JPH08201559A - Cooling equipment of reactor container - Google Patents

Abstract

PURPOSE: To obtain cooling equipment of a reactor container of which the center of gravity is low and the cooling effect is excellent, by lowering the position of a cooling water pool of a static container cooling system in the case when the static container cooling system is combined with an emergency core cooling system operated by a dynamic pump and others in a nuclear power plant. CONSTITUTION: In an emergency core cooling system wherein cooling water for emergency is injected into a reactor pressure vessel 1 by a core cooling pump 7 with a suppression pool 5 used as a water source, in regard to cooling equipment of a reactor container, a cooling water pool 21 wherein a heat exchanger 12 is held is provided in the circumference of the suppression pool 5 outside the reactor container 2. Besides, a dry well 3 and the heat exchanger 12 are connected by a steam supply pipe 14, while the heat exchanger is connected with the suppression pool 5 by an exhaust pipe 22 and a condensed water return piping 23, and the position of the heat exchanger 12 is set to be above an ordinary water level 5a of the suppression pool.

Description

Detailed Description of the Invention

[0001]

BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to the containment of a nuclear reactor containing a nuclear reactor and the containment of the nuclear reactor by releasing decay heat into a cooling water pool outside the primary containment in case of emergency such as pipe breakage. The present invention relates to a cooling device for a reactor containment vessel that cools the vessel.

[0002]

2. Description of the Related Art In a conventional nuclear power plant, as shown in the sectional view of FIG. 11, in order to suppress the release of radioactive substances into the atmosphere at the time of a coolant loss accident, a reactor pressure vessel 1 A reactor containment vessel 2 is provided so as to surround the.

This reactor containment vessel 2 has a dry well 3 surrounding the reactor pressure vessel 1, a mixture of steam and water released into the dry well 3 at the time of a coolant loss accident, and a pressure suppression vent pipe 4. The suppression chamber 6 that suppresses an excessive rise in the pressure inside the reactor containment vessel 2 by cooling and condensing with the suppression pool water that is the emergency cooling water stored in the suppression pool 5 via the
It is composed of

Further, for example, by using the suppression pool 5 as one cooling water source for the emergency cooling water and activating the core cooling pump 7 of the emergency core cooling system, the suppression pool water for the emergency cooling water is supplied to the injection pipe 8. The core is cooled by injecting water into the reactor pressure vessel 1 via the via.

Regarding the cooling of the reactor containment vessel 2, for example, the suppression pool water in the suppression pool 5 is forcedly circulated in a loop of a cooling system including a heat exchanger (not shown) using a circulation pump, The containment vessel 2 is cooled by cooling the suppression pool water. On the other hand, as a nuclear reactor that has been recently studied, a system that removes decay heat without using dynamic equipment such as a core cooling pump in the event of an accident, for example, a static containment cooling system for a next-generation boiling water reactor There is.

In this system, as shown in the sectional view of FIG. 12, a cooling water chamber 9 is installed at a position higher than the core in the reactor containment vessel 2, and the cooling water in this cooling water chamber 9 is provided in the event of a coolant loss accident. Using the gravity as the final driving force,
The emergency core cooling system is characterized by injecting and replenishing into the reactor pressure vessel 1 via 10. In a reactor having such a gravity drop water injection system, the static containment cooling system cools the steam in the dry well 3 in the heat exchanger 12 contained in the cooling water pool 11 outside the reactor containment vessel 2. To do.

In the steam chamber 13 at the entrance of the heat exchanger 12,
A steam supply pipe 14 for supplying steam from the dry well 3 is connected, and a condensed water return pipe 16 for returning condensed water to a cooling water chamber 9 of the emergency cooling system is provided in a water chamber 15 at the outlet of the heat exchanger.
And an exhaust pipe 18 connected to the suppression pool 5 for exhausting the non-condensable gas accumulated in the heat transfer pipe 17 of the heat exchanger 12.

Further, the heat exchanger for cooling the static containment vessel
The cooling water pool 11 containing 12 is in contact with the reactor containment vessel 2 in order to return the condensed water generated in the heat exchanger 12 to the reactor pressure vessel 1 by gravity and finally to the reactor pressure vessel 1. Is installed above. The initial temperature of the pool water in the cooling water pool 11 is room temperature. The steam generated in the reactor due to the decay heat at the time of the accident of the reactor is, for example, the dry well 3 via the broken main steam pipe 19 or the pressure reducing valve 20 for discharging the steam in the reactor pressure vessel 1 to the dry well 3. Is released into.

The steam discharged into the dry well 3 is guided to the heat exchanger 12 contained in the cooling pool 11 outside the reactor containment vessel 2 via the steam supply pipe 14, and the steam exchanges heat. The condensed water, which is cooled by the pool water through the wall of the heat transfer tube 17 while passing through the inside of the vessel 12, and is generated by the condensation of this steam, reaches the cooling water chamber 9 through the condensed water return pipe 16 by gravity, Finally, it is returned to the reactor pressure vessel 1.

Further, at the same time when the steam flows into the heat exchanger 12, the non-condensable gas existing in the dry well 3 also mixes into the heat exchanger 12, and this non-condensable gas is exchanged with the heat exchanger 12.
To deteriorate the heat transfer function of the heat exchanger 12,
It is discharged into the suppression pool water of the suppression pool 5 via the exhaust pipe 18.

