JPH06242279A - Reactor containment equipment - Google Patents

Abstract

PURPOSE:To make cooling reactor containment possible for a long period without discharging radioactives into the air by providing a cooling water pool for removing heat from a reactor containment with a reactor containment equipment and supplying the pool water during long term cooling of a reactor without using such active component as pumps and external water source, and improve economy, reliability and safety of a reactor. CONSTITUTION:Outside of a reactor containment 10, an air cooling duct 104 and a condenser consisting of heat conduction pipes 106 are provided, the steam generated in a cooling water pool 113 for an isolation condenser 112 provided in the reactor containment 10 is condensed in this condenser and the condensate water is supplied to the cooling water pool 113. Since the cooling water is eventually supplied to the cooling water pool 113 by this, long term cooling of reactor containment 10 becomes possible, and the size of the reactor containment 10 is minimized. Also, radioactives are not discharged to the atmosphere as the pipes 101, 102 and heat conduction pipes 106 are shielded from the atmosphere.

Description

Detailed Description of the Invention

[0001]

BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a reactor containment facility, and more particularly to a reactor containment facility suitable for improving the long-term cooling performance of the reactor against a pipe break accident assumed in safety design of the reactor.

[0002]

2. Description of the Related Art In a conventional boiling water reactor, in order to suppress a pressure increase due to steam ejected into a reactor containment vessel when a pipe breakage accident is assumed, steam is guided to a suppression pool in a pressure suppression chamber. Condense. Further, in the long-term cooling process, the suppression pool water is generally cooled by using a residual heat removal system including a pump and a heat exchanger to remove heat from the reactor containment vessel.

Japanese Patent Laid-Open Nos. 3-215792 and 2
In the nuclear reactors described in JP-A-253196 and JP-A-3-75593, a cooling water pool is provided in the reactor containment vessel, an isolation condenser is provided in the cooling water pool, and a main steam pipe and a dry well are provided. The steam in the reactor is condensed by the condenser at the time of isolation, and the boiling steam of the cooling water pool water is exhausted to the outside of the reactor containment vessel to release the heat in the reactor containment vessel to the outside of the reactor containment vessel. In this case, JP-A-2-253196
In the nuclear reactors described in Japanese Patent Laid-Open No. 3-75559 and Japanese Patent Laid-Open No. 3-75593, the boiling steam of the cooling water pool water exhausted outside the reactor containment vessel is cooled by an external cooling means including an injector, a cooling tower, and an external cooling water pool. .

Further, in a reactor containment vessel of the outer pool type as described in JP-A-4-9694, the heat transferred to the suppression pool water is transferred to the outer pool through the wall of the reactor containment vessel and The boiling of pool water releases the heat in the containment vessel to the atmosphere. In the long-term cooling process, as a cooling means for the reactor containment vessel after the outer peripheral pool water is evaporated, channels are provided in the upper and lower portions of the outer peripheral pool, and the reactor containment vessel wall after the pool water is evaporated is cooled by air cooling.

Further, as described in Japanese Patent Laid-Open No. 2-47586, there is one that supplies seawater to the heat exchanger in the suppression pool to cool the suppression pool water and remove heat from the reactor containment vessel.

[0006]

In the prior art in which the suppression pool water is cooled using a residual heat removal system consisting of a pump and a heat exchanger to remove heat from the reactor containment vessel, dynamic equipment such as a pump is used. Since it is used, the reliability of the reactor cannot be improved.

In the prior art disclosed in Japanese Patent Laid-Open No. 3-215792, the condenser during isolation cannot be cooled after the cooling water in the cooling water pool is evaporated, so that the heat removal performance in the reactor containment vessel is improved. descend. Therefore, in order to cool the reactor containment vessel over a long period of time, it is necessary to significantly increase the volume of the cooling water pool or to supply water into the cooling water pool by an external water source and equipment such as a pump. Increasing the volume of the cooling water pool will increase the size of the reactor containment vessel,
The economics of manufacturing a nuclear reactor are reduced. When an external water source is used, the economical efficiency related to the production of the nuclear reactor is reduced and the reliability of the nuclear reactor cannot be improved because dynamic equipment such as a pump is used.

