JP2014181928A - Reactor cooling system - Google Patents

Abstract

PROBLEM TO BE SOLVED: To provide a reactor cooling system that operates without a power source, can remove decay heat immediately after a reactor shutdown, and has no restriction in operation time.SOLUTION: A reactor cooling system comprises: a steam supply tube 21 for venting steam from a reactor pressure vessel 4, a steam generator 15, or a reactor containment vessel 2; a condensation tank 22 connected to a downstream side of the steam supply tube 21; a heat exchanger 27 that is connected to a downstream side of the condensation tank 22 and placed in a cooling pool 8; a return tube 28 whose one end is connected to a downstream side of the heat exchanger 27 and whose other end is connected to the reactor pressure vessel 4, the steam generator 15, or the reactor containment vessel 2; and an air-cooling system 23 that has an internal heat exchanger 24 placed in the condensation tank 22 and cools the internal heat exchanger 24 with air.

Description

  The present invention relates to a reactor cooling system.

  In a nuclear power generation system, for example, a boiling water reactor (BWR), it is necessary to cool the reactor by removing the decay heat of the core in the reactor pressure vessel even after the reactor is shut down. Usually, decay water is removed by extracting a part of water from the reactor pressure vessel, cooling the water through a heat exchanger that exchanges heat with seawater, and returning it to the reactor pressure vessel. Since this type of reactor cooling system uses an electric pump for drawing water from the reactor pressure vessel and pumping seawater for cooling, electricity is required for the operation of the cooling system. Therefore, when an abnormal event occurs in which power transmission from the outside to the reactor stops, an emergency generator installed in the reactor is activated to operate this cooling system.

  In view of this point, as a system capable of cooling a reactor without requiring a dynamic device such as a pump or a power source for operating the pump when power transmission from the outside to the reactor stops, Patent Document 1 and Patent There is a technique described in Document 2.

  The technique described in Patent Document 1 includes a cooling water pool provided above the reactor containment vessel, a heat exchanger in the cooling water pool, a steam chamber connected to the upper part of the heat exchanger, and a heat exchanger. A water chamber connected to the lower portion, a first piping connecting the steam chamber and the dry well of the reactor containment vessel, and a second piping connecting the bottom of the water chamber and the suppression pool of the reactor containment vessel; And a cooling system (static containment vessel cooling and cooling equipment) including a third pipe that connects the space portion of the water chamber and the suppression pool. In this system, steam that has flowed into the dry well due to an accident such as a reactor pipe breakage is led to the heat exchanger via the first pipe and condensed by heat exchange with the cooling water pool. It is made to flow into the suppression pool through the piping of No. 2, and operates without a power source by using as a driving force the pressure difference between the wet well and the dry well whose pressure has risen due to the outflowed steam. This system cools the decay heat of the core with water.

  In addition, the technique described in Patent Document 2 is an evaporation unit disposed so as to be able to transfer heat to the reactor pressure vessel, a condensing unit disposed above the reactor pressure vessel and exposed to the atmosphere, and an evaporation unit. A steam pipe that causes the working fluid to flow to the condensing part, a liquid return pipe that causes the working fluid condensed in the condensing part to flow to the evaporating part, a reservoir that stores the working fluid and is connected to the liquid return pipe, and a liquid return pipe And a cooling system including a loop heat pipe having a main valve that is opened under a predetermined condition. In this system, the working fluid in the reservoir is supplied to the evaporation section by opening the main valve, vaporized by heat exchange with the decay heat in the reactor pressure vessel, and the vaporized working fluid is supplied to the condensing section Then, it is condensed by heat exchange with the atmosphere, and the condensed working fluid is returned to the evaporation section. In other words, this system finally cools the decay heat of the core with air.

JP 2003-240888 A JP 2012-233737 A

  In the technique described in Patent Document 1 described above, since the decay heat of the core is transferred to the cooling water pool, the pool water is heated to boil and then evaporates. Since this system can utilize boiling heat transfer of water with a large heat transfer coefficient, it is easy to realize a system that removes the large decay heat immediately after the reactor shut down, but if the pool water does not evaporate, it will collapse. The heat removal function is substantially stopped. That is, there is a problem that the operation time of this system is limited by the pool water amount.