As described above, in the static containment cooling system, the pressure of the dry well 3 rises due to the outflow of the coolant due to the steam through the broken pipe when the pipe breaks. Since the decay heat removal starts automatically after flowing into 12, it is not necessary to operate a valve or the like, and high reliability can be expected regarding its operation.

[0012]

Since a static containment cooling system can be expected to have high reliability in its operation, a nuclear power plant using a conventional dynamic pump or the like in an emergency core cooling system will be used as a future nuclear power plant. It is being considered for use in plants. However, the concept of a future nuclear power plant that combines a static design cooling system with a nuclear power plant that uses a conventionally designed dynamic pump or the like for an emergency core cooling system has not been clarified.

Further, the conventional static containment cooling system has the following problems in terms of structure and cooling function of the reactor containment vessel 2 at the time of an accident. That is, in principle, the cooling water pool 9 of the static containment cooling system needs to be installed above the reactor containment vessel 2.

Further, as the reactor power increases, the cooling water pool 9 required to remove decay heat
Since the volume of the space is also large, the position of the center of gravity is at the top, which hinders the seismic design.

From the viewpoint of plant layout,
Since the installation location of the fuel storage pool (not shown) is arranged on the outer periphery of the cooling water pool 9 of the static containment cooling system, as the cooling water pool 9 becomes larger, the fuel storage pool becomes Since it is separated from directly above the container 1, the distance for moving the fuel during the fuel exchange increases, and the time required for the fuel exchange increases.

Furthermore, since the static containment cooling system is a system for cooling the dry well 3 in the reactor containment vessel 2, it has the ability to suppress the rise of the pressure in the dry well 3 and maintain it at a constant value. The pressure in the dry well 3 could not be positively reduced unless the pressure in the suppression chamber 6 was reduced.

When the static containment cooling system is simply combined with the conventional emergency core cooling system using the suppression pool 5 as one water source, when the accident occurs, the reactor using the emergency core cooling system As the water injection into the pressure vessel 1 progresses, the water level of the suppression pool 5 may decrease, and the lower end of the exhaust pipe 18 of the static containment vessel cooling system may be exposed from the suppression pool 5 to the space of the suppression chamber 6. .

At that time, in the worst case, the steam not completely condensed in the heat exchanger 12 of the static containment cooling system is
Since it directly flows into the space of the suppression chamber 6, the pressure in the suppression chamber 6 may continue to rise. In addition, when the reactor containment vessel 2 is cooled by the static containment vessel cooling system for a long period of time, there is a problem that the cooling water pool 9 must be enlarged.

The object of the present invention is to provide a cooling water for a static containment cooling system when the static containment cooling system is combined with an emergency core cooling system using a dynamic pump or the like in a nuclear power plant. (EN) It is an object to provide a cooling device for a reactor containment vessel which has a low center of gravity and has a good cooling effect by setting the pool position low.

[0020]

In order to achieve the above object, the cooling device for a reactor containment vessel according to the invention of claim 1 has at least one suppression pool for storing emergency cooling water in the reactor containment vessel. In the emergency core cooling system, which pumps emergency cooling water into the reactor pressure vessel in the event of a loss of reactor coolant as one water source, steam installed around the suppression pool outside the reactor containment vessel. Cooling water pool containing a heat exchanger consisting of a chamber, a heat transfer tube and a water chamber, a dry well in the reactor containment vessel and a steam chamber of the heat exchanger are connected by a steam supply pipe to form condensed water. A return pipe connects the bottom of the water chamber to the suppression pool, connects the water chamber space to the suppression pool in the reactor containment vessel with an exhaust pipe, and cools the heat exchanger. The installation position in the water pool, characterized in that it has above the normal water level of said suppression pool.

A reactor containment vessel cooling apparatus according to a second aspect of the present invention is the reactor containment vessel cooling apparatus, wherein the pressure suppression vent pipe is provided in a wet well formed at a lower portion of the dry well during vapor discharge. While branching the communicating return pipe, the water depth in the suppression pool of the condensed water return pipe is the same as or deeper than the water depth in the suppression pool of the exhaust pipe, and the suppression pool from the exhaust pipe outlet height. The volume of cooling water up to the initial water surface of the volume from the bottom of the wet well to the return pipe height of the pressure suppression vent pipe and the steam space volume above the normal operating water level and above the normal operating water level in the reactor pressure vessel It is characterized in that the volume is made larger than the volume including the vapor space volume.

According to a third aspect of the present invention, there is provided a reactor containment vessel cooling apparatus in which the suppression pool is divided into a plurality of pools by partition walls, and each divided pool is located above the water surface. It is characterized in that they are connected to each other in the suppression chamber space and that the condensed water return pipe and the exhaust pipe and the cooling water injection pipe of the emergency core cooling system are connected to another divided pool.

A cooling device for a reactor containment vessel according to a fourth aspect of the present invention is the cooling device for a reactor containment vessel, wherein the reactor containment vessel is made of steel and the cooling water pool is divided into a plurality of regions by partition walls. Divide each divided cooling water pool into one containing heat exchanger and one not containing heat exchanger,
The split cooling water pool containing the heat exchanger is thermally isolated from the wall of the reactor containment vessel and the split cooling water pool not containing the heat exchanger, and the split cooling water does not contain the heat exchanger. The water pool exchanges heat with the suppression pool and the suppression chamber via the wall of the reactor containment vessel.

