JP7232164B2 - nuclear power plant - Google Patents

Description

The present invention relates to a nuclear plant with a nuclear reactor and a reactor building.

Regarding the location of a nuclear power plant, it is necessary to install the reactor building and the building that houses the safety equipment on stable ground and in a position that avoids faults within the power plant site.
Furthermore, since power plants in Japan use seawater for final heat removal, it is necessary to locate seawater cooling equipment for heat removal as close to the coastline as possible.

In a conventional BWR (boiling water reactor) plant, reactor system facilities (buildings) and seawater cooling facilities are located in separate buildings due to restrictions on building shape and facility layout. (See, for example, Patent Document 1.).
Buildings for these facilities must each be designed to be the most earthquake resistant (S class), increasing the cost of building design and construction.

JP 2012-230085 A

Reactor auxiliary cooling water system (RCW: Reactor Building Closed Cooling Water System) and seawater cooling system (RSW: Reactor Building Closed Cooling Sea Water System) equipment dissipates the heat generated from the reactor during normal operation and during emergencies. Transfer to the sea, the final refuge.
These RCW and RSW facilities are important systems for safety, so they are required to withstand the most severe natural events, including earthquakes, and are designed with redundancy so that they can achieve their functions. should be

In a conventional nuclear power plant, from the viewpoint of maintainability, the RSW facility among the RCW and RSW facilities is installed in a building separate from the reactor building.

However, due to the recent increase in seismic ground motion and the demand for strengthening system separation due to stricter separation of sections due to fires and flooding, the range of seismic strengthening of buildings other than the reactor building and the range of strengthening system separation are expanding. . Along with this, the range of countermeasures against fire and flooding of doors, pipes and cable openings has expanded, which is a factor in increasing plant costs.

SUMMARY OF THE INVENTION An object of the present invention is to provide a nuclear power plant capable of strengthening facilities and suppressing an increase in costs associated with the strengthening of facilities.

In addition, the above objects, other objects and novel features of the present invention will be made clear by the description of the specification and the accompanying drawings.

A nuclear power plant of the present invention is a nuclear power plant comprising a nuclear reactor and a reactor building housing the nuclear reactor, and a reactor auxiliary equipment cooling system for cooling auxiliary equipment for the nuclear reactor is provided in the reactor building. system equipment, and seawater cooling system equipment that takes in seawater for cooling the cooling water of the reactor auxiliary cooling system equipment. It is divided into system divisions, and reactor auxiliary cooling system equipment and seawater cooling system equipment are arranged for each system division of the reactor building divided into multiple system divisions.

According to the present invention, the reactor auxiliary cooling system equipment and the seawater cooling system equipment are arranged in the reactor building. It is possible to reduce the number of buildings with high earthquake resistance and consolidate them, and to suppress the dispersion of buildings with high earthquake resistance.
Therefore, it is possible to strengthen the facilities, and to suppress increases in building design and building costs associated with the reinforcement of the facilities.

Problems, configurations, and effects other than those described above will be clarified by the following description of the embodiments.

1 is a plan view of a nuclear power plant to which the present invention is applied; FIG.

Hereinafter, embodiments and examples according to the present invention will be described with reference to sentences or drawings. However, the structure, materials, and various other specific configurations shown in the present invention are not limited to the embodiments and examples taken up here, and can be appropriately combined and improved within the scope of not changing the gist. is. Elements that are not directly related to the present invention are omitted from the drawing.

A nuclear power plant of the present invention comprises a nuclear reactor and a reactor building housing the nuclear reactor, and in the reactor building, a reactor auxiliary equipment cooling system facility for cooling auxiliary equipment for the nuclear reactor, and a nuclear A seawater cooling system facility for taking in seawater for cooling the cooling water of the reactor auxiliary cooling system facility is arranged.

A reactor building is a building that houses a nuclear reactor inside.
In the above nuclear power plant, in addition to the reactor, a reactor auxiliary cooling system facility and a seawater cooling system facility are arranged in the reactor building.
A reactor component cooling system (RCW) facility is a facility for cooling accessories (pumps, coolers, heat exchangers, etc.) for a nuclear reactor.
A seawater cooling system (RSW) facility is a facility that takes in seawater for cooling the cooling water of the reactor component cooling system facility.