  On the other hand, the technique described in Patent Document 2 described above removes the decay heat of the core using air that is present infinitely, so there is no restriction on the operating time, but the technique described in Patent Document 1 Compared with such a water cooling system, the heat transfer coefficient is low and the heat removal performance is inferior. For this reason, it is necessary to increase the surface area of the condensing part that exchanges heat with the atmosphere in order to remove the large decay heat immediately after the reactor shutdown by this system, so it is not realistic considering the cost and installation location There's a problem.

  The present invention has been made to solve the above-described problems, and an object of the present invention is to operate a reactor without a power source, to remove decay heat immediately after shutting down the reactor, and to have no operating time restriction Is to provide.

In order to solve the above problems, for example, the configuration described in the claims is adopted.
The present application includes a plurality of means for solving the above-mentioned problems. To give an example, a reactor containment vessel, a reactor pressure vessel or a steam generator installed in the reactor containment vessel, and the atom A reactor cooling system comprising a reactor pressure vessel or a cooling pool installed at a position higher than the normal water level of the cooling water of the steam generator, the reactor pressure vessel, the steam generator, or the reactor A steam supply pipe for extracting steam from the containment vessel, a condensation tank connected to the downstream side of the steam supply pipe, a heat exchanger connected to the downstream side of the condensation tank and installed in the cooling pool, and one end thereof A return pipe connected to the downstream side of the heat exchanger and the other end connected to the reactor pressure vessel, the steam generator, or the reactor containment vessel, and an internal heat exchange installed in the condensation tank Has, the internal heat exchanger is characterized in that a cooling system for cooling the air.

According to the present invention, the steam generated by the decay heat is first cooled by air through the air cooling system and then cooled by the cooling pool through the heat exchanger, so that it operates without a power source. The decay heat immediately after the reactor shutdown can be removed and the operation time is not limited.
Problems, configurations, and effects other than those described above will be clarified by the following description of embodiments.

It is a schematic block diagram which shows the boiling water reactor to which 1st Embodiment of the reactor cooling system of this invention is applied. It is a schematic block diagram which shows the boiling water reactor to which 2nd Embodiment of the reactor cooling system of this invention is applied. It is a schematic block diagram which shows the boiling water reactor to which 3rd Embodiment of the reactor cooling system of this invention is applied. It is a schematic block diagram which shows an example of the pressurized water reactor to which 1st Embodiment of the reactor cooling system of this invention is applied. It is a schematic block diagram which shows the other example of the pressurized water reactor to which 1st Embodiment of the reactor cooling system of this invention is applied.

Hereinafter, embodiments of a reactor cooling system of the present invention will be described with reference to the drawings.
[First Embodiment]
FIG. 1 is a schematic configuration diagram showing a boiling water nuclear reactor to which a first embodiment of a reactor cooling system of the present invention is applied. The present embodiment is applied to a boiling water reactor (BWR).

  In FIG. 1, a reactor building 1 of a boiling water reactor is provided with a reactor containment vessel 2. In the reactor containment vessel 2, a reactor pressure vessel 4 containing a core 3 is installed. The inside of the reactor containment vessel 2 is divided into an upper dry well 5 surrounding the reactor pressure vessel 4, a lower dry well 6 formed below the reactor pressure vessel 4, and a wet well 7 for storing suppression pool water. It is partitioned. A cooling pool 8 is installed on the upper side outside the reactor containment vessel 2. The cooling pool 8 is installed at a position higher than the normal water level 4 a of the cooling water in the reactor pressure vessel 4.

  A reactor steam supply pipe (steam supply pipe) 21 for extracting steam from the reactor pressure container 4 is connected to the reactor pressure vessel 4. A condensing tank 22 installed vertically in the cooling pool 8 is connected to the downstream side (the other end side) of the reactor steam supply pipe 21. An air cooling system 23 that is finally cooled by air is connected to the condensation tank 22.

