JP2008241657A - Primary containment vessel - Google Patents

Abstract

In the unlikely event that a core melt flows out of a reactor pressure vessel, an excessive temperature rise of the reactor containment vessel is prevented over a long period of time, and an active reaction due to the core melt is prevented.
A reactor pressure vessel 2 is supported by a substantially cylindrical pressure vessel support pedestal 3, and includes a lower dry well 5 and a hopper 9 below, and accommodates a core 4 therein. In the unlikely event that a severe accident occurs in which the core 4 melts out of the reactor pressure vessel 2 and flows out, the hopper 9 receives and guides the core melt so that it does not scatter. A core catcher 10 for holding the core melt falling from the hopper 9 is provided on the floor surface of the lower dry well 5. A cooling water passage is provided that circulates and supplies the water of the pressure suppression pool 7 to the gap between the side wall surface and floor surface of the lower dry well 5 and the side surface and bottom surface of the core catcher 10.
[Selection] Figure 1

Description

  The present invention is a reactor containment vessel of a nuclear power plant, and in particular, even if the core melt flows out of the reactor pressure vessel, the increase in temperature and internal pressure is suppressed to ensure safety. Related to the containment vessel.

  In future reactors, safety measures tend to be required even for virtual severe events that exceed design standards. As an example of such a virtual severe event, it is assumed that the core in the reactor pressure vessel melts and flows out of the pressure vessel.

  Known techniques for such a virtual accident include the following.

  Patent Document 1 installs a device (a saucer) for holding a melted core below a pressure vessel in a reactor containment vessel in the event of a core melting accident that is a hypothetical severe event, and this core holding device is used as a lower dry well. The core melt is indirectly cooled by immersing the water in the pressure suppression pool in the cooling water that has been stored therein.

  In Patent Document 2, a melting core holding means is installed in a lower dry well, and pressure suppression pool water is supplied from both above the held core melt and under the core holding means to cool the core melt.

  In Patent Document 3, a thick plate glass in which a heat pipe is embedded in the floor of the lower dry well is installed, the active metal in the core melt is stabilized by melting the core melt into the glass, and the pressure-suppressed pool water is heated. Supply to the condensing part of the pipe to cool the core melt.

  In Patent Document 4, a core melt recovery cooling device is immersed in pool water stored on the floor surface of the lower dry well to recover and cool the core melt. In order to effectively perform the recovery cooling, a recovery wall constituting the recovery cooling device is formed in a bellows shape.

In Patent Document 5, a conical structure or an inclined flat plate structure is installed at the lower part of a nuclear reactor, and the core melt is temporarily received by the conical structure or the inclined flat plate structure to make small droplets. By dropping into the pool water below it, the effect of suppressing the steam explosion generated by the contact between the pool water and the core melt is expected.
JP 59-196498 A JP-A-6-130169 JP 2001-166081 A Japanese Patent Laid-Open No. 5-134076 Japanese Patent Laid-Open No. 7-244186

  The known technique described above has the following problems.

  In Patent Document 1, since water of approximately the same water level as the pressure suppression pool water is stored in the lower dry well even in a normal state, a large amount of water must be drained during periodic inspections, resulting in poor maintainability. To do.

  In Patent Document 2, the cooling rate is increased by direct water injection from above the core melt held in the holding means and water injection from the lower side of the holding means. The direct injection of water into the reactor is also used, and the internal pressure of the reactor containment vessel may increase due to the generation of a large amount of water vapor and non-condensable gas such as hydrogen gas generated by the reaction between water and the core melt.

  Patent Document 3 is characterized in that the core melt can be dissolved in a glass body to convert the active metal into a stable oxide and suppress the generation of hydrogen gas. However, since thick glass is used, Is difficult to handle and may lead to an increase in construction work time.

  In Patent Document 4, since the core melt is cooled by being brought into direct contact with the pool water, a large amount of water vapor may be generated.

  In Patent Document 5, the core melt is separated into small spheres and cooled with a conical structure in order to suppress the steam explosion, but a large amount of the core melt falls in a short time. In such a case, the effect may be diminished, and there may be a risk of direct contact with the pool water and generation of a large amount of water vapor or direct contact with the floor surface.

  The reactor containment vessel is the last barrier to contain radioactive materials, and it is necessary to maintain its integrity semi-permanently even if a core melting accident occurs. The present invention has been made to solve the above-described problems.