Assuming that the heat transfer tube of the isolation condenser is broken, the flow path to the isolation condenser must be closed in order to prevent the vapor in the reactor from being released into the atmosphere. Therefore, the heat removal function of the reactor containment vessel by the isolation condenser is lost.

Further, in the prior arts disclosed in JP-A-2-253196 and JP-A-3-75593, the cooling water condensed by the injector flows down together with the cooling water flowing down from the external cooling water pool to adjust the flow rate. A part of the flow rate distributed by the orifice is returned to the cooling water pool, and the rest is returned to the external cooling water pool via the cooling tower. In this case, when the water level of the cooling water pool that surrounds the condenser during isolation rises, the operation of the injector stops, so it is necessary to delicately set the flow rate adjusting orifice in order to keep the water level appropriate. Therefore, in order to ensure the reliability of the operation of the injector, it is necessary to dispose an expensive control device for controlling the opening of the flow rate adjusting orifice, which reduces the economical efficiency of manufacturing the nuclear reactor. Moreover, since the dynamic equipment is used, the reliability of the reactor cannot be improved.

Further, the cooling water returned to the cooling tower is sprayed and cooled in the cooling tower, but since the cooling tower communicates with the atmosphere, it does not have a completely closed loop structure. Therefore, assuming the case where the heat transfer tube of the isolation condenser is broken, the flow path to the isolation condenser must be closed in order to prevent the release of steam in the reactor into the atmosphere. The heat removal function of the reactor containment vessel by the isolation condenser is lost.

Further, in the prior art disclosed in Japanese Patent Laid-Open No. 4-9694, after the outer peripheral pool water is evaporated, the heat transfer coefficient is lowered from the heat removal by water to the heat removal by air cooling. The heat transfer area of the wall of the containment vessel is insufficient, and the heat removal performance inside the containment vessel is reduced. In order to cool the reactor containment vessel by removing heat by air cooling, it is necessary to enlarge the reactor containment vessel and to significantly increase the wall area, which reduces the economical efficiency of manufacturing the reactor.

Further, in the conventional technique disclosed in Japanese Patent Laid-Open No. 2-47586, it is necessary to assume breakage of the seawater pipe in the reactor containment vessel in order to introduce external seawater into the reactor containment vessel. Since the seawater is supplied by a dynamic device such as a pump, the economical efficiency is lowered and the reliability of the reactor cannot be improved.

An object of the present invention is to provide a reactor containment facility having a cooling water pool for removing heat from the reactor containment vessel during long-term cooling of the reactor, without using dynamic equipment such as a pump or an external water source. It is to provide a reactor containment facility that makes it possible to remove heat from the reactor containment vessel for a long period of time without replenishing it and releasing radioactive substances into the atmosphere, thereby improving the economic efficiency and reliability and safety of the reactor. .

[0014]

To achieve the above object, the present invention provides a reactor pressure vessel containing a nuclear fuel core, a reactor containment vessel containing the reactor pressure vessel, and the core. It has a main steam pipe for transporting the generated steam from the reactor pressure vessel to a facility outside the reactor containment vessel, a space dry well in the reactor containment vessel, and a suppression pool and a suppression pool holding cooling water. A cooling water having a pressure suppression chamber having a wet well which is an upper gas phase portion, and a vent pipe connecting the dry well and the suppression pool, and further removing heat from the reactor containment vessel in a long-term cooling process after the accident. In a reactor containment facility having a pool, located above the water surface of the cooling water pool and connected to the cooling water pool by a closed loop,
A reactor containment facility is provided, which is provided with a condensing unit that condenses a vapor of cooling water in the cooling water pool that is heated by the condenser during isolation and boils, and returns the condensed water to the cooling water pool.