In the above nuclear power plant, the reactor building containing the reactor is further divided into multiple system divisions, and for each system division of the reactor building, the reactor auxiliary cooling system equipment and the seawater cooling system equipment are installed. , respectively.

In the above nuclear power plant, the reactor building is further divided into three system divisions, and adjacent to each system division of the reactor building, there are reactor auxiliary cooling system equipment and seawater cooling system equipment for each system division. It can be arranged.
In this nuclear power plant configuration, the reactor auxiliary cooling system equipment and the seawater cooling system equipment for the three system divisions are arranged along each of the three sides of the outer periphery of the reactor building. can do.

In the above nuclear power plant, the reactor auxiliary cooling system equipment and the seawater cooling system equipment of each system division are further surrounded by earthquake-resistant walls, and the earthquake-resistant walls separate the reactor auxiliary cooling system equipment of different system divisions. and seawater cooling system equipment.

In the above nuclear power plant, furthermore, an integral water intake channel or a separate water intake channel for each system division provided in accordance with the arrangement of the pumps of the seawater cooling system equipment for each system division installed in the reactor building , can be configured.

In the above nuclear power plant, the pump of the seawater cooling system installed in the reactor building can be replaced.

The nuclear power plant of the present invention can be applied to various nuclear reactors such as boiling water reactors (BWR).

According to the nuclear power plant having the configuration described above, the reactor auxiliary cooling system equipment and the seawater cooling system equipment, which were conventionally installed in a separate building from the reactor building, are installed in the reactor building.
As a result, there is no need to provide separate buildings for the reactor auxiliary cooling system equipment and the seawater cooling system equipment, resulting in the following advantages.
(1) Even if the seismic resistance of the reactor auxiliary cooling system equipment and the seawater cooling system equipment is strengthened, the number of necessary buildings can be reduced and consolidated. For this reason, it becomes possible to construct a nuclear power plant even in a cramped place where site conditions are severe.
(2) Even if the seismic resistance of the reactor auxiliary cooling system and seawater cooling system is strengthened, the dispersal of buildings with high seismic resistance (such as the S class mentioned above) can be suppressed, so rational building design and Building costs can be reduced. In buildings other than the reactor building (for example, the turbine building, etc.), there is no need for an unnecessarily high level of earthquake resistance, and design can be made according to the earthquake resistance class of the building.
(3) Since the reactor, reactor auxiliary cooling system equipment, and seawater cooling system equipment are installed in the same reactor building, in the conventional configuration, necessary for the reactor auxiliary cooling system equipment and the seawater cooling system equipment This eliminates the need for connecting pipes between different buildings. Therefore, it is possible to avoid a cause of breakage of pipes (connection pipes, etc.) due to relative displacement during an earthquake or the like.
(4) Since the reactor, reactor auxiliary cooling system equipment, and seawater cooling system equipment are installed in the same reactor building, the length of piping for the reactor auxiliary cooling system equipment and seawater cooling system equipment is greatly reduced. can. Therefore, the risk of pipe breakage can be minimized.
(5) Since the inspection of the reactor auxiliary cooling system equipment can be performed in the reactor building, maintenance and inspection of the reactor auxiliary cooling system equipment can be ensured even in a confined space, and periodic inspections can be performed. It is possible to shorten the time required for

In addition, the reactor building containing the reactor is divided into multiple system divisions, and the reactor auxiliary cooling system equipment and seawater cooling system equipment are arranged for each system division of the reactor building. When this is done, cooling can be performed independently for each system section. Therefore, even if one system section is stopped due to equipment maintenance or failure, the other system section can be used for cooling.

Furthermore, the reactor auxiliary cooling system equipment and seawater cooling system equipment of each system division are surrounded by seismic walls, and are separated from the reactor auxiliary cooling system equipment and seawater cooling system equipment of other system divisions by the seismic walls. When the configuration is such that the safety system equipment and the seawater system equipment can be completely separated. In addition, since each system of safety system equipment can be separated and independent, it is possible to further improve safety. Then, the seismic walls enable each system division to be partitioned with a strong frame that can withstand the water pressure caused by internal flooding.