  An object of the present invention is to provide a reactor containment vessel that can prevent the core melt from coming into direct contact with the reactor containment vessel and prevent an excessive temperature rise of the reactor containment vessel over a long period of time. And

  Another object of the present invention is to provide a reactor containment vessel that can prevent an active reaction due to a core melt.

  In order to solve the above problems, in the present invention, a reactor pressure vessel, a pressure vessel support pedestal provided with the reactor pressure vessel, a core accommodated in the reactor pressure vessel, and a reactor pressure vessel A lower dry well provided below, a pressure suppression chamber provided around the pressure vessel support pedestal, a pressure suppression pool in which water is stored in the pressure control chamber, and provided around the reactor pressure vessel A reactor containment vessel provided with an upper dry well, a hopper installed below the reactor pressure vessel, receiving and guiding the core melt from the core so that it does not scatter, and the lower dry well A core catcher for holding the core melt, provided on the floor of the well, and a gap between a side wall and a floor of the lower dry well and a side and a bottom of the core catcher And configured cooling water passage gap, provides a reactor containment vessel, characterized in that a cooling water passage for supplying water in the pressure suppression pool to the cooling water flow path clearance.

  According to the present invention, in the unlikely event that the core melt flows out of the reactor pressure vessel, the outflow core melt is prevented from coming into direct contact with the reactor containment vessel, and the core melt Reactor containment that prevents generation of non-condensable gases such as water vapor and hydrogen gas due to water, prevents an increase in the internal pressure of the containment vessel, and prevents excessive temperature rise of the containment vessel due to core melt over a long period of time The purpose is to provide a container.

  Hereinafter, embodiments of a containment vessel according to the present invention will be described with reference to the drawings.

[First Embodiment]
A first embodiment of a nuclear reactor containment vessel according to the present invention will be described with reference to FIGS. 1 to 5.

  As shown in FIG. 1, the reactor containment vessel 1 of this embodiment stores a reactor pressure vessel 2, and the reactor pressure vessel 2 is supported by a substantially cylindrical pressure vessel support pedestal 3. The reactor containment vessel 1 has a pressure vessel support pedestal 3 inside, and a lower dry well 5 below the reactor pressure vessel 2. A pressure suppression chamber 6 is provided around the pressure vessel support pedestal 3. This pressure suppression chamber 6 has a pressure suppression pool 7 in which water is stored at the bottom, and is stored as cooling water. Further, an upper dry well 8 is provided around the reactor pressure vessel 3 above the pressure suppression chamber 6.

  Here, as shown in FIG. 1, the reactor containment vessel 1 includes a hopper 9 below the reactor pressure vessel 2. The reactor pressure vessel 2 accommodates the core 4 inside, but if a severe accident occurs when the core 4 melts out of the reactor pressure vessel 2 and flows out, the hopper 9 Take it so that it won't scatter and guide you down. Further, a core catcher 10 for holding the core melt falling from the hopper 9 is provided on the floor surface of the lower dry well 5. The core catcher 10 has a volume that can accommodate the estimated total amount of core melt. The core catcher 10 is installed on the floor surface of the lower dry well 5 via a support member (not shown) for supporting a load including the core melt. The hopper 9 includes a cylindrical portion 9 a that receives the core melt so that it does not scatter, an inclined portion 9 b that collects the core melt, and a dropping port 9 c that introduces the core melt into the core catcher 10.

  As shown in FIG. 2, the hopper 9 has a high melting point material 9A such as tungsten in order from the inside that becomes high temperature when receiving the core melt, and a low thermal conductive material 9B such as alumina or zirconia or magnesium oxide, For example, a highly ductile material 9C such as stainless steel or carbon steel is laminated to form a multilayer structure.

  On the other hand, as shown in FIG. 3, the core catcher 10 includes a high melting point material 10A such as tungsten, a low thermal conductive material 10B such as alumina or zirconia or magnesium oxide, and a high melting material such as stainless steel or carbon steel. The ductile material 10C is laminated to form a multilayer structure.

  Further, the gap between the side wall surface and floor surface of the lower dry well 5 and the side surface and bottom surface of the core catcher 10 constitutes a cooling water passage gap for circulating the water of the pressure suppression pool 7 as cooling water. A cooling water passage that circulates and supplies the water of the pressure suppression pool 7 is provided in the cooling water passage gap. When the core melt is held by the core catcher 10, the heat of the core melt is transferred to the water in the pressure suppression pool 7 filled in the cooling water flow path gap, and the core melt is cooled.