In the nuclear reactor containment facility, preferably, the condensing means is a heat transfer tube installed outside the nuclear reactor containment vessel at a position above the water surface of the cooling water pool,
Means for cooling the heat transfer tube, steam generated in the cooling water pool flows through the heat transfer tube and is condensed, and the condensed water is returned to the cooling water pool by the hydrostatic head.

The means for cooling the heat transfer tube may be a duct containing the heat transfer tube and through which air flows, a cooling water pool containing the heat transfer tube, or the heat transfer tube. It may be seawater.

In the nuclear reactor containment facility, the condensing means may be a condensation tank installed outside the reactor containment vessel at a position above the water surface of the cooling water pool, and a coolant installed in the condensation tank. Has a duct through which
The steam generated in the cooling water pool may flow in the condensing tank to be condensed, and the condensed water may be returned to the cooling water pool by the hydrostatic head.

The condensing means includes a cooling water tank installed outside the reactor containment vessel at a position above the water surface of the cooling water pool, the vicinity of the water surface of the cooling water pool and the gas in the cooling water tank. A pipe that communicates with the phase space to supply steam from the cooling water pool to the cooling water tank, and connects the water in the cooling water pool and the water in the cooling water tank to return condensed water from the cooling water tank to the cooling water pool A configuration having a pipe may be used.

Further preferably, the condensing means is provided in a pipe for supplying steam from the cooling water pool and a pipe for returning condensed water to the cooling water pool, and is capable of melting in response to a temperature rise of the cooling water pool. A condensing plug is provided, and cooling water is filled into the condensing means during normal operation of the nuclear reactor so that the accommodating plug melts and the pipes communicate with each other in the event of an accident. Instead of filling the cooling means with the cooling water, the pressure inside the condensation means may be kept low.

Further preferably, the condensing means has one end communicating with a pipe for returning the condensed water to the cooling water pool, and the other end is open to the atmosphere at a position above the uppermost part of the condensing means. Further has.

To achieve the above object, the present invention provides
A water pool condenser installed outside the reactor containment vessel at a position above the water surface of the cooling water pool and having an overflow pipe, and a pipe for supplying steam from the cooling water pool to the water in the water pool condenser And a pipe for returning condensed water from the overflow pipe to the cooling water pool.

Further, in order to achieve the above object, the present invention has a condenser located inside a gas phase space in the cooling water pool, in which a coolant flows, and the steam generated in the cooling water pool is A reactor containment facility characterized by condensing in a condenser and returning the condensed water to a cooling water pool. In this case, the coolant flowing inside the condenser may be air or seawater.

To achieve the above object, the present invention provides
Condensation means connected to the cooling water pool in a closed loop, condensing the cooling water vapor of the cooling water pool that is heated and boiled by the condenser during isolation, and a pipe that connects the condensing means and the cooling water pool. A reactor containment facility characterized by having a pump installed to return condensed water from a condensing means to a cooling water pool. In this case, it is installed in the pipe that connects the cooling water pool and the condensing means,
It is preferable to further have a blower that supplies steam from the cooling water pool to the condensing means.

In the above reactor containment equipment, the cooling water pool preferably includes an isolation condenser installed in the reactor containment vessel, and a steam inlet of the isolation condenser communicates with the main steam pipe. The condensate outlet of the isolation condenser communicates with the suppression pool. Further, the cooling water pool may be an outer peripheral pool that is installed on the outer periphery of the reactor containment vessel and is in contact with the pressure suppression chamber via the outer wall of the reactor containment vessel.

[0025]

[Operation] When a pipe breakage accident is assumed, steam generated by decay heat of the core flows into the vent pipe, is blown into the suppression pool from the vent pipe outlet, is condensed in the suppression pool water, and is condensed in the reactor containment vessel. Pressure is suppressed.

In a nuclear reactor that uses an isolation condenser for long-term cooling of a reactor containment vessel after an accident, steam in the reactor containment vessel is made to flow from the main steam pipe into the isolation condenser to be condensed.
The cooling water in the cooling water pool water boils due to the heat transfer due to the condensation of the steam, and the steam is discharged to the outside of the reactor containment vessel, so that the reactor containment vessel is deheated.