In addition, when the water intake channel is separated for each system division in accordance with the arrangement of the pumps of the seawater cooling system equipment for each system division installed in the reactor building, the multiplicity of intake passages can be ensured. In addition, it becomes possible to thoroughly separate the system division from the most upstream to the most terminal.
On the other hand, when the integrated intake channel is configured in accordance with the arrangement of the pumps of the seawater cooling system equipment for each system division installed in the reactor building, the intake channel is integrated even if the system division is separated. Therefore, the area occupied by the intake channel can be reduced. As a result, the intake channel and its intake can be arranged even in a geographically narrow place.

A nuclear power plant according to an embodiment of the present invention will be described below with reference to the drawings.

(Example 1)
FIG. 1 shows a plan view of a nuclear power plant to which the present invention is applied as an embodiment of the nuclear power plant of the present invention.

The nuclear power plant shown in FIG. 1 includes a reactor building 1 and a turbine building 5 .
The reactor building 1 and the turbine building 5 are arranged adjacent to each other.

A reactor building 1 is mainly composed of a reactor building 3 containing a reactor 2 and an annex building 4 installed so as to surround the reactor building 3 .

The reactor 2 is surrounded by earthquake-resistant walls having a circular planar shape, and although not shown, there is a reactor containment vessel containing a reactor pressure vessel containing fuel, a reactor pressure vessel, a pressure suppression pool, and a recirculation pump. container, etc.

In the reactor building 3, the section outside the circular seismic wall of the reactor 2 is divided into three system sections, a system A section 3a, a system B section 3b, and a system C section 3c. The A system section 3a is arranged on the upper right side of the reactor 2 in the drawing, the B system section 3b is arranged on the lower right side of the reactor 2 in the drawing, and the C system section 3c is arranged on the left side of the reactor 2 in the drawing. .

The equipment in the annex building 4 is installed so as to be close to the system divisions 3a, 3b, and 3c of the reactor building 3, and the equipment in the annex building 4 is installed according to the system divisions 3a, 3b, and 3c of the adjacent reactor building 3. A system division is determined.
1 specifically shows RSW pumps 6a, 6b, 6c, RSW pipes 7a, 7b, 7c, and RCW heat exchangers 8a, 8b, 8b as devices in the annex 4. FIG.

The A-system RSW pump 6a and the A-system RCW heat exchanger 8a are provided along the right side of the reactor building 1 in the drawing, and are adjacent to the outside of the A-system section 3a in the reactor building 3. It is installed in the A system division of building 4.
The A-system RSW pump 6a and the A-system RCW heat exchanger 8a are arranged close to each other and connected by an A-system RSW pipe 7a in order to reduce the risk of breakage of seawater pipes and the potential for leakage of seawater. .
The A-system RCW heat exchanger 8a includes an A-system diesel generator auxiliary machine (not shown) installed in the annex building 4 and an A-system residual heat removal system (RHR; Residual heat removal system) in the reactor building 3. Heat Removal System) cools the heat exchanger (not shown).
The A-system RCW heat exchanger 8a and the A-system residual heat removal system (RHR) heat exchanger in the A-system section 3a of the reactor building 3 are connected by an A-system RCW pipe 9a.
An earthquake-resistant wall is provided between the A-system RSW pump 6a and the A-system RCW heat exchanger 8a, and the A-system RSW pipe 7a is arranged in a through hole opened in the earthquake-resistant wall.
An earthquake-resistant wall is provided between the A-system RCW heat exchanger 8a and the A-system section 3a of the reactor building 3, and the A-system RCW pipe 9a is arranged in a through hole opened in the earthquake-resistant wall.
In addition, the outer walls of the A-system RSW pump 6a and the A-system RCW heat exchanger 8a (also serving as the outer wall of the reactor building 1) are earthquake-resistant walls.

A B system RSW pump 6b is installed in the B system section of the annex building 4, which is provided along the lower side of the reactor building 1 in the drawing and is adjacent to the outside of the B system section 3b in the reactor building 3. , a B-system RSW pipe 7b, and a B-system RCW heat exchanger 8b are installed. A system B RCW pipe 9b connects the system B RCW heat exchanger 8b and a system B residual heat removal system (RHR) heat exchanger (not shown) in the system B section 3b of the reactor building 3. .
The wall between the B system RSW pump 6b and the B system RCW heat exchanger 8b, the wall between the B system RCW heat exchanger 8b and the B system section 3b of the reactor building 3, the B system RSW pump 6b and the B system RCW The outer wall of the heat exchanger 8b (also serving as the outer wall of the reactor building 1) is a seismic wall.