  As shown in FIG. 4, this cooling water channel gap communicates with the cooling water channel gap 11 </ b> A configured by a gap between the floor surface of the lower dry well 5 and the bottom surface of the core catcher 10, and this cooling water channel gap 11 </ b> A. The cooling water passage gap 11B is formed by a gap between the side wall surface of the lower dry well 5 and the side surface of the core catcher 10, and the sealing portion 11C is used to seal the upper portion of the cooling water passage gap 11B. The cooling water channel includes a communication pipe 12 that connects the bottom of the cooling water channel gap 11A and the low position of the pressure suppression pool 7, and the top of the cooling water channel gap 11B and the high position of the pressure suppression pool 7. The communication pipe 13 is connected.

  FIG. 5 shows the configuration of another cooling water passage gap and the cooling water passage.

  As shown in FIG. 5, this cooling water channel gap is constituted by a gap between the floor surface of the lower dry well 5 and the bottom surface of the core catcher 10, and is constituted by a cooling water channel gap 111 </ b> A that seals the outer periphery. The cooling water channel includes a communication pipe 12 that connects the center bottom of the cooling water channel gap 111A and a low position of the pressure suppression pool 7, and an outer peripheral part of the cooling water channel gap 111A and a high position of the pressure suppression pool 7. The communication pipe 113 is connected.

  Furthermore, the structure of another cooling water flow path gap and a cooling water path is shown in FIG. 6 and FIG.

  As shown in FIG. 6, in the embodiment of FIG. 4, the shape of the bottom lower surface of the core catcher 10 is a reverse cone shape such as an inverted conical shape or an inverted polygonal pyramid shape, and the cooling water flow path is shaped along the bottom lower surface. A gap 211A is formed.

  As shown in FIG. 7, in the embodiment of FIG. 5, the shape of the bottom lower surface of the core catcher 10 is a reverse cone shape such as an inverted conical shape or an inverted polygonal pyramid shape, and the cooling water flow path has a shape along the bottom lower surface. A gap 311A is formed.

  In the case of this embodiment configured as described above, if a severe accident occurs such that the core 4 melts and flows out through the lower part of the reactor pressure vessel 2, a reactor pressure vessel 2 is generated. Even if the core melt flows out at a location that cannot be specified at the lower portion of the core, the core melt that has flowed out is temporarily received by the hopper 9 without being scattered. Next, the core melt flows down the inclined surface of the hopper 9 and is guided to the dropping port 9c. Further, the core melt is guided to the core catcher 10 from the dropping port 9c. Thereby, the installation area | region of the core catcher 10 can be reduced and limited.

  The hopper 9 uses a high ductility material 9C such as stainless steel or carbon steel as a strength member, and is fixed to the pedestal 4 to support a load due to the core melt and its own weight. Further, the inner surface of the hopper 9 that contacts the core melt has a high-melting-point material 9A such as tungsten as a heat-resistant member, and a low-heat conductive material 9B such as alumina, zirconia, or magnesium oxide as a heat-insulating member. Even if a high-temperature core melt of 2000 ° C. or higher comes into contact, the temperature rise of the strength member can be suppressed and the soundness can be maintained.

  The core catcher 10 prevents the high temperature core melt from coming into direct contact with the side wall surface or floor surface of the lower dry well 5 constituting the reactor containment vessel 1, holds it for a long period of time, and keeps atoms from being heated by the core melt. It is provided to prevent damage to the reactor containment vessel 1.