According to a fifth aspect of the present invention, there is provided a cooling device for a reactor containment vessel, wherein a partition wall for thermally isolating a divided cooling water pool in the cooling device for the reactor containment vessel is a heat insulating material. To do. According to a sixth aspect of the present invention, there is provided a cooling device for a reactor containment vessel, wherein a partition wall for thermally isolating a divided cooling water pool in the cooling device for the reactor containment vessel is formed by vacuum layer heat insulation.

According to a seventh aspect of the present invention, there is provided a cooling device for a reactor containment vessel, wherein in the cooling device for a reactor containment vessel, a steam chamber, a heat transfer tube, and a water chamber are provided around the suppression pool outside the reactor containment vessel. A second cooling water pool accommodating the second heat exchanger is installed, and the steam chamber of the second heat exchanger is connected to the suppression pool by the upper pipe and the water chamber is connected by the lower pipe to the suppression pool. The connection position is connected to the outlet height of the pressure suppression vent pipe, and the lower pipe is connected to the bottom of the suppression pool.

According to an eighth aspect of the present invention, there is provided a cooling device for a reactor containment vessel, wherein in the cooling device for a reactor containment vessel, a second heat exchanger installed outside the reactor containment vessel around the suppression pool comprises: It is characterized by being air-cooled. In the cooling device for a reactor containment vessel according to the invention of claim 9, in the cooling device for a reactor containment vessel, the second heat exchanger installed around the suppression pool outside the reactor containment vessel is air-cooled. In addition, it is characterized by being installed in the cooling tower.

According to a tenth aspect of the present invention, there is provided a cooling apparatus for a reactor containment vessel, wherein the cooling water pool installed around the suppression pool outside the reactor containment vessel has a wall surface. It is characterized by being made of a steel plate and forming an air flow path between the cooling water pool wall surface and the reactor containment vessel.

[0028]

According to the first aspect of the present invention, in the emergency core cooling system which is dynamic by operating the core cooling pump at the time of loss of coolant, the emergency cooling water which is the suppression pool water of the suppression pool is supplied to the reactor pressure vessel. To cool the core.

Further, the heat exchanger in the cooling water pool of the static containment vessel cooling system sucks the steam flowing out into the dry well, cools and condenses it, and then flows it down to the suppression pool by gravity. The water is cooled to cool the reactor pressure vessel and the reactor containment vessel. In addition, since the cooling water pool is installed at a low position, the center of gravity of the reactor containment vessel will be lowered, improving seismic resistance, and the plant layout such as the position of the fuel pool installed above the reactor pressure vessel will be appropriate. You can do it.

According to the second aspect of the present invention, in the emergency core cooling system, when the emergency cooling water of the suppression pool water is injected from the suppression pool into the reactor pressure vessel for core cooling, the suppression pool water level is lowered. To do.

However, the outlet end of the exhaust pipe connecting the heat exchanger and the suppression pool in the static containment cooling system has more suppression than the volume of the cooling water evaporated or stored in the reactor pressure vessel and the reactor containment vessel. It is installed in a position that secures the volume of suppression pool water in the pool. As a result, the uncondensed vapor and the non-condensable gas from the heat exchanger do not directly flow into the suppression chamber and continue to increase the temperature of the reactor containment vessel.

According to a third aspect of the present invention, the pool which is the source of the emergency cooling water for the dynamic emergency core cooling system and the pool for storing the condensed water in the static containment cooling system are divided by partition walls in the suppression pool. ing.

As a result, during the cooling treatment of the non-condensable gas in the static containment cooling system, the driving of the static containment cooling system is performed due to the decrease in the water level associated with the reduction of the storage amount of the emergency cooling water in the emergency core cooling system. A force, a pressure difference between the drywell and the suppression chamber is secured. Further, the uncondensable vapor and the non-condensable gas from the heat exchanger do not directly flow into the suppression chamber and continue to increase the temperature of the reactor containment vessel, which may deteriorate the cooling function of the reactor containment vessel. Absent.

According to a fourth aspect of the present invention, a steel reactor containment vessel having good heat transfer is provided, and a cooling water pool of a static containment vessel cooling system is closely installed at an outer peripheral position of the suppression pool. The cooling water pool is divided by a heat insulating partition to accommodate the heat exchanger in the cooling water pool farther from the steel reactor containment vessel.

As a result, the steel reactor containment vessel exchanges heat with the cooling water pool in contact with the wall to cool the suppression pool and suppression chamber. Also,
In a cooling water pool containing heat exchangers with adiabatic partition walls sandwiched between them, the pressure rise of the dry well as a static containment vessel cooling system is suppressed.

According to the fifth aspect of the present invention, since the partition wall for dividing the cooling water pool in the static containment cooling system is filled with the heat insulating material, mutual division of the cooling water pool water and thermal isolation are easy. You can do it. According to the sixth aspect of the invention, since the vacuum layer is formed on the partition wall that divides the cooling water pool in the static containment cooling system, mutual cooling water pool water separation and thermal isolation can be easily performed.

According to a seventh aspect of the present invention, a second cooling water pool accommodating a second heat exchanger is installed as a static containment vessel cooling system on the outer circumference of the suppression chamber.
Since the suppression pool is cooled by the cooling water pool, cooling can be performed without enlarging the reactor containment vessel. Further, since the cooling water pool is installed on the outer periphery of the reactor containment vessel, the center of gravity is lowered and the earthquake resistance is improved.

According to an eighth aspect of the present invention, the second heat exchanger is installed as a static containment cooling system in the atmosphere around the reactor containment vessel, and the suppression pool is cooled by air cooling. Therefore, the structure is simple and the maintenance is easy. In the invention according to claim 9, since the second heat exchanger by air cooling is installed in the cooling tower in the static containment cooling system, natural ventilation by the atmosphere is further promoted, and the suppression pool is effectively heat-exchanged. Can be cooled.