C-system RSW pump 6c, C-system RSW pump 6c, A C-system RSW pipe 7c and a C-system RCW heat exchanger 8c are installed. A C-system RCW pipe 9c connects the C-system RCW heat exchanger 8c and a C-system residual heat removal system (RHR) heat exchanger (not shown) in the C-system section 3c of the reactor building 3. .
The wall between the C-system RSW pump 6c and the C-system RCW heat exchanger 8c, the wall between the C-system RCW heat exchanger 8c and the C-system section 3c of the reactor building 3, the C-system RSW pump 6c and the C-system RCW The outer wall of the heat exchanger 8c (also serving as the outer wall of the reactor building 1) is a seismic wall.

The RSW pumps 6a, 6b, 6c, the RSW pipes 7a, 7b, 7c, the RCW heat exchangers 8a, 8b, 8c, and the RCW pipes 9a, 9b, 9c are similar rotationally symmetrical in the A system, the B system, and the C system, respectively. , which standardizes the piping layout.

The walls of the reactor building 1 indicated by thick solid lines in the drawing are seismic walls, and sufficient seismic resistance is ensured in the reactor 2 and the facilities of the RSW and RCW.

In the nuclear power plant shown in FIG. 1, intake channels are installed for each system.
Specifically, the system A intake channel 10a draws seawater from the sea 11 into the RSW pump 6a, the system B intake channel 10b draws seawater from the sea 11 into the RSW pump 6b, and the seawater from the sea 11 into the RSW pump 6c. C-system intake channels 10c are provided independently of each other.

During the periodical inspection, the operation of all equipment in the reactor building 3 and the annex building 4 is stopped before inspection.
When replacing any one of the RSW pumps 6a, 6b, 6c, the operation of all the equipment in the reactor building 3 and the annex building 4 is stopped and the RSW pump to be replaced (for example, , A system RSW pump 6a) is replaced with a new RSW pump.
In order to replace or inspect the RSW pumps 6a, 6b, 6c, a door or the like is provided in the earthquake-resistant wall surrounding the RSW pumps 6a, 6b, 6c to allow the pumps to be taken in and out.

According to the configuration of the present embodiment described above, the RSW pumps 6a, 6b, 6c, the RSW pipes 7a, 7b, 7c, the RCW heat exchangers 8a, 8b, 8c, and the RCW pipes 9a, 9b, 9c are installed in the reactor building 1. placed inside. That is, a reactor component cooling system (RCW) facility and a seawater cooling system (RSW) facility are arranged in the reactor building 1 .
This eliminates the need for separate buildings for the Reactor Component Cooling System (RCW) and Seawater Cooling System (RSW) facilities.
Therefore, since the number of necessary buildings can be reduced and consolidated, it is possible to construct a nuclear power plant even in a narrow space with severe site conditions.
In addition, the dispersal of buildings with high earthquake resistance can be suppressed, making it possible to rationally design buildings and reduce building costs. Buildings other than the reactor building 1, such as the turbine building 5, can be designed according to the seismic class of the building.
In addition, connecting pipes between separate buildings, which were required in the conventional configuration, are no longer required. Therefore, it is possible to avoid a cause of breakage of the connecting pipe or the like due to relative displacement during an earthquake or the like.
In addition, the pipe lengths of the RSW pipes 7a, 7b, 7c and the RCW pipes 9a, 9b, 9c can be significantly shortened. Therefore, the risk of pipe breakage can be minimized.
In addition, since the RCW equipment can be inspected in the reactor building 1, maintenance and inspection of the RCW equipment can be ensured even in a narrow space, and the periodical inspection time can be shortened.

According to the configuration of the present embodiment described above, the reactor building 3 is divided into three system divisions 3a, 3b, and 3c, and each of the system divisions 3a, 3b, and 3c of the reactor building 3 has an RCW facility and an RSW Each facility is placed
Thereby, cooling can be performed independently for each system section. Therefore, even if one system section is stopped due to equipment maintenance or failure, the other system section can be used for cooling.

According to the configuration of the present embodiment described above, the walls surrounding the RSW pumps 6a, 6b, 6c and the RCW heat exchangers 8a, 8b, 8c are earthquake-resistant walls.
Thereby, the RCW equipment and the earthquake resistance of the RCW equipment can be strengthened.