  Therefore, the core catcher 10 uses a high ductility material 10C such as stainless steel or carbon steel as a strength member, and is provided on the floor surface of the lower dry well 5 to support the entire load due to the core melt and its own weight. Further, the inner surface where the core catcher 10 is in contact with the core melt is made of a high melting point material 10A such as tungsten as a heat-resistant member, and the soundness can be maintained even when the surface directly in contact with the core melt reaches 2000 ° C. or higher. . Furthermore, since the low heat conductive material 10B such as alumina, zirconia, or magnesium oxide is used as the heat insulating member, the thermal resistance is increased, and the temperature rise of the strength member made of the high ductility material 10C can be suppressed to maintain the soundness. Furthermore, since the thermal resistance is increased, there is an advantage that the heat passage rate from the core melt to the cooling water passage gap via the core catcher 10 is reduced. In order to keep the temperature of the floor surface of the lower dry well 4 and the side wall surface in the vicinity thereof by the heat of the core melt held by the core catcher 10, the water in the pressure suppression pool 7 is cooled by the connecting pipes 12 and 13. The water channel gaps 11A and 11B are injected. The water in the pressure suppression pool 7 does not leak to the lower dry well 5 side by the sealed portion 11C, and generation of non-condensable gases such as water vapor and hydrogen gas can be prevented. Once the core melt is held by the core catcher 10, the heat of the core melt is transferred to the water in the pressure suppression pool 7 filled in the cooling water flow path gaps 11A and 11B, and the temperature of the water in the pressure suppression pool 7 is To rise. Further, when the temperature of the water in the pressure suppression pool 7 rises, the water in the pressure suppression pool 7 begins to boil. The water in the pressure suppression pool 7 that has become lighter as the temperature rises flows into the pressure suppression pool 7 through the communication pipe 13 from the cooling water passage gap 11B. Further, the water in the pressure suppression pool 7 is injected into the cooling water passage gap 11 </ b> A through the communication pipe 12 due to a water head difference. In this way, the water in the pressure suppression pool 7 continues to circulate naturally through the cooling water passage gaps 11A and 11B, so that the floor surface and side wall surface of the lower dry well 5 and the bottom surface and side surface of the core catcher 10 are cooled, and the core The melt can be cooled.

  Similarly, in the case of the configuration of the cooling water channel gap and the cooling water channel shown in FIG. 5, the water in the pressure suppression pool 7 flows from the cooling water channel gap 111A to the communication pipe 113, the pressure suppression pool 7, the communication pipe 12, and the cooling water flow. It can be naturally circulated and cooled to the road gap 111A.

  In the case of the cooling water passage gap and the cooling water passage shown in FIGS. 6 and 7, the downstream side of the cooling water passage gaps 211 </ b> A and 311 </ b> A is inclined higher than the lowermost portion of the bottom of the core catcher 10. Therefore, the water in the pressure suppression pool 7 that has become lighter by heating can easily circulate between the cooling water passage gap and the cooling water passage, thereby preventing local stagnation of the cooling water passage gaps 211A and 311A and preventing local overheating.

  According to this embodiment, even if a severe accident that the core 4 melts and flows out through the lower part of the reactor pressure vessel 3 occurs, the core melt is not scattered by the hopper 9. The core melter can be safely guided to the core catcher 10 and can hold the core melt without directly contacting the floor surface and the side wall surface of the lower dry well 5, so that the core melt erodes the reactor containment vessel. Thus, the generation of gas and the increase of the internal pressure of the reactor containment vessel can be suppressed. Furthermore, the core catcher 10 has a heat-resistant structure and a heat-insulating structure, so that the soundness is maintained even when a high-temperature core melt is held, and the floor surface of the lower dry well 5 and Since the side wall surface, the bottom and side surfaces of the core catcher 10 and the core melt are cooled, a sound and intrinsically safe reactor containment vessel 1 that does not generate non-condensable gases such as water vapor and hydrogen gas can be provided.

[Second Embodiment]
A second embodiment of the reactor containment vessel according to the present invention will be described with reference to FIG.

  In the present embodiment, the same components as those in the first embodiment are denoted by the same reference numerals, and redundant description is omitted.

  In this embodiment, in addition to the configuration described in the first embodiment, a glass body 14 formed in a pellet shape as shown in FIG. 8 is laid inside the core catcher 10.

  In the present embodiment configured as described above, when the core melt is held in the core catcher 10, the core melt melts the pellet-like glass body 14 and the active metal such as zirconium in the core melt is It becomes an oxide and is dissolved and stabilized in the glass melt. Thereby, it is possible to suppress the generation of non-condensable gas such as hydrogen gas by reacting with water vapor, and it is possible to suppress the pressure increase in the reactor containment vessel. Generally, a glass body can dissolve an oxide with an oxide mixture. Such an action is described in, for example, the above-mentioned Patent Document 3 disclosed as a publicly known technique relating to cooling of the core catcher by a heat pipe, but in this known example, a slab glass body is used as a configuration example. There is a problem that a great deal of labor is required at the time of installation.

  According to the present embodiment, active metal such as zirconium in the core melt can be dissolved as a stable oxide in the glass body of the pellet-shaped glass body 14, so that safety is improved and the pellet-shaped glass body 14 By using the glass body 14, the handling is easy and the laying operation can be easily performed, so that the construction time of the reactor containment vessel 1 can be shortened.

[Third Embodiment]
A third embodiment of a reactor containment vessel according to the present invention will be described with reference to FIG.