  The air cooling system 23 includes, for example, an internal heat exchanger 24 installed vertically in the condensation tank 22 and an external device installed vertically above the reactor building 1 and positioned above the internal heat exchanger 24. The heat exchanger 25 and a heat transport loop 26 connecting the heat exchangers 24 and 25 are configured as a closed loop. In the closed loop of the air cooling system 23, a coolant such as water or alternative chlorofluorocarbon is enclosed. The heat transport loop 26 includes, for example, a pipe 26a through which the vaporized refrigerant passes and a pipe 26b through which the condensed refrigerant passes.

  An emergency condenser heat exchanger (heat exchanger) 27 installed in the cooling pool 8 is connected to the downstream side of the condensation tank 22. One end of a condensed water return pipe (return pipe) 28 is connected to the downstream side of the emergency condenser heat exchanger 27. The other end of the condensed water return pipe 28 is connected to the reactor pressure vessel 4. An activation valve 29 is installed on the condensed water return pipe 28.

  A duct portion 30 is installed outside the reactor building 1. A flow path is formed by the reactor building 1 and the duct portion 30. An external heat exchanger 25 is disposed in this flow path.

  By the way, as a general knowledge, the decay heat immediately after the reactor shutdown, for example, 1 hour, is about 1.5% of the heat output during rated operation. The decay heat then gradually decreases and decreases to about 0.2% after 10 days.

  Therefore, in the present embodiment, the heat removal performance of the air cooling system 23 is equivalent to, for example, decay heat 10 days after the reactor shutdown. On the other hand, the cooling system using the pool water of the cooling pool 8 is designed with a heat removal amount equivalent to the decay heat immediately after the reactor stop or a heat removal amount obtained by subtracting the heat removal amount of the air cooling system 23 from the heat amount of the decay heat.

Next, operation | movement of 1st Embodiment of the reactor cooling system of this invention is demonstrated using FIG.
Even after the reactor is shut down, the decay heat of the core 3 is generated inside the reactor pressure vessel 4 and steam is generated. In order to remove the decay heat and cool the reactor, the start valve 29 is opened.

  When the start valve 29 is opened, the steam in the reactor pressure vessel 4 is extracted and supplied to the condensation tank 22 through the reactor steam supply pipe 21. A part of this vapor is cooled and condensed by air through an air cooling system 23 connected to the condensation tank 22.

  Specifically, a part of the steam flowing into the condensation tank 22 is cooled and condensed by exchanging heat with the refrigerant in the internal heat exchanger 24 of the air cooling system 23. On the other hand, the refrigerant in the internal heat exchanger 24 is vaporized by exchanging heat with the steam, and flows into the external heat exchanger 25 through the pipe 26a of the heat transport loop 26. The vaporized refrigerant is cooled and condensed by exchanging heat with the air outside the reactor building 1 via the external heat exchanger 25. The condensed refrigerant returns to the internal heat exchanger 24 through the pipe 26b of the heat transport loop 26 by gravity, and cools the vapor flowing into the condensation tank 22.

  Moreover, the external air heat-exchanged with the refrigerant | coolant which flowed into the external heat exchanger 25 is heated, and the inside of the duct part 30 rises by buoyancy. As a result, the air flows in the duct portion 30 and the refrigerant flowing into the external heat exchanger 25 is effectively cooled.

  Thus, this air cooling system 23 finally cools the vapor | steam which flowed in the condensation tank 22 with external air using the circulating refrigerant | coolant. However, since the heat removal performance of the air cooling system 23 is equivalent to the decay heat after a certain period of time after the reactor is shut down, it is not possible to condense all the steam flowing into the condensation tank 22.

  The steam that has not been condensed in the condensing tank 22 is condensed by exchanging heat with the pool water of the cooling pool 8 via the emergency condenser heat exchanger 27. The condensed water returns to the reactor pressure vessel 4 through the condensed water return pipe 28 by gravity.

  Pool water in the cooling pool 8 heated by steam through the emergency condenser heat exchanger 27 boils and evaporates. For this reason, this cooling system can utilize boiling heat transfer of water having a large heat transfer coefficient, and can remove large decay heat immediately after the reactor is shut down.