According to the configuration of the present embodiment described above, the RCW equipment and RSW equipment of each system division of system A, B, and C are further separated from the RCW equipment and RSW equipment of another system division by seismic walls. ing.
As a result, safety system equipment and seawater system equipment can be completely separated. In addition, since each system of safety system equipment can be separated and independent, it is possible to further improve safety. Moreover, the seismic walls enable each system section to be partitioned with a strong frame that can withstand the water pressure caused by internal flooding.

According to the configuration of the present embodiment described above, the intake channels 10a, 10b, and 10c are separated for each system section in accordance with the arrangement of the RSW pumps 6a, 6b, and 6c for each system section installed in the reactor building 1. have
As a result, it is possible to secure the multiplicity of intake channels and to thoroughly separate the system division from the most upstream to the most terminal.

(Modification)
In Example 1, the water intake channels 10a, 10b, and 10c are provided independently for each system, and the water intake ports from the sea 11 of the respective water intake channels 10a, 10b, and 10c are provided separately.
On the other hand, it is also possible to use a common intake for two or more systems, and to have a structure in which the intake channel is branched in the middle to be separated for each system. If the water intake is shared in this way, it is possible to provide an intake channel for each system even when it is difficult to provide separate water intakes for each system due to restrictions on the topography of the coast.

Although three systems (system A, system B, system C) are provided in the first embodiment, the number of systems is not limited to three, and a plurality of systems (two or more) may be provided.
By providing a plurality of systems, even if one system stops for some reason, the other system can be operated.

The present invention is not limited to the above-described embodiments and examples, and includes various modifications. For example, the above-described embodiments have been described in detail for easy understanding of the present invention, and are not necessarily limited to those having all the described configurations.

DESCRIPTION OF SYMBOLS 1... Reactor building, 2... Reactor, 3... Reactor building, 3a... System A division, 3b... System B division, 3c... System C division, 4... Annex building, 5... Turbine building, 6a... System A RSW Pumps 6b...B system RSW pump 6c...C system RSW pump 7a...A system RSW pipe 7b...B system RSW pipe 7c...C system RSW pipe 8a...A system RCW heat exchanger 8b...B system RCW heat exchanger 8c...C system RCW heat exchanger 9a...A system RCW pipe 9b...B system RCW pipe 9c...C system RCW pipe 10a...A system intake channel 10b...B system intake channel 10c ... C system intake channel, 11 ... sea

Claims (6)

A nuclear plant comprising a reactor and a reactor building housing the reactor,
In the reactor building, reactor auxiliary equipment cooling system equipment for cooling the nuclear reactor auxiliary equipment, and seawater cooling system equipment for taking in seawater for cooling the cooling water of the nuclear reactor auxiliary equipment cooling system equipment. is placed and
The reactor building includes a reactor building containing the reactor, the reactor building is divided into a plurality of system divisions, and each system of the reactor building divided into the plurality of system divisions The reactor auxiliary cooling system equipment and the seawater cooling system equipment are respectively arranged for the divisions
nuclear plant. The reactor building is divided into three system divisions, and the reactor auxiliary cooling system equipment and the seawater cooling system equipment for each system division are arranged adjacent to each of the system divisions of the reactor building. 2. The nuclear plant of claim 1 , wherein the nuclear plant. 3. The system according to claim 2, wherein said reactor auxiliary cooling system equipment and said seawater cooling system equipment for said three system sections are arranged along each of three sides of an outer circumference of said reactor building. nuclear plant. The reactor auxiliary cooling system equipment and the seawater cooling system equipment of each system division are surrounded by earthquake-resistant walls, and the reactor auxiliary cooling system equipment and the seawater cooling systems of different system divisions are surrounded by the earthquake-resistant walls. 2. A nuclear plant according to claim 1 , separate from system equipment. Claim having an integrated water intake channel or separate water intake channels for each of the system divisions installed in the reactor building, provided in accordance with the arrangement of the pumps of the seawater cooling system equipment of each system division Item 1. The nuclear power plant according to Item 1 . 2. The nuclear power plant according to claim 1, wherein pumps of said seawater cooling system installed in each of said system divisions of said reactor building of said reactor building are replaceable.

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