  In the present embodiment, the same components as those in the first embodiment are denoted by the same reference numerals, and redundant description is omitted.

  In the present embodiment, in addition to the configuration of the second embodiment, the core catcher 10 is prepared by mixing a neutron absorber 15 such as boron formed into a pellet shape and a pellet-shaped glass body 14 as shown in FIG. Constructed by laying inside.

  According to the present embodiment configured as described above, if the core melt is held in the core catcher 10, it is possible to suppress a rapid nuclear fission reaction. A container 1 can be provided.

[Fourth Embodiment]
A fourth embodiment of a reactor containment vessel according to the present invention will be described with reference to FIG.

  In the present embodiment, the same components as those in the first to third embodiments are denoted by the same reference numerals, and redundant description is omitted.

  In this embodiment, a heat exchanger 16 is provided in the pressure suppression pool 7 in order to cool the water in the pressure suppression pool 7 of the first to third embodiments. The heat exchanger 16 is a tube type, and a coolant such as water circulates therein. A circulation pump 17 and a cooling device 18 are provided outside the reactor containment vessel.

  In the first to third embodiments, while cooling the core melt, the floor surface and side wall surface of the lower dry well 5, and the bottom surface and side surface of the core catcher 10, the water temperature of the pressure suppression pool 7 rises to increase the cooling efficiency. May fall. According to this embodiment, it is possible to provide the reactor containment vessel 1 that can prevent the rise of the water temperature of the pressure suppression pool 7 by heat exchange by the heat exchanger 16 and can stably cool the core melt.

[Fifth Embodiment]
A fifth embodiment of a reactor containment vessel according to the present invention will be described with reference to FIG.

  In the present embodiment, the same components as those in the first to third embodiments are denoted by the same reference numerals, and redundant description is omitted.

  In the present embodiment, a heat pipe 19 is provided in the pressure suppression pool 7 in order to cool the water in the pressure suppression pool 7 of the first to third embodiments. The condensation cooling section 20 of the heat pipe 19 is provided outside the reactor containment vessel. Since the refrigerant naturally circulates due to the vaporization and condensation action of the refrigerant in the heat pipe 19, a circulation pump is not necessary and can be simplified as compared with the fourth embodiment.

[Sixth Embodiment]
A sixth embodiment of a reactor containment vessel according to the present invention will be described with reference to FIG.

  In the present embodiment, the same components as those in the first to third embodiments are denoted by the same reference numerals, and redundant description is omitted.

  In this embodiment, a heat pipe 19 is provided in the pressure suppression pool 7 and a condensation cooling unit 20 is provided in the upper dry well 8 in order to cool the water in the pressure suppression pool 7 of the first to third embodiments. Is. The upper dry well 8 is cooled by, for example, an upper dry well cooling unit described in a known reactor containment vessel (Japanese Patent Laid-Open No. 2001-83275). This eliminates the need for a dedicated cooling device, which can be simplified.

  Furthermore, the present invention is not limited to the above-described embodiments, and various modifications can be made without departing from the spirit of the present invention by combining the configurations of the embodiments.

BRIEF DESCRIPTION OF THE DRAWINGS Basic explanatory drawing which shows 1st Embodiment of the reactor containment vessel concerning this invention. The structure explanatory drawing of the hopper with which the nuclear reactor containment vessel shown in 1st Embodiment of this invention was equipped. Structure explanatory drawing of the core catcher with which the nuclear reactor containment vessel shown in 1st Embodiment of this invention was equipped. The fragmentary sectional view of a nuclear reactor containment vessel by other embodiment explanatory drawing with which 1st Embodiment of this invention was equipped. The fragmentary sectional view of a nuclear reactor containment vessel by other embodiment explanatory drawing with which 1st Embodiment of this invention was equipped. The fragmentary sectional view of a nuclear reactor containment vessel by other embodiment explanatory drawing with which 1st Embodiment of this invention was equipped. The fragmentary sectional view of a nuclear reactor containment vessel by other embodiment explanatory drawing with which 1st Embodiment of this invention was equipped. Explanatory drawing of the nuclear reactor containment vessel which shows 2nd Embodiment of this invention. Explanatory drawing of the nuclear reactor containment vessel which shows 3rd Embodiment of this invention. Explanatory drawing of the nuclear reactor containment vessel which shows 4th Embodiment of this invention. Explanatory drawing of the nuclear reactor containment vessel which shows 5th Embodiment of this invention. Explanatory drawing of the nuclear reactor containment vessel which shows 6th Embodiment of this invention.