According to a tenth aspect of the invention, the wall surface of the cooling water pool installed on the outer periphery of the reactor containment vessel in the static containment cooling system is made of a steel plate with good heat transfer, and An air flow path is formed between the reactor containment vessel. As a result, the cooling water pool is positively cooled by the atmosphere flowing in the air flow path, so that the cooling efficiency of the suppression pool by the static containment cooling system is improved and the evaporation of the cooling water is reduced to reduce the cooling water. The expiration date of the pool can be extended.

[0040]

DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS An embodiment of the present invention will be described with reference to the drawings. It should be noted that the same components as those of the above-described conventional technique are denoted by the same reference numerals and detailed description thereof will be omitted. In the first embodiment, as shown in the sectional view of FIG. 1, a reactor containment vessel 2 is provided so as to surround a reactor pressure vessel 1.

In the reactor containment vessel 2, a dry well 3 around the reactor pressure vessel 1 and a mixture of steam and water released into the dry well 3 at the time of the loss of coolant are placed in a pressure suppression vent pipe 4. A suppression chamber 6 that suppresses an excessive increase in the pressure inside the reactor containment vessel 2 is formed by cooling the cooling water with the suppression pool water in the suppression pool 5 and condensing it.

The suppression pool 5 and the reactor pressure vessel 1 are connected by a core cooling pump 7 and a water injection pipe 8 to form an emergency core cooling system such as a dynamic pump. By activating 7,
Suppression pool water, which is the emergency cooling water for the suppression pool 5, is injected into the reactor pressure vessel 1 via the water injection pipe 8 to cool the reactor core.

Further, on the outer peripheral portion of the suppression chamber 6, there is provided an evaporation chamber 13 and a heat transfer tube 17 as a static containment vessel cooling system.
A heat exchanger 12 including a water chamber 15 and a water chamber 15 is housed, and a cooling water pool 21 open to the atmosphere is provided.

The heat exchanger 12 has a normal water level 5a of the suppression pool water in the suppression pool 5.
Installed at a higher position, the evaporation chamber 13 of the heat exchanger 12 is connected to the dry well 3 by a steam supply pipe 14, the upper part of the water chamber 15 is an exhaust pipe 22, and the lower part is a condensed water return pipe. It is configured to be connected to the suppression pool 5 by 23.

Next, the operation of the above configuration will be described. For example, assuming a case where a breakage accident occurs in the main steam pipe 19, the pressure of the dry well 3 increases due to the steam flowing from the reactor pressure vessel 1 to the dry well 3 of the reactor containment vessel 2. The pressure difference between the well 3 and the suspension chamber 6 serves as a driving force, and the steam existing in the dry well 3 enters the cooling water pool 21 via the steam supply pipe 14 of the static containment vessel cooling system. It flows into the contained heat exchanger 12.

The steam flowing into the heat exchanger 12 exchanges heat with the cooling water pool 21 and is cooled and condensed in the heat transfer tube 17, but the heat exchanger 12 causes the normal water level 5 of the suppression pool 5 to rise.
Since it is installed above a, the condensed water flows into the suppression pool 5 through the condensed water pipe 23 due to gravity.

The non-condensable gas, which was sealed in the dry well 3 at the beginning of operation to prevent fire, flows into the heat exchanger 12 together with the steam flowing into the dry well 3, but this non-condensable gas is exhausted. It flows into the suppression chamber 6 via the pipe 22 and the suppression pool 5.

Next, the core cooling pump 7 for the emergency core cooling system
Since the suppression pool water of the suppression pool 5 is injected into the reactor pressure vessel 1 with the start of
Condensed water from the static containment cooling system is also finally returned to the reactor pressure vessel 1. As a result, the vapor of the dry well 3 generated in the reactor pressure vessel 1 by the decay heat is cooled by the static containment vessel cooling system and forms a loop that returns to the reactor pressure vessel 1.

Therefore, according to this first embodiment, the cooling water pool 21 is provided in the reactor containment vessel 2 in the static containment vessel cooling system.
Since it is not necessary to install the cooling water pool 21 around the suppression pool 5, the center of gravity of the reactor containment vessel 2 is lowered and the earthquake resistance is improved.

Further, since the cooling water pool 21 is not installed above the reactor containment vessel 2, it becomes possible to install a fuel storage pool (not shown) directly above the reactor pressure vessel 1, and at the time of fuel loading work. The distance traveled by the fuel is short,
It is possible to solve problems in plant layout, such as improving work efficiency and reducing exposure of workers.

In the second embodiment, as shown in the sectional view of FIG.
In the pressure suppression vent pipe 4 connecting the dry well 3 and the suppression pool 5 of the suppression chamber 6, the lower part of the dry well 3 where the steam and the coolant discharged from the reactor pressure vessel 1 to the dry well 3 are stored. A return pipe 25 connecting to the dry well 24 is branched.

The cooling water pool for the static containment vessel cooling system
The heat exchanger 12 housed in 21 has a normal water level 5 of the suppression pool water in the suppression pool 5.
It is installed at a position higher than a. Further, the outlet end of the exhaust pipe 22 connected to the water chamber 15 opened in the suppression pool 5 is located below the normal water level 5a of the suppression pool water.

