JP2021063771A - Nuclear power plant - Google Patents

Abstract

To provide a nuclear power plant that reinforces a facility and prevents increase of cost for the reinforcement of the facility.SOLUTION: The nuclear power plant includes: a nuclear reactor; and a nuclear reactor building for containing the nuclear reactor. The nuclear reactor building includes: a nuclear reactor sub-machine cooling system facility for cooling a sub-machine for the nuclear reactor; and a sea water cooling system facility for drawing sea water to cool the cooling water of the nuclear reactor sub-machine cooling system facility.SELECTED DRAWING: Figure 1

Description

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

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

In a conventional BWR (boiling water reactor) plant, the reactor system equipment (building) and seawater cooling equipment are arranged in a distributed manner, that is, in different buildings due to restrictions on the building shape and equipment layout. (See, for example, Patent Document 1).
Since each of the buildings of these facilities needs to be designed as having the most seismic resistance (S class), the cost of designing and constructing the building is high.

Japanese Unexamined Patent Publication No. 2012-23805

Reactor Building Closed Cooling Water System (RCW) and Reactor Building Closed Cooling Sea Water System (RSW) equipment generate heat from reactors during normal operation and emergencies. Transfer to the sea, the final escape.
Since each of these RCW and RSW facilities is an important system for safety, it is required to withstand the most severe natural events including earthquakes, and it is designed with multiplex to achieve its functions. Must be.

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

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

An object of the present invention is to provide a nuclear power plant that can strengthen the equipment and suppress the increase in cost due to the strengthening of the equipment.

In addition, the above-mentioned object and other object and novel features of the present invention will be clarified by the description and the accompanying drawings of the present specification.

The nuclear power plant of the present invention is a nuclear power plant including a nuclear reactor and a reactor building accommodating the nuclear reactor, and is used for cooling auxiliary equipment for the reactor in the reactor building. The configuration is such that the system equipment and the seawater cooling system equipment that takes in the seawater that cools the cooling water of the reactor auxiliary cooling system equipment are arranged.

According to the present invention, since the reactor auxiliary cooling system equipment and the seawater cooling system equipment are arranged in the reactor building, it is necessary even if the earthquake resistance of the reactor auxiliary equipment cooling system equipment and the seawater cooling system equipment is strengthened. The number of buildings can be reduced and consolidated, and the dispersion of buildings with high earthquake resistance can be suppressed.
Therefore, it is possible to strengthen the equipment and realize the building design and the suppression of the increase in the cost of the building due to the strengthening of the equipment.

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

It is a top view of the nuclear power plant to which this invention was applied.

Hereinafter, embodiments and examples according to the present invention will be described with reference to text 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 without changing the gist. Is. In addition, elements not directly related to the present invention are not shown.

The nuclear power plant of the present invention includes a nuclear reactor and a nuclear reactor building accommodating the nuclear reactor, and in the nuclear reactor building, a nuclear reactor auxiliary equipment cooling system facility for cooling auxiliary equipment for the nuclear reactor, and an atomic reactor. This is a configuration in which seawater cooling system equipment that takes in seawater that cools the cooling water of the reactor auxiliary cooling system equipment is arranged.

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

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

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

In the above nuclear power plant, the reactor auxiliary cooling system equipment and seawater cooling system equipment of each system division are further surrounded by a seismic wall, and the reactor auxiliary equipment cooling system equipment of another system division is surrounded by the seismic wall. And the configuration can be separated from the seawater cooling system equipment.

In the above nuclear power plant, an integrated intake channel installed in the reactor building according to the arrangement of pumps of the seawater cooling system equipment of each system division, or an intake channel separated for each system division. , Can be configured to have.

In the above nuclear power plant, the pump of the seawater cooling system equipment installed in the reactor building can be further configured to be replaceable.