In a nuclear reactor which uses an outer peripheral pool for long-term cooling of the reactor containment vessel after an accident, heat from the pressure suppression chamber in the reactor primary containment vessel is transferred to the outer peripheral pool via the wall of the reactor primary containment vessel. Then, the peripheral pool cooling water is boiled to remove heat from the containment vessel.

In the present invention, the cooling water pool for the condenser at the time of isolation or above the water surface of the cooling water pool of the outer peripheral pool is connected to the cooling water pool in a closed loop and is heated by the isolation time condenser to boil the cooling water pool. Condensing means is provided for condensing the cooling water vapor and returning the condensed water to the cooling water pool. By this condensing means, the cooling water pool is removed of heat and the cooling water is semipermanently supplied to the cooling water pool by gravity, which is a natural force, so that the reactor containment vessel can be cooled by the cooling water pool for a long period of time.

Further, since the cooling water is returned to the cooling water pool from the condensing means, the required cooling water amount in the cooling water pool may be small, and the cooling water pool and the reactor containment vessel can be downsized. Further, since the condensing means can be constituted by a heat transfer tube, a duct, etc., it can be installed at an arbitrary location apart from the reactor containment vessel, and can be designed without any restrictions on the dimensions of the reactor containment vessel 10.

Further, even if it is assumed that radioactive material in the reactor containment vessel leaks into the cooling water pool due to breakage of the heat transfer tube of the condenser during isolation, etc., the condensing means is constituted by a closed loop and is shielded from the external environment. Therefore, radioactive materials in the PCV are not released to the outside world.

Before the accident, air or the like inside the pipe and the condensing means is provided before the accident by providing the pipe with a compatible plug and filling the condensing means with cooling water or keeping the condensing means in a low pressure state. Since the non-condensable gas does not exist, the heat transfer performance of the condensing means in the event of an accident is improved and the safety is further improved. Further, since the capacity of the condensing means can be reduced by improving the heat transfer performance, the economical efficiency of the nuclear reactor is improved.

By providing a pressure adjusting pipe in the pipe for returning condensed water to the cooling water pool, pressurization in the cooling water pool,
Since the pressure reduction can be prevented, the safety of the reactor is further improved.

[0033]

DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS A first embodiment of the present invention will be described with reference to FIGS. This embodiment is an application of the present invention to an ABWR type reactor containment facility having a reinforced concrete containment vessel.

In FIG. 1, the reactor containment equipment of this embodiment has a reactor containment vessel 10 made of reinforced concrete. Inside the reactor containment vessel 10, a dry well 11 and a pressure suppression chamber 14 are provided by a concrete structure wall 16. And the pressure suppression chamber 14 is a suppression pool 1 that holds cooling water.
2 and a wet well 13 which is a gas phase above the wet well 13. The suppression pool 12 and the dry well 11 are connected by a number of vent pipes 17. The reactor pressure vessel 1 is installed in the dry well 11. A core 2 made of nuclear fuel is built in the reactor pressure vessel 1, and steam generated in the core 2 is supplied to a turbine outside the reactor containment vessel 10 through a main steam pipe 3 to serve as a drive source for the turbine. Condensed water of the used steam is supplied to the reactor pressure vessel 1 through the water supply pipe 4. Circulation of cooling water in the core 2 is performed by a circulation pump 166.

An automatic pressure reducing valve 23 is provided in the dry well 11.
Also, an automatic depressurization system including an exhaust pipe 25 for blowing the exhaust gas into the pool water in the suppression pool 12 is provided. The automatic depressurizing system includes a control system that opens the automatic depressurizing valve 23 when the cooling water level in the reactor pressure vessel 1 becomes a low water level dangerous to the core 2.

Inside the reactor containment vessel 10, a cooling water tank 90, a water injection pipe 93 having a valve 99 and a check valve 97 is provided as a gravity drop type water injection device. Further, as a pressure accumulation type water injection device, a water injection pipe 24 including a high pressure pressure accumulation tank 20, a valve 81, and a check valve 26 is provided.