This is because the volume a of the steam space portion above the normal operating water level 26 in the reactor pressure vessel 1 and the volume b of the steam space portion below the normal operating water level 26 in the core and the upper plenum, And the position below the dry well 3 to obtain a volume larger than the volume obtained by adding the volume c of the wet well 24 from the bottom to the height of the return pipe 25, the other configurations being the same as those of the first embodiment. Is.

The operation of the above configuration is that, when a coolant loss accident occurs, the emergency core cooling system using the suppression pool 5 as one water source activates the core cooling pump 7 and uses the water injection pipe 8 to supply water to the suppression pool 5. Suppression pool water is poured into the reactor pressure vessel 1 to cool the core.

The steam flowing out from the damaged portion into the dry well 3 of the reactor containment vessel 2 due to the occurrence of the accident and the subsequent decay heat passes through the suppression pool 5 from the heat exchanger 12 of the static containment vessel cooling system. The steam and the coolant that have been returned to the reactor pressure vessel 1 and condensed in the dry well 3 are stored in the wet well 24 below the dry well 3. Here, when the injection of water into the reactor pressure vessel 1 using the suppression pool 5 by the emergency core cooling system as a water source proceeds,
The water level of the suppression pool water in the suppression pool 5 decreases.

At this time, if the outlet end of the exhaust pipe 22 connected to the heat exchanger 12 of the static containment cooling system is exposed in the space of the suppression chamber 6,
The non-condensable vapor flows directly into the suppression chamber 6 together with the non-condensable gas, the pressure inside the suppression chamber 6 rises, and this continues.

However, in the second embodiment, the maximum volume of the suppression pool water reduced by this water injection is the sum of the volume a and the volume b in the reactor pressure vessel 1 and the volume c in the wet well 24. A volume d shown by a larger diagonal line is secured.

As a result, even if water is injected into the reactor by the emergency core cooling system, the exhaust pipe of the static containment cooling system is
The outlet end of 22 is not exposed to the space of the dry well 3, and uncondensed vapor and non-condensable gas from the static containment cooling system directly flow into the space of the suppression chamber 6 to generate pressure. The rise and the continuation of it will be prevented.

In the wet well 24, when the water level 24a of the stored water reaches or exceeds the position of the return pipe 25, it flows into the suppression pool 5 via the return pipe 25 and is returned to the reactor pressure vessel 1. .

The third embodiment is a sectional view of FIG.
As shown in the schematic view taken along the line AA in (a) of (b),
Suppression chamber 6 provided in the reactor containment vessel 2
An annular suppression pool partition wall 27 is provided inside, and the suppression pool 5 is concentrically divided into an inner pool 28a and an outer pool 28b.

The height of the suppression pool partition wall 27 that divides the suppression pool 5 is such that the suppression pool 5 has a normal water level of 5 from the bottom of the suppression pool 5.
Both pool waters are separated from each other by a position higher than a, but the space portion of the suppression chamber 6 is not separated.

The cooling water pool for the static containment cooling system
Condensed water return pipe 23 of heat exchanger 12 housed in 21 and exhaust pipe 22
Is connected to the outer pool 28b, while the water injection pipe 8 of the emergency core cooling system is connected to the inner pool 28a. The heat exchanger 12 is installed at a position higher than the water level of the outer pool 28b in the suppression pool 5. Further, the other configurations are similar to those of the first embodiment.

The operation of the above configuration is as follows. When water is injected into the reactor pressure vessel 1 by the emergency core cooling system during a loss of coolant accident, the water level in the inner pool 28a decreases, but the water level in the outer pool 28b decreases. It is not affected and remains constant. Therefore, the heat exchanger in the static containment cooling system
The outlet end of the exhaust pipe 22 from 12 is not exposed in the space of the suppression chamber 6.

As a result, due to the operation of the emergency core cooling system, the uncondensed vapor directly flows into the space portion of the suppression chamber 6 from the static containment cooling system, and the pressure inside the reactor containment vessel 2 rises. And no situation will continue.

Further, since the water depth to the exhaust pipe 22 is kept constant, the heat removal of the static containment vessel cooling system is stably performed. That is, the driving force of the static containment vessel cooling system is easily affected by the water level of the suppression pool 5 because the differential pressure between the dry well 3 and the suppression chamber 6 is the driving force, but the third embodiment According to the example the outer pool
Since the depth of the pool water to the exhaust pipe 22 in 28b is constant, a stable driving force is secured.

In the fourth embodiment, the reactor containment vessel 29 is made of steel, as shown in the sectional view of FIG. 4A and the schematic view taken along the line BB in FIG. The cooling water pool for the static containment vessel cooling system provided on the outer periphery of this steel reactor containment vessel 29.
The cooling water pool partition wall 31 divides the inside of the inside into concentric circles into an inner pool 32a and an outer pool 32b. In addition,
The height of the cooling water pool partition wall 31 is higher than the initial cooling water level 30a in the cooling water pool 30,
The cooling waters of 32a and the outer pool 32b are isolated from each other.

Two inner pools 32a and outer pool 32b
Are all open to the atmosphere, and cooling water pool partition walls
Thermally shut off by 31. The heat exchanger 12 of the static containment vessel cooling system is housed in the outer pool 32b and is installed at a position higher than the normal water level 5a of the suppression pool 5. Others are the same as those in the first embodiment.