Explanation of symbols

DESCRIPTION OF SYMBOLS 1 Reactor containment vessel 2 Reactor pressure vessel 3 Pressure vessel support pedestal 4 Core 5 Lower dry well 6 Pressure suppression chamber 7 Pressure suppression pool 8 Upper dry well 9 Hopper 9a Tube portion 9b Inclined portion 9c Drop port 9A High melting point material 9B Low heat Conductive material 9C High ductility material 10 Core catcher 10A High melting point material 10B Low thermal conductivity material 10C High ductility material 11A, 11B, 111A, 211A, 311A Neutron absorber 16 Heat exchanger 17 Circulation pump 18 Cooling device 19 Heat pipe 20 Condensing cooling section

Claims (11)

A reactor pressure vessel;
A pressure vessel support pedestal provided with the reactor pressure vessel;
A core housed in the reactor pressure vessel;
A lower dry well provided below the reactor pressure vessel;
A pressure suppression chamber provided around the pressure vessel support pedestal;
A pressure suppression pool in which water is stored in the pressure control chamber;
An upper dry well provided around the reactor pressure vessel;
In a containment vessel with
A hopper that is installed below the reactor pressure vessel and receives and guides the core melt from the core so that it does not scatter.
A core catcher for holding the core melt, provided on the floor of the lower dry well;
A cooling water passage gap formed by a gap between a side wall surface and a floor surface of the lower dry well and a side surface and a bottom surface of the core catcher;
A cooling water channel for supplying water of the pressure suppression pool to the cooling water channel gap;
A reactor containment vessel characterized by comprising: The reactor containment vessel according to claim 1, wherein the inner surface layer of the hopper is made of a high melting point material, the intermediate layer is made of a low heat conductive material, and the outer surface layer is made of a highly ductile material. The reactor containment vessel according to claim 1 or 2, wherein an inner surface layer of the core catcher is made of a high melting point material, an intermediate layer is made of a low thermal conductivity material, and a re-outer layer is made of a high ductility material. The reactor containment vessel according to any one of claims 1 to 3, wherein a glass body formed into a pellet shape is laid inside the core catcher. The reactor containment according to any one of claims 1 to 3, wherein a glass body formed into a pellet and a neutron absorber formed into a pellet are mixed and laid inside the core catcher. container. The cooling water passage gap is provided in communication with the gap between the side wall surface and floor surface of the lower dry well and the side surface and bottom surface of the core catcher, and is configured to be sealed at the top of the side surface of the core catcher.
The cooling water channel is connected to the bottom of the cooling water channel gap and a low position of the pressure suppression chamber pool, and is connected to the upper part of the cooling water channel gap and the high position of the pressure suppression chamber pool. The reactor containment vessel according to any one of claims 1 to 5, characterized in that the reactor containment pipe is connected to the communication pipe. The cooling water passage gap is configured such that the gap between the floor surface of the lower dry well and the bottom surface of the core catcher is sealed at the bottom of the side surface of the core catcher,
The cooling water channel is connected to and communicated with a bottom of the cooling water channel gap and a lower position of the pressure suppression pool, and a communication pipe connected to an outer periphery of the cooling water channel gap and a higher position of the pressure suppression pool. The reactor containment vessel according to any one of claims 1 to 5, characterized in that the reactor containment pipe is configured to be connected to the communication pipe. The bottom of the core catcher is configured in an inverted cone shape,
The reactor containment vessel according to any one of claims 1 to 7, wherein the cooling channel gap is configured to follow a bottom shape of an inverted cone of the core catcher. A heat exchanger,
A cooling device connected to the heat exchanger;
A refrigerant circulating in the heat exchanger and the cooling device;
A circulation pump for circulating the refrigerant;
The high-temperature part of the said heat exchanger is immersed in the said pressure suppression chamber pool, It comprised so that a pressure suppression pool might be cooled, The any one of Claim 1 to 8 characterized by the above-mentioned. Reactor containment vessel. Heat pipes,
A condensation cooling unit connected to the heat pipe;
A refrigerant circulating in the heat pipe and the cooling device;
The atom according to any one of claims 1 to 8, characterized in that the high-temperature portion of the heat pipe is immersed in the pressure suppression chamber pool to cool the pressure suppression pool. Containment vessel. The reactor containment vessel according to claim 10, wherein the condensation cooling unit is provided in the upper dry well.

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