  Then, with the removal of decay heat, the pool water in the cooling pool 8 is depleted, and the operation of the cooling system by the cooling pool 8 is substantially stopped. At this time, the decay heat has decreased with the passage of time, so that all the decay heat generated can be removed by the air cooling system 23. Since this air cooling system 23 uses the air outside the reactor building 1 which exists substantially infinitely, there is no restriction on the operation time.

  Note that the start valve 29 is closed during the normal operation of the nuclear reactor. For this reason, when the steam flowing into the condensation tank 22 condenses, the condensed water accumulates in the condensation tank 22. In this state, the refrigerant of the air cooling system 23 does not circulate, and the air cooling system 23 automatically stops its operation. As a result, the heat energy of the steam in the nuclear pressure vessel 4 is not released to the outside of the reactor building 1 by the air cooling system 23 during normal operation of the reactor.

  On the other hand, when the starting valve 29 is opened, the condensed water accumulated in the condensing tank 22 due to the closing of the starting valve 29 is discharged downstream. For this reason, the steam of the reactor pressure vessel 4 flows into the condensation tank 22 and the refrigerant of the air cooling system 23 is vaporized, so that the refrigerant starts to circulate in the closed loop of the air cooling system 23. That is, the air cooling system 23 is automatically activated when the activation valve 29 is opened.

  As described above, according to the first embodiment of the reactor cooling system of the present invention, the steam generated by the decay heat is first cooled by air through the air cooling system 23 and then the emergency recovery. Since the cooling pool 8 is used for cooling through the water heat exchanger (heat exchanger) 27, it operates without a power source, can remove decay heat immediately after the reactor is shut down, and is limited in operating time. Absent.

  Furthermore, according to the present embodiment, since a part of the decay heat is removed by the air cooling system 23 immediately after the reactor is shut down, the evaporation of the pool water in the cooling pool 8 is suppressed, and the operating time of the cooling system by the cooling pool 8 Can be long. Further, the longer the operation time of the cooling system by the cooling pool 8 is, the smaller the decay heat of the nuclear reactor becomes, so the heat removal by the air cooling system 23 becomes easier.

  Furthermore, according to the present embodiment, the internal heat exchanger 24 and the external heat exchange are not directly led to the steam containing the radioactive substance to the heat exchanger installed outside the reactor building 1 and cooled by air. The steam is cooled by the air outside the reactor building 1 through the closed-loop air cooling system 23 constituted by the reactor 25 and the heat transport loop 26 connecting the two heat exchangers 24, 25. Therefore, the reactor building 1 Even when the external heat exchanger 25 installed outside is damaged, the radioactive material is not released into the air outside the reactor building 1.

  Further, according to the present embodiment, the air cooling system 23 is automatically started / stopped by opening / closing the start valve 29 provided in the cooling system by the cooling pool 8, so that the air cooling system 23 is started / stopped. There is no need to install a separate valve. As a result, it is possible to reduce the risk of inability to start due to the provision of a plurality of start valves.

[Second Embodiment]
Next, a second embodiment of the reactor cooling system of the present invention will be described with reference to FIG. FIG. 2 is a schematic configuration diagram showing a boiling water reactor to which the second embodiment of the reactor cooling system of the present invention is applied. In FIG. 2, the same reference numerals as those shown in FIG. 1 denote the same parts, and a detailed description thereof will be omitted.

  In the second embodiment of the reactor cooling system of the present invention shown in FIG. 2, the first embodiment cools the steam in the reactor pressure vessel, whereas the reactor pressure vessel or the like The steam discharged from the reactor into the reactor containment vessel is cooled.

  Specifically, a containment vessel steam supply pipe (steam supply pipe) 41 for extracting steam from the reactor containment vessel 2 is connected to the reactor containment vessel 2. A condensation tank 22 is connected to the downstream side of the containment vessel steam supply pipe 41.

  A static containment vessel cooling facility heat exchanger (heat exchanger) 47 installed in the cooling pool 8 is connected to the downstream side of the condensation tank 22. One end of a containment vessel return pipe (return pipe) 48 is connected to the downstream side of the static containment vessel cooling equipment heat exchanger 47. The other end of the containment vessel return pipe 48 is connected to the wet well 7 in the reactor containment vessel 2.