The operation of the above configuration is that, in the event of a coolant loss accident, the steam in the dry well 3 reaches the heat exchanger 12 via the steam supply pipe 14 and transfers heat to the outer pool 32b, thereby condensing with cooling. Then, the condensed water flows into the suppression pool 5 through the condensed water return pipe 23 to cool the dry well 3. At the same time, the suppression chamber 6 and the suppression pool 5 are also efficiently cooled by passing heat through the side wall of the steel reactor containment vessel 29 to the inner pool 32a of the cooling water pool 30.

Normally, the temperature of the dry well 3 at this time is 400
The temperature of the suppression chamber 6 and the suppression pool 5 is about 350K. In addition, the outer pool 32b of the cooling water pool 30 transfers heat from the dry well 3 to the heat exchanger 12 to 373K in a few hours from the initial room temperature.
However, the outer pool 32b and the inner pool 32a are thermally insulated by the cooling water pool partition wall 31.

For this reason, heat transfer from the outer pool 32b to the inner pool 32a does not occur, and the inner pool 32a is maintained below the temperature of the suppression chamber 6 and the suppression pool 5, so that the inside of the suppression chamber 6 and the suppression pool 5 is maintained. Heat transfer to the pool 32a is maintained.

The fifth embodiment relates to the cooling water pool partition wall 31 provided in the fourth embodiment, and is a perspective view of FIG.
As shown in the sectional view of (b), a steel plate frame 33 is filled with a heat insulating material 34 such as glass wool. With this cooling water pool partition wall 31, the inside pool 32a and the outside pool 32 are
By partitioning b, mutual cooling water is blocked by the steel plate frame 33, and heat is not transferred by the heat insulating material 34, so that even if there is a temperature difference between the cooling water, there is no interference and no influence. .

The sixth embodiment relates to the cooling water pool partition wall 31 provided in the fourth embodiment, and is a perspective view of FIG. 6 (a) and FIG.
As shown in the sectional view of (b), a vacuum layer 35 is formed in the steel plate frame 33. By partitioning the inner pool 32a and the outer pool 32b by this cooling water pool partition wall 31, mutual cooling water is blocked by the steel plate frame 33, and
Since heat transfer is blocked in the vacuum layer 35, even if there is a temperature difference between the cooling waters, they do not interfere with each other and are not affected by each other.

In the seventh embodiment, as shown in the sectional view of FIG. 7, the second cooling water pool 36 is provided at the position of the suppression pool 5 installed in the reactor containment vessel 2 on the outer periphery of the reactor containment vessel 2. The second heat exchanger 37 is housed in the cooling water, and the upper part of the second heat exchanger 37 and the suppression pool 5 are connected by the upper pipe 38 and the lower part is connected by the lower pipe 39.

Suppression pool 5 of this upper pipe 38
The connection position to the pressure suppression vent pipe 4 outlet height,
The lower pipe 39 is configured to be connected to the bottom of the suppression pool 5, and the other configurations are the same as those in the first or second embodiment.

Next, the operation of the above configuration will be described. In the event of loss of coolant due to pipe breakage, etc., high-temperature steam flows into the suppression pool 5 from the drywell 3 via the pressure suppression vent pipe 4, so the temperature rise near the outlet of the pressure suppression vent pipe 4 in the suppression pool 5. Grows larger.

Suppression pool 5 with this temperature rise
The suppression pool water flows into the second heat exchanger 37 via the upper pipe 38, radiates heat to the cooling water in the second cooling pool 36 while passing through the second heat exchanger 37, and the temperature of Suppression pool 5 again after lowering through lower pipe 39
Reflux to. As a result, the suppression pool water in the suppression pool 5 can be automatically cooled by the natural environment without using power.

Therefore, according to the seventh embodiment, the cooling water pool 21 of the static containment cooling system sucks and cools the steam in the dry well 3 and cools the second well of the static containment cooling system. Since the suppression pool water of the suppression pool 5 is cooled by the cooling water pool 36, the reactor containment vessel 2 can be cooled efficiently and highly reliably without increasing the size of the reactor containment vessel 2.

In the eighth embodiment, as shown in the sectional view of FIG. 8, the second heat exchanger 37, which is a part of the static containment cooling system, is an air-cooled type, and the atmosphere at the outer periphery of the reactor containment vessel 2 The suppression pool 5 installed in the reactor containment vessel 2 is connected to the suppression pipe 5 by an upper pipe 38 and a lower pipe 39. The connection positions of the upper pipe 38 and the lower pipe 39 to the suppression pool 5 and the others are the same as those in the seventh embodiment.

The operation of the above construction is similar to that of the seventh embodiment, and in the event of loss of coolant due to pipe breakage or the like, high temperature steam from the drywell 3 via the pressure suppression vent pipe 4 enters the suppression pool 5. Because of the inflow, the temperature increase near the outlet of the pressure suppression vent pipe 5 becomes large. The pool water whose temperature has risen flows into the second heat exchanger 37 via the upper pipe 38, and while passing through the inside of the second heat exchanger 37, it radiates heat to the atmosphere and the temperature drops. After that, it is returned to the suppression pool 5 via the lower pipe 39.

In this way, the second heat exchanger 37 is cooled by the atmosphere, the suppression pool water in the suppression pool 5 is cooled, and the temperature rise of the reactor containment vessel 2 is suppressed. Further, the structure and maintenance can be simplified without the need for the second cooling water pool and the cooling water.

