION SYSTEM OF THE REACTOR CONTAINMENT BUILDING IN NUCLEAR POWER STATIONS.| US5384814A|1993-04-12|1995-01-24|General Electric Company|Lower tie plate strainers for boiling water reactors| EP0730776B1|1993-11-23|1998-05-20|Siemens Aktiengesellschaft|Device for retaining a core melt-through inside the spreading chamber of a nuclear reactor installation| JPH0843576A|1994-07-27|1996-02-16|Toshiba Corp|Reactor core catcher| FR2763168B1|1997-05-06|1999-11-05|Commissariat Energie Atomique|NUCLEAR WATER REACTOR, OF WHICH THE TANK CONTAINS A DEVICE FOR RECOVERING THE HEART AFTER ITS ACCIDENTAL FUSION| FR2784785B1|1998-10-14|2000-12-01|Commissariat Energie Atomique|NUCLEAR WATER REACTOR HAVING A RECEPTACLE CONTAINING DEFORMABLE INTERNAL STRUCTURES| FR2784784B1|1998-10-14|2000-12-01|Commissariat Energie Atomique|NUCLEAR WATER REACTOR WITH INTEGRATED RECEPTACLE| KR100546317B1|2003-02-21|2006-01-26|삼성전자주식회사|Method for detecting optical disc| US20070138072A1|2005-11-02|2007-06-21|Continuum Dynamics, Inc.|Trash rack for nuclear power plant| JP2009052951A|2007-08-24|2009-03-12|Toshiba Corp|Core melt cooling device and reactor container| JP2012247216A|2011-05-25|2012-12-13|Toshiba Corp|Corium holding apparatus| JP6011327B2|2012-12-27|2016-10-19|新日鐵住金株式会社|Vibrating sieve device and cleaning method thereof| JP2014190869A|2013-03-27|2014-10-06|Mitsubishi Heavy Ind Ltd|Dispersion acceleration device for fused materials, and reactor containment vessel| KR101546317B1|2014-06-11|2015-08-25|한국원자력연구원|Water ball to make the molten core porous| KR101606872B1|2014-07-04|2016-03-28|주식회사 아리텍|Porous cooling block and cooling apparatus of corium having the same and the cooling method using it| RU2576516C1|2014-12-16|2016-03-10|Акционерное Общество "Атомэнергопроект"|System of localisation and cooling of melt of active zone of pressurised water reactor| JP2017187370A|2016-04-05|2017-10-12|株式会社東芝|Nuclear reactor containment and molten reactor core receiving device| KR101752215B1|2016-09-28|2017-06-29|포항공과대학교 산학협력단|Melted core catcher for fragmentation.|DE102019126049B3|2019-09-26|2020-11-19|Framatome Gmbh|System for stabilizing a core meltdown in a nuclear power plant| RU2736544C1|2020-03-20|2020-11-18|Акционерное Общество "Атомэнергопроект"|Nuclear reactor core melt localization and cooling system|
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申请号 | 申请日 | 专利标题 KR1020180104724A|KR102216695B1|2018-09-03|2018-09-03|Cooling apparatus for molten core| KR10-2018-0104724|2018-09-03| 相关专利
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