Next, operation | movement of 2nd Embodiment of the reactor cooling system of this invention is demonstrated using FIG.
When a pipe rupture accident occurs in the reactor with a low probability, the steam in the reactor pressure vessel 4 generated by the decay heat is released into the upper dry well 5 and the lower dry well 6 from the broken pipe. This vapor increases the pressure in the dry wells 5 and 6.

  Vapor discharged to the dry wells 5 and 6 passes through the containment vessel vapor supply pipe 41 using the non-condensable gas in the dry wells 5 and 6 as a driving force with a pressure difference between the dry wells 5 and 6 and the wet well 7. It flows into the condensation tank 22. A part of this steam is finally cooled by air and condensed through an air cooling system 23 connected to the condensation tank 22 as in the first embodiment.

  Most of the steam that has not been condensed in the condensation tank 22 is condensed by exchanging heat with the cooling pool 8 via the static containment vessel cooling facility heat exchanger 47. The condensed water flows into the wet well 7 through the storage container return pipe 48 by gravity. Gases such as uncondensed vapor and non-condensable gas also flow into the wet well 7 through the containment return pipe 48.

  Pool water in the cooling pool 8 heated by steam through the static containment vessel cooling equipment heat exchanger 47 boils and evaporates. For this reason, as in the first embodiment, this cooling system can utilize boiling heat transfer of water having a large heat transfer coefficient, and can remove large decay heat immediately after the reactor is shut down. After that, as in the first embodiment, the pool water in the cooling pool 8 is depleted, and the operation of the cooling system by the cooling pool 8 is substantially stopped, but collapsed by the air cooling system 23 that has no operating time restriction. Remove heat.

  As described above, according to the second embodiment of the reactor cooling system of the present invention, when the steam in the reactor pressure vessel 4 is released into the dry wells 5 and 6, the reactor containment vessel 2 Since the steam extracted from the air is first cooled by air through the air cooling system 23 and then cooled by the cooling pool 8 through the static containment vessel cooling equipment heat exchanger (heat exchanger) 47, It operates without a power source, can remove decay heat immediately after the reactor shutdown, and is not limited in operation time.

[Third Embodiment]
Next, a third embodiment of the reactor cooling system of the present invention will be described with reference to FIG. FIG. 3 is a schematic configuration diagram showing a boiling water nuclear reactor to which the third embodiment of the reactor cooling system of the present invention is applied. In FIG. 3, the same reference numerals as those shown in FIGS. 1 and 2 are the same parts, and detailed description thereof is omitted.

  The third embodiment of the reactor cooling system of the present invention shown in FIG. 3 is a combination of the first embodiment and the second embodiment.

  According to the third embodiment of the reactor cooling system of the present invention described above, the reactor pressure is provided because the cooling system in which the first embodiment and the second embodiment coexist is provided. Both the case where the steam in the vessel 4 is cooled and the case where the steam released into the reactor containment vessel 2 is cooled can be dealt with.

[Others]
In addition, although the example applied to the boiling water reactor was shown in 1st Embodiment mentioned above, it is applicable also to a pressurized water reactor (PWR (Pressurized Water Reactor)). A first embodiment applied to a pressurized water reactor will be described with reference to FIGS.
FIG. 4 is a schematic configuration diagram showing an example of a pressurized water reactor to which the first embodiment of the reactor cooling system of the present invention is applied, and FIG. 5 shows the first embodiment of the reactor cooling system of the present invention. It is a schematic block diagram which shows the other example of the applied pressurized water reactor. 4 and FIG. 5, the same reference numerals as those shown in FIG. 1 to FIG. 3 are the same parts, and detailed description thereof will be omitted.

  In FIG. 4, a steam generator 15 and a reactor pressure vessel 4 containing a reactor core 3 are installed in a reactor containment vessel 2 of a pressurized water reactor. The steam generator 15 is connected to the reactor pressure vessel 4. A cooling pool 8 is installed in the reactor containment vessel 2. The cooling pool 8 is installed at a position higher than the normal water level 15 a of the cooling water of the steam generator 15.