In the ninth embodiment, as shown in the sectional view of FIG. 9, the second heat exchanger 37, which is a part of the static containment cooling system, is of the air cooling type, and the atmosphere outside the reactor containment vessel 2 is the atmosphere. In addition to being installed inside, it is installed inside the cooling tower 40. Further, the second heat exchanger 37 is configured by connecting the suppression pool 5 provided in the reactor containment vessel 2 with an upper pipe 38 and a lower pipe 39. The rest of the configuration is similar to that of the seventh embodiment.

According to this construction, the atmosphere actively flows in the cooling tower 40 as shown by the arrow 41 without the need for a dynamic device such as a blower, so that the second heat exchanger 37 Cooling is promoted and the temperature rise of the reactor containment vessel 2 is suppressed. In the seventh to ninth embodiments described above, by using the heat exchanger 12 and the second heat exchanger 37 for cooling the reactor containment vessel 2, the reactor containment vessel 2 is not increased in size. Cooling of the reactor containment vessel 2 can be performed by a highly efficient and highly reliable static containment vessel cooling system.

Further, since the suppression pool cooling water in the suppression pool 5 is cooled by the second heat exchanger 37, the pressure in the suppression chamber 6 is kept low as compared with the case where the suppression pool 5 is not cooled. As a result, the differential pressure between the drywell 3 and the suppression chamber 6 becomes large, so that the heat exchanger
Exhaust from 12 to the suppression chamber 6 is promoted, and the accumulation of non-condensable gas in the heat exchanger 12 is reduced.
This has the effect of increasing the amount of heat removed by the static containment cooling system.

In the tenth embodiment, as shown in the sectional view of FIG. 10, the cooling water pool 21 is formed of a steel plate wall 42 having good heat transfer, and this cooling water pool 21 is connected to the reactor containment vessel wall 43. The air flow path 44 is formed with a space provided therebetween.

According to the above configuration, the pool water temperature of the cooling water pool 21 rises by cooling the steam discharged to the dry well 3 in the cooling water pool 21 at the time of the loss of coolant, but the atmosphere flow path 44 The atmosphere flowing inside as indicated by an arrow 41 radiates heat through the steel plate wall 42 of the cooling water pool 21 to efficiently cool the cooling water pool 21. This suppresses the temperature rise of the cooling water pool 21 and delays the decrease of the pool water in the cooling water pool 21 due to evaporation, so that the cooling water pool 21 can be easily maintained and the effective period can be extended. .

In the above-mentioned first embodiment, etc.,
Even if the exhaust pipe 22 connecting the water chamber 13 of the heat exchanger 12 and the suppression pool 5 in the static containment vessel cooling system and the condensed water return pipe 23 are combined into one pipe, substantially the same effect can be obtained.

Further, in the description of the third embodiment, the suppression pool 5 and the suppression chamber 6 are concentrically divided by the suppression pool partition wall 27, but the suppression fool 5 and the suppression chamber 6 are circumferentially divided. The water injection pipe 8 for the emergency core cooling system and the condensed water return pipe 23 for the static containment cooling system may be divided and connected to separate divided pools 28a and 28b, respectively.

Similarly, in the description of the fourth embodiment, the cooling water pool partition wall 31 divides the cooling water pool 30 of the static containment vessel cooling system into concentric circles, but this cooling water pool 30 is circumferentially divided. The cooling water pools 32a and 32b, which include the heat exchanger 12, and the steel containment vessel 29 may be used to cool the suppression pool 5 and the suppression chamber 6 as a divided cooling water pool.

[0089]

As described above, according to the present invention, by using the static containment cooling system in combination with the nuclear power plant using a dynamic pump or the like as the emergency core cooling system, the conventional static containment cooling system can be realized. Resolving the various problems that accompany it, cooling the reactor containment vessel appropriately, and further facilitating seismic resistance and plant layout, and efficiently cooling the reactor pressure vessel and reactor containment vessel in the event of a reactor accident. There is an effect that high reliability can be obtained.

[Brief description of drawings]

FIG. 1 is a structural cross-sectional view of a first embodiment according to the present invention.

FIG. 2 is a structural cross-sectional view of a second embodiment according to the present invention.

FIG. 3A is a sectional view showing the configuration of a third embodiment of the present invention, and FIG. 3B is a schematic view taken along the line AA of FIG.

FIG. 4A is a sectional view showing the configuration of a fourth embodiment of the present invention, and FIG. 4B is a schematic view taken along the line BB of FIG.

5A and 5B are perspective views and sectional views of a partition wall of a fifth embodiment according to the present invention.

FIG. 6 is a perspective view of a partition wall of a sixth embodiment according to the present invention, and FIG.

FIG. 7 is a structural cross-sectional view of a seventh embodiment according to the present invention.

FIG. 8 is a sectional view showing the configuration of an eighth embodiment according to the present invention.

FIG. 9 is a structural cross-sectional view of a ninth embodiment according to the present invention.

FIG. 10 is a structural sectional view of a tenth embodiment according to the present invention.

FIG. 11 is a cross-sectional view of the configuration of a conventional reactor containment vessel cooling device using an emergency core cooling system.

FIG. 12 is a cross-sectional view of the configuration of a conventional reactor containment vessel cooling device using a static containment cooling system.