Further, in the nuclear reactor containment facility shown in FIG.
The reactor pressure vessel 1A has an elongated shape, and the reactor core 2 is located below the reactor containment vessel 10. Further, the suppression pool 12 and the reactor pressure vessel 1 are provided with a valve 83 and a check valve 8.
4 is connected to the core submersion system piping 22, cooling water is injected into the reactor pressure vessel 1 by the water level difference in the suppression pool 12 and the water head difference in the reactor pressure vessel 1 during long-term cooling in the event of an accident, and the core 2 is A flood system for flooding is provided. When this submerged system is provided, the long-term cooling performance of the core 2 is further improved. In the following examples, the operation is described with reference to the drawings in the case where the submerged system is not provided, but each example is applicable to both the case where the submerged system is provided and the case where the submerged system is not provided. .

Next, the characteristic structure of the reactor containment equipment according to this embodiment will be described with reference to FIG. An isolation condenser 112 and an isolation condenser 112 are provided in the reactor containment vessel 10.
And a cooling water pool 113 that encloses the main steam pipe 3 and the steam inlet of the isolation condenser 112 are communicated with each other by a pipe line 114 having an isolation valve 28, and the condensed water outlet of the isolation condenser 112 and the suppression pool are connected. The 12 waters communicate with each other through a pipe line 116.

Cooling water pool 11 outside the reactor containment vessel 10
3 above the water surface, the heat transfer tube 106 and the air cooling duct 10
4. A condenser comprising the duct support 105 is provided, and the gas phase space of the cooling water pool 113 and the upper part of the heat transfer tube 106 are connected to the conduit 1
01, and the cooling water pool 113 and the lower portion of the heat transfer pipe 106 are connected to each other by a pipe line 102 having a check valve 103. A vacuum breaking valve 140 is provided in the pipe line 101, and has a function of introducing air into the pipe line 101 to keep the cooling water pool 113 at the atmospheric pressure when the cooling water pool 113 has a negative pressure. The air cooling duct 104 has an upper part and a lower part open to the atmosphere, and has a structure that allows air to flow.

Next, the operation of the reactor containment equipment according to this embodiment will be described. Assuming an accident such as main steam pipe breakage,
The steam that has flowed out of the main steam pipe 3 to the dry well 11 flows into the suppression pool 12 from the vent pipe 17 and is condensed. Further, the steam from the main steam pipe 3 is condensed by the isolation condenser 112, and the condensed water is
The pressure in the containment vessel 10 is suppressed by flowing into the suppression pool 12 through 16. The heat is transferred to the cooling water in the cooling water pool 113 due to the condensation of the steam, and the heat in the reactor containment vessel 10 is removed to suppress the pressure increase.

The steam generated by the boiling of the cooling water in the cooling water pool 113 flows into the heat transfer tube 106 through the pipe line 101. The air around the heat transfer tube 106 is
The air heated by the steam therein rises in the air-cooling duct 104 due to buoyancy. Air cooling duct 1
The steam in the heat transfer tube 106 cooled by the air in 04 is condensed, descends in the heat transfer tube 106 by gravity, and returns to the cooling water pool 113 through the pipe line 102.

Cooling water in the cooling water pool 113 and vapor condensation in the heat transfer tubes 106 remove heat from the cooling water pool 113, and the cooling water is semipermanently supplied to the cooling water pool 113 by gravity, which is a natural force. Therefore, the reactor containment vessel 10 can be cooled for a long period of time by the isolation condenser 112 and the cooling water pool 113.

When the condenser comprising the heat transfer tube 106 and the air cooling duct 104 according to this embodiment is not used, the cooling water vapor in the cooling water pool 113 is contained in the reactor containment vessel 10.
Since it is discharged to the outside, it is necessary to store a large amount of cooling water in the cooling water pool 113. However, when the condenser of this embodiment is used, the cooling water is returned to the cooling water pool 113. Since the required amount of cooling water in the cooling water pool 113 is reduced, the volumes of the cooling water pool 113 and the reactor containment vessel 10 can be reduced.