  When this embodiment is applied to a pressurized water reactor, the reactor steam supply pipe 21 is connected not to the reactor pressure vessel 4 but above the normal water level 15a of the cooling water of the steam generator 15. Further, the condensed water return pipe 28 is connected not to the reactor pressure vessel 4 but to the steam generator 15.

  In this case, the pool water in the cooling pool 8 exchanges heat with the steam generated in the steam generator 15 via the emergency condenser heat exchanger 27 and is discharged into the reactor containment vessel 2 as steam. For this reason, the pressure in the reactor containment vessel 2 rises. Therefore, the reactor containment vessel 2 is made of steel, and the outer surface of the containment vessel 2 is cooled from the outside by equipment to condense the steam released into the reactor containment vessel 2. At this time, part of this condensed water can be returned to the cooling pool 8, so that the amount of water in the cooling pool 8 can be saved.

  Further, as shown in FIG. 5, the cooling pool 8 can be installed outside the reactor containment vessel 2. In this case, since the steam generated in the cooling pool 8 is released to the outside, the steam generated in the cooling pool 8 is cooled by special equipment as in the case where the cooling pool 8 is installed inside the reactor containment vessel 2. There is no need to do. Therefore, compared with the case where the cooling pool 8 is installed inside the reactor containment vessel 2, the equipment can be simplified.

  In the first to third embodiments described above, an example in which the heat transport loop 26 is configured by the pipe 26a and the pipe 26b has been described, but a heat transport loop using a double pipe or the like is shown. It can also be set as the structure which put all into one.

  In the first to third embodiments described above, water or an alternative chlorofluorocarbon is shown as an example of the refrigerant of the air cooling system 23. However, the temperature condition during operation of the air cooling system 23 is used as the refrigerant. Those that boil and condense within the range can be used.

  In the first to third embodiments described above, the example in which the internal heat exchanger 24 and the external heat exchanger 25 are installed vertically is shown, but these are installed horizontally. You can also.

  In the first to third embodiments described above, a partition plate or the like can be placed in the condensation tank 22 in order to control / suppress the flow of steam.

  In the first to third embodiments described above, the example in which the condensation tank 22 is installed in the cooling pool 8 has been described. However, if there is no problem in arrangement, the condensation tank 22 is cooled. It can also be installed outside the pool 8.

  In the first to third embodiments described above, an example in which the cooling pool 8 shown in FIGS. 1 to 3 is installed in the reactor building 1 is shown. It can also be installed outside the reactor building 1.

  In the above-described first embodiment, an example in which the start valve 29 is installed on the condensed water return pipe 28 has been shown. However, the start valve 29 is not limited to the steam / cooling system in the cooling system during normal operation of the nuclear reactor. As long as the flow of the condensed water can be blocked, the start valve 29 can be installed at any position on the loop of the reactor cooling system. For example, the start valve 29 (start valve 29 indicated by a two-dot chain line in FIG. 1) can be installed on the reactor steam supply pipe 21. Furthermore, the activation failure of the activation valve 29 can be prevented by installing a plurality of activation valves 29 in parallel.

  Further, in the first embodiment described above, an example in which the reactor steam supply pipe 21 is connected to the reactor pressure vessel 4 is shown, but steam is supplied from the reactor pressure vessel 4 to a turbine (not shown). It can also be connected to a main steam pipe (not shown).

  In the above-described second embodiment, an example in which the containment vessel return pipe 48 is connected to the wet well 7 has been described. However, the containment vessel return pipe 48 is connected to the lower dry well 6 of the reactor containment vessel 2. You can also.

  In the above-described second embodiment, an example is shown in which one storage container return pipe 48 is installed. However, two storage container return pipes may be installed separately for condensed water and for gas. it can.

  The present invention is not limited to the modifications of the first to third embodiments described above, and includes various modifications. The above-described embodiment has been described in detail for easy understanding of the present invention, and is not necessarily limited to the one having all the configurations described. For example, part of the configuration of one embodiment can be replaced with the configuration of another embodiment, and the configuration of another embodiment can be added to the configuration of one embodiment. Moreover, it is also possible to add, delete, or replace another configuration for a part of the configuration of each embodiment.

  Moreover, in an actual nuclear reactor facility, an isolation valve is provided at a portion penetrating the reactor containment vessel 2, an inspection stop valve is provided on the system, and condensed water excessively accumulated during normal operation is discharged above the heat exchanger. A water discharge pipe, a gas discharge pipe for discharging non-condensable gas, and the like are installed, but these are not shown in the first to third embodiments described above. In addition, the performance of the safety system is usually designed with a margin, but in this specification, these margins are described on the assumption that they will be examined separately.

2 Reactor containment vessel 4 Reactor pressure vessel 8 Cooling pool 15 Steam generator 21 Reactor steam supply piping (steam supply piping)
22 Condensation tank 23 Air cooling system 24 Internal heat exchanger 25 External heat exchanger 26 Heat transport loop 27 Emergency condenser heat exchanger (heat exchanger)
28 Condensate return pipe (return pipe)
29 Start valve 41 PCV steam supply piping (steam supply piping)
47 Static containment vessel cooling equipment heat exchanger (heat exchanger)
48 containment return pipe (return pipe)

Claims (9)

A reactor containment vessel, a reactor pressure vessel or steam generator installed in the reactor containment vessel, and a cooling pool installed at a position higher than the normal water level of cooling water in the reactor pressure vessel or the steam generator A reactor cooling system comprising:
A steam supply pipe for extracting steam from the reactor pressure vessel, the steam generator, or the reactor containment vessel;
A condensing tank connected to the downstream side of the steam supply pipe;
A heat exchanger connected to the downstream side of the condensation tank and installed in the cooling pool;
A return pipe having one end connected to the downstream side of the heat exchanger and the other end connected to the reactor pressure vessel, the steam generator, or the reactor containment vessel;
A reactor cooling system comprising an internal heat exchanger installed inside the condensation tank, and an air cooling system for cooling the internal heat exchanger with air. The reactor cooling system according to claim 1,
The nuclear reactor cooling system, wherein the nuclear reactor is a boiling water reactor including the nuclear reactor pressure vessel. The reactor cooling system according to claim 1,
The nuclear reactor includes the steam generator,
The steam generator is a pressurized water reactor connected to a reactor pressure vessel. The reactor cooling system according to claim 2,
The steam supply pipe is a reactor steam supply pipe for extracting steam from the reactor pressure vessel,
The heat exchanger is an emergency condenser heat exchanger connected to the downstream side of the condensing tank and installed in the cooling pool,
The reactor cooling system, wherein the return pipe is a condensed water return pipe having one end connected to the downstream side of the emergency condenser heat exchanger and the other end connected to the reactor pressure vessel. . The reactor cooling system according to claim 2,
The steam supply pipe is a containment vessel steam supply pipe for extracting steam from the reactor containment vessel,
The heat exchanger is a static containment vessel cooling equipment heat exchanger connected to the downstream side of the condensation tank and installed in the cooling pool,
The return pipe is a containment vessel return pipe having one end connected to the downstream side of the static containment vessel cooling equipment heat exchanger and the other end connected to the inside of the reactor containment vessel. Cooling system. The reactor cooling system according to claim 2,
A reactor cooling system comprising both the reactor cooling system according to claim 4 and the reactor cooling system 5 according to claim 5. The reactor cooling system according to claim 3, wherein
The steam supply pipe is a reactor steam supply pipe for extracting steam from the steam generator,
The heat exchanger is an emergency condenser heat exchanger connected to the downstream side of the condensing tank and installed in the cooling pool;
The reactor cooling system, wherein the return pipe is a condensed water return pipe having one end connected to the downstream side of the emergency condenser heat exchanger and the other end connected to the steam generator. The reactor cooling system according to any one of claims 1 to 7,
The air cooling system includes a closed loop including the internal heat exchanger, an external heat exchanger installed outside the reactor containment vessel, and a heat transport loop connecting the internal heat exchanger and the external heat exchanger. Consists of
A reactor cooling system, wherein a refrigerant is enclosed in the closed loop. The reactor cooling system according to any one of claims 4, 6 and 7,
A reactor cooling system, wherein an activation valve is installed in at least one of the reactor steam supply pipe and the condensed water return pipe.

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