[Explanation of symbols]

DESCRIPTION OF SYMBOLS 1 ... Reactor pressure vessel, 2 ... Reactor containment vessel, 3 ... Dry well, 4 ... Pressure suppression vent pipe, 5 ... Suppression pool, 5a ... Normal water level of suspension pool, 6 ... Suppression chamber, 7 ... Core cooling pump, 8 … Water injection pipe, 9… Gravity drop type water injection system pool, 10… Gravity drop water injection system pipe, 11, 21, 30… Cooling water pool, 12… Heat exchanger, 13
… Steam chamber, 14… Steam supply pipe, 15… Water chamber, 16, 23… Condensate return pipe, 17… Heat transfer pipe, 18, 22… Exhaust pipe, 19… Main steam pipe, 20… Pressure reducing valve, 24… Wet Well, a ... Volume of upper vapor space portion, b ... Volume of lower vapor space portion, c ... Volume of wet well, d ... Maximum volume of suppression pool water by water injection (a + b + c volume), 25 ... Return pipe, 26 ...
Normal operating water level, 27 ... Suppression pool bulkhead, 28a,
32a ... inner pool, 28b, 32b ... outer pool, 29 ... steel reactor containment vessel, 31 ... cooling water pool partition wall, 33 ... steel plate frame,
34 ... Insulation material, 35 ... Vacuum layer, 36 ... Second cooling water pool, 37 ...
Second heat exchanger, 38 ... upper piping, 39 ... lower piping, 40 ... cooling tower, 41 ... atmosphere flow (arrow), 42 ... cooling water pool steel wall, 43 ... reactor containment vessel wall, 44 ... Atmosphere flow path.

Continuation of the front page (51) Int.Cl. ⁶ Identification code Office reference number FI Technical display location G21C 15/18 PR

Claims (10)

[Claims] 1. The emergency cooling water is pumped into the reactor pressure vessel at the time of a coolant loss accident in the reactor by using at least one suppression pool for storing the emergency cooling water in the reactor containment vessel as a water source. In an emergency core cooling system, a cooling water pool open to the atmosphere containing a steam chamber installed around the suppression pool outside the reactor containment vessel, a heat exchanger consisting of a heat transfer tube and a water chamber, and the reactor containment The dry well in the vessel and the steam chamber of the heat exchanger are connected by a steam supply pipe to connect the water chamber bottom part and the suppression pool with a condensed water return pipe, and the water chamber space part and the reactor containment vessel The suppression pool is connected by an exhaust pipe, and the installation position of the heat exchanger in the cooling water pool is above the normal water level of the suppression pool. Cooling device for reactor containment vessel. 2. In a reactor containment vessel cooling device, a return pipe communicating with a wet well formed at the time of vapor release at the lower part of the dry well is branched to the pressure suppression vent pipe, and the condensed water return pipe is connected with the return pipe. The water depth in the suppression pool is the same as or deeper than the water depth in the suppression pool of the exhaust pipe, and the cooling water volume from the exhaust pipe outlet height to the initial water surface of the suppression pool is the bottom of the wet well. To the height of the return pipe of the pressure suppression vent pipe and the volume of the steam space above the normal operating water level in the reactor pressure vessel and above the normal operating water level and below The cooling device for the reactor containment vessel according to claim 1. 3. In a reactor containment vessel cooling device, the suppression pool is divided into a plurality of pools by partition walls, and the divided pools communicate with each other in a suppression chamber space above the water surface, and the condensed water return pipe is connected. The cooling device for the reactor containment vessel according to claim 1, wherein the exhaust pipe and the cooling water injection pipe for the emergency core cooling system are connected to different divided pools. 4. A reactor containment vessel cooling device, wherein the reactor containment vessel is made of steel, the cooling water pool is divided into a plurality of regions by partition walls, and each divided cooling water pool accommodates a heat exchanger. Distinguishing things from those that are not housed,
The divided cooling water pool containing the heat exchanger is thermally isolated from the wall of the reactor containment vessel and the divided cooling water pool not containing the heat exchanger, and the divided cooling pool does not contain the heat exchanger. The cooling apparatus for the reactor containment vessel according to claim 1, wherein the water pool exchanges heat with the suppression pool and the suppression chamber via a wall of the reactor containment vessel. 5. The cooling device for the reactor containment vessel according to claim 4, wherein the partition wall that thermally isolates the divided cooling water pool in the cooling device for the reactor containment vessel is a heat insulating material. 6. The cooling device for the reactor containment vessel according to claim 4, wherein the partition wall for thermally isolating the divided cooling water pool in the cooling device for the reactor containment vessel is formed by vacuum layer heat insulation. 7. A cooling device for a reactor containment vessel, comprising a second cooling water pool containing a second heat exchanger composed of a steam chamber, a heat transfer tube and a water chamber around the suppression pool outside the reactor containment vessel. Installed, the steam chamber of the second heat exchanger is connected to the suppression pool by the upper pipe and the water chamber is connected by the lower pipe, and the connection position of the upper pipe in the suppression pool is at the outlet height of the pressure suppression vent pipe, and The cooling device for a reactor containment vessel according to claim 1, wherein the pipe is connected to a bottom portion of the suppression pool. 8. The nuclear reactor containment vessel cooling device according to claim 7, wherein the second heat exchanger installed around the suppression pool outside the reactor containment vessel is air cooled. Cooling device for reactor containment vessel. 9. A cooling device for a reactor containment vessel, characterized in that a second heat exchanger installed outside the reactor containment vessel around the suppression pool is air-cooled and installed in a cooling tower. The cooling device for a reactor containment vessel according to claim 8. 10. A cooling device for a reactor containment vessel, comprising:
The cooling water pool installed around the suppression pool outside the reactor containment vessel, while the wall surface is made of steel plate,
The cooling device for a reactor containment vessel according to claim 1, wherein an air passage is formed between the wall surface of the cooling water pool and the reactor containment vessel.