Further, the condenser comprising the heat transfer tube 106 and the air cooling duct 104 of this embodiment can be installed at any place outside the reactor containment vessel 10, and is restricted by the size of the reactor containment vessel 10. It can be designed without the need for a large capacity condenser.

Further, even if the radioactive substance in the reactor containment vessel 10 leaks into the cooling water pool 113 due to the breakage of the heat transfer tube of the isolation condenser 112, etc., the pipeline 10
Since the inside of 1, the heat transfer tube 106, and the pipeline 102 is shielded from the outside, the radioactive material in the reactor containment vessel 10 is not released to the outside.

Therefore, according to the present embodiment, it is possible to remove heat from the reactor containment vessel for a long period of time by the isolation condenser in the event of an accident, thus improving the safety of the reactor. Even if an accident such as a breakage of the heat transfer tube of the condenser during isolation is assumed, the safety of the reactor is further improved because the substance in the reactor containment vessel is not released to the outside. In addition, since the size of the reactor containment vessel can be reduced, the economical efficiency of manufacturing the reactor is improved. In addition, since the cooling water can be supplied to the cooling water pool of the condenser during isolation by gravity, which is a natural force, the reliability of the device is improved.

A second embodiment of the present invention will be described with reference to FIG. In the reactor containment facility shown in the first embodiment, a condenser composed of the heat transfer pipes 106 and the cooling water pool 107 is provided above the water surface of the cooling water pool 113 outside the reactor containment vessel 10, and the cooling water pool 113 Gas phase space and heat transfer tube 10
6, the upper part of 6 is connected by a pipe line 101, and the cooling water pool 113 and the lower part of the heat transfer pipe 106 are provided with a check line 103.
Communicate with. A vacuum breaking valve 140 is provided in the pipe line 101, and has a function of introducing air into the pipe line 101 to keep the cooling water pool 113 at the atmospheric pressure when the cooling water pool 113 has a negative pressure. The upper part of the cooling water pool 107 is open to the atmosphere.

Assuming an accident such as breakage of the main steam pipe, the cooling water pool 11 heated by the isolation condenser 112.
The steam generated by the boiling of the cooling water in 3 passes through the pipe line 101 and flows into the heat transfer pipe 106. While the cooling water around the heat transfer tube 106 is heated by the steam in the heat transfer tube 106 and convection occurs in the cooling water pool 107, the steam in the heat transfer tube 106 condenses and descends in the heat transfer tube 106 by gravity,
Return to the cooling water pool 113 through the pipe line 102.

The cooling water in the cooling water pool 113 is removed by the boiling of the cooling water in the cooling water pool 113 and the vapor condensation in the heat transfer tube 106, and the cooling water in the cooling water pool 107 is completely evaporated until the cooling water is completely evaporated. Since cooling water is supplied to the pool 113 by gravity, which is a natural force, the reactor containment vessel 10 can be cooled for a long time by the cooling water pool 113.

When the condenser comprising the heat transfer pipe 106 and the cooling water pool 107 according to this embodiment is not used, the cooling water in the cooling water pool 113 evaporates to the outside of the reactor containment vessel 10, so that the cooling water pool 113 is used. It is necessary to store a large amount of cooling water in the inside, but when the condenser of this embodiment is used, the cooling water is returned to the cooling water pool 113, and the required amount of cooling water in the cooling water pool 113 is Since the volume is reduced, the volume of the reactor containment vessel 10 can be reduced.

Further, the condenser comprising the heat transfer tube 106 and the cooling water pool 107 of this embodiment can be installed at any place outside the reactor containment vessel 10 and is restricted by the size of the reactor containment vessel 10. It can be designed without the need for a large capacity condenser.

Furthermore, even if the radioactive substance in the reactor containment vessel 10 leaks into the cooling water pool