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

According to the nuclear power plant having the above-described configuration, the reactor auxiliary cooling system equipment and the seawater cooling system equipment, which were conventionally installed in a building different from the reactor building, are installed in the reactor building.
As a result, it is not necessary to provide a separate building for the reactor auxiliary cooling system equipment and the seawater cooling system equipment, which has the following advantages.
(1) Even if the seismic resistance of the reactor auxiliary cooling system equipment and seawater cooling system equipment is strengthened, the number of required buildings can be reduced and consolidated. Therefore, it is possible to construct a nuclear power plant even in a narrow place where the location conditions are strict.
(2) Even if the seismic resistance of the reactor auxiliary cooling system equipment and seawater cooling system equipment is strengthened, the dispersion of buildings with high seismic resistance (S class, etc. mentioned above) can be suppressed. It is possible to reduce the cost of the building. Then, in a building other than the reactor building (for example, a turbine building, etc.), it is not necessary to have higher seismic resistance than necessary, and it is possible to design the building according to the seismic class.
(3) Since the reactor, reactor auxiliary cooling system equipment and seawater cooling system equipment are installed in the same reactor building, it is necessary for the reactor auxiliary equipment cooling system equipment and seawater cooling system equipment in the conventional configuration. However, there is no need for a crossing pipe between other buildings. Therefore, it is possible to avoid the cause of breakage of pipes (crossover 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 will be installed in the same reactor building, the piping length for the reactor auxiliary equipment cooling system equipment and seawater cooling system equipment will be significantly shortened. it can. Therefore, the risk of pipe breakage can be minimized.
(5) Since the inspection of the reactor auxiliary cooling system equipment can be performed inside the reactor building, the maintenance and inspection of the reactor auxiliary cooling system equipment can be ensured even in a narrow place, and the periodic inspection It is possible to reduce 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 happens, cooling can be performed independently for each system division. Therefore, even if one system division is stopped due to equipment maintenance or failure, cooling can be performed by the other system division.

Furthermore, the reactor auxiliary cooling system equipment and seawater cooling system equipment of each system division are surrounded by a seismic wall, and are separated from the reactor auxiliary equipment cooling system equipment and seawater cooling system equipment of another system division by the seismic wall. When the configuration is set up, safety equipment and seawater equipment can be completely separated. Further, since each system of the safety system can be separated and independent, the safety can be further improved. Then, each system division can be divided by a robust skeleton that receives the water pressure due to the internal overflow by the earthquake-resistant wall.

Further, when the structure is such that the intake channels are separated for each system division according to the arrangement of the pumps of the seawater cooling system equipment installed in the reactor building, the multiplicity of the intake channels can be ensured. In addition, it becomes possible to thoroughly separate from the most upstream to the most terminal of the system division.
On the other hand, when the structure has an integrated intake channel according to the arrangement of the pumps of the seawater cooling system equipment installed in the reactor building, the intake channels are integrated even if the system divisions are separated. Therefore, the area occupied by the intake channel can be reduced. As a result, the intake channel and its intake port can be arranged even in a geographically narrow place.

Hereinafter, the nuclear power plant according to the embodiment of the present invention will be described with reference to the drawings.

(Example 1)
As an example of the nuclear power plant of the present invention, a plan view of the nuclear power plant to which the present invention is applied is shown in FIG.

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.

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

The reactor 2 is surrounded by a seismic wall having a circular planar shape, and although not shown, the reactor containment vessel containing the fuel, the reactor pressure vessel, the pressure suppression pool, and the recirculation pump is stored. It is equipped with a container, etc.

In the reactor building 3, the section outside the circular earthquake-resistant wall of the reactor 2 is divided into three system sections, A system section 3a, B system section 3b, and C system section 3c. The A system division 3a is arranged in the upper right of the figure of the reactor 2, the B system division 3b is arranged in the lower right of the figure of the reactor 2, and the C system division 3c is arranged in the left of the figure of the reactor 2. ..

The equipment in the annex 4 is installed so as to be close to the system divisions 3a, 3b, 3c of the reactor building 3 described above, and in the annex 4 according to the system divisions 3a, 3b, 3c of the adjacent reactor building 3. The system classification is decided.
In FIG. 1, the RSW pumps 6a, 6b, 6c, the RSW pipes 7a, 7b, 7c, and the RCW heat exchangers 8a, 8b, 8b are specifically shown as the devices in the annex 4.

The A system RSW pump 6a and the A system RCW heat exchanger 8a are provided along the right side of the figure of the reactor building 1 and are adjacent to the outside of the A system division 3a in the reactor building 3, and are attached. It will be 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 in order to reduce the risk of breakage of the seawater system pipe and the leakage potential of seawater, and are connected by the A system RSW pipe 7a. ..
The A system RCW heat exchanger 8a includes an auxiliary machine (not shown) of the A system diesel generator installed in the annex 4 and an A system residual heat removal system (RHR; Residual) in the reactor building 3. Heat Removal System) The heat exchanger (not shown) is being cooled.
The A system RCW heat exchanger 8a and the A system residual heat removal system (RHR) heat exchanger in the A system division 3a of the reactor building 3 are connected by the A system RCW pipe 9a.
A seismic 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 seismic wall.
A seismic wall is provided between the A system RCW heat exchanger 8a and the A system division 3a of the reactor building 3, and the A system RCW pipe 9a is arranged in a through hole opened in the seismic wall.
Further, the outer walls of the A-based RSW pump 6a and the A-based RCW heat exchanger 8a (which also serve as the outer wall of the reactor building 1) are also earthquake-resistant walls.

The B system RSW pump 6b is provided in the B system division of the annex building 4 which is provided along the lower side of the figure of the reactor building 1 and is adjacent to the outside of the B system division 3b in the reactor building 3. , B system RSW pipe 7b and B system RCW heat exchanger 8b are installed. Then, the B system RCW pipe 9b connects the B system RCW heat exchanger 8b and the B system residual heat removal system (RHR) heat exchanger (not shown) in the B system division 3b of the reactor building 3. ..
The wall between the B-based RSW pump 6b and the B-based RCW heat exchanger 8b, the wall between the B-based RCW heat exchanger 8b and the B-based division 3b of the reactor building 3, the B-based RSW pump 6b and the B-based RCW The outer wall of the heat exchanger 8b (which also serves as the outer wall of the reactor building 1) is an earthquake-resistant wall.

In the C system division of the annex building 4, which is provided along the left side of the figure of the reactor building 1 and is adjacent to the outside of the C system division 3c in the reactor building 3, the C system RSW pump 6c, A C-based RSW pipe 7c and a C-based RCW heat exchanger 8c are installed. Then, the C system RCW pipe 9c connects the C system RCW heat exchanger 8c and the C system residual heat removal system (RHR) heat exchanger (not shown) in the C system division 3c of the reactor building 3. ..
The wall between the C-based RSW pump 6c and the C-based RCW heat exchanger 8c, the wall between the C-based RCW heat exchanger 8c and the C-based division 3c of the reactor building 3, the C-based RSW pump 6c and the C-based RCW The outer wall of the heat exchanger 8c (which also serves as the outer wall of the reactor building 1) is an earthquake-resistant wall.

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

The walls shown by the thick solid lines in the figure of the reactor building 1 are each earthquake-resistant walls, and sufficient earthquake resistance is ensured in the reactor 2, each facility of RSW and RCW.

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

When conducting a periodic inspection, the operation of all the equipment in the reactor building 3 and the annex building 4 is stopped and the inspection is performed.
Further, when replacing any of the RSW pumps 6a, 6b, 6c, the operation of all the equipment in the reactor building 3 and the accessory building 4 is stopped and replaced as in the periodic inspection (for example, the RSW pump (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 on 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, the RCW pipes 9a, 9b, 9c are installed in the reactor building 1 It is placed inside. That is, the reactor auxiliary cooling system (RCW) equipment and the seawater cooling system (RSW) equipment are arranged in the reactor building 1.
This eliminates the need to provide separate buildings for reactor auxiliary cooling system (RCW) equipment and seawater cooling system (RSW) equipment.
Therefore, since the number of required buildings can be reduced and consolidated, it is possible to construct a nuclear power plant even in a narrow place where the location conditions are strict.
In addition, it is possible to suppress the dispersion of buildings with high earthquake resistance, and it is possible to rationalize the building design and reduce the cost of the building. 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, the crossover piping between different buildings, which was required in the conventional configuration, becomes unnecessary. Therefore, it is possible to avoid the cause of breakage of the crossover pipe or the like due to the relative displacement during an earthquake or the like.
Further, 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.
Further, since the inspection of the RCW equipment can be performed in the reactor building 1, the maintenance and inspection of the RCW equipment can be ensured even in a narrow place, and the time required for the periodic inspection 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, 3c, and the RCW equipment and RSW are provided for the respective system divisions 3a, 3b, 3c of the reactor building 3. Each facility is located,
As a result, cooling can be performed independently for each system division. Therefore, even if one system division is stopped due to equipment maintenance or failure, cooling can be performed by the other system division.

According to the configuration of the present embodiment described above, the walls around the RSW pumps 6a, 6b, 6c and the RCW heat exchangers 8a, 8b, 8c are earthquake-resistant walls.
This makes it possible to enhance the seismic resistance of RCW equipment and RCW equipment.

According to the configuration of the present embodiment described above, the RCW equipment and RSW equipment of each system division of A system, B system and C system are further separated from the RCW equipment and RSW equipment of another system division by the earthquake-resistant wall. ing.
As a result, safety equipment and seawater equipment can be completely separated. Further, since each system of the safety system can be separated and independent, the safety can be further improved. Then, each system division can be divided by a robust skeleton that receives the water pressure due to the internal overflow by the earthquake-resistant wall.

According to the configuration of the present embodiment described above, the intake channels 10a, 10b, 10c separated for each system division according to the arrangement of the RSW pumps 6a, 6b, 6c of each system division installed in the reactor building 1. Has.
As a result, the multiplicity of intake channels can be ensured, and it becomes possible to thoroughly separate the system division from the most upstream to the terminal.

(Modification example)
In the first embodiment, the intake channels 10a, 10b, and 10c were independently provided for each system, and the intakes of the intake channels 10a, 10b, and 10c from the sea 11 were separately provided.
On the other hand, it is also possible to make the intake ports of two or more systems common, and to have a configuration in which the intake channels are branched in the middle and separated for each system. If the intakes are shared in this way, even if it is difficult to provide separate intakes for each system due to restrictions on the topography of the coast, it is possible to provide intake channels for each system.

In the first embodiment, three systems (A system, B system, C system) are provided, but the system is not limited to three, and a plurality of (two or more) systems may be provided.
By providing a plurality of systems, even if one system is stopped for some reason, the operation can be performed on the other system.

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

1 ... Reactor building, 2 ... Reactor, 3 ... Reactor building, 3a ... A system classification, 3b ... B system classification, 3c ... C system classification, 4 ... Annex building, 5 ... Turbine building, 6a ... A system RSW Pump, 6b ... B system RSW pump, 6c ... C system RSW pump, 7a ... A system RSW piping, 7b ... B system RSW piping, 7c ... C system RSW piping, 8a ... A system RCW heat exchanger, 8b ... B system RCW heat exchanger, 8c ... C system RCW heat exchanger, 9a ... A system RCW piping, 9b ... B system RCW piping, 9c ... C system RCW piping, 10a ... A system intake channel, 10b ... B system intake channel, 10c … C system intake channel, 11… sea

Claims (7)

A nuclear power plant equipped with a nuclear reactor and a reactor building that houses the nuclear reactor.
Reactor auxiliary equipment cooling system equipment for cooling auxiliary equipment for the reactor and seawater cooling system equipment for taking in seawater for cooling the cooling water of the reactor auxiliary equipment cooling system equipment in the reactor building. However, the nuclear plant where it was placed. The reactor building includes a reactor building containing the reactor, the reactor building is divided into a plurality of system divisions, and each of the systems of the reactor building divided into the plurality of system divisions. The nuclear power plant according to claim 1, wherein the reactor auxiliary cooling system equipment and the seawater cooling system equipment are respectively arranged for the classification. 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 system division of the reactor building. The nuclear plant according to claim 2. The third aspect of claim 3, wherein 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. Nuclear plant. The reactor auxiliary cooling system equipment and the seawater cooling system equipment of each of the above system divisions are surrounded by a seismic wall, and the said reactor auxiliary equipment cooling system equipment and the seawater cooling of another system division by the earthquake resistant wall. The nuclear power plant according to claim 2, which is separated from the system equipment. Claims having an integrated intake channel or an intake channel separated for each system category, which is installed in the reactor building and is provided according to the arrangement of pumps of the seawater cooling system equipment of each system category. Item 2. The nuclear power plant according to item 2. The nuclear power plant according to claim 1, wherein the pump of the seawater cooling system equipment installed in the reactor building has a configuration in which the pump can be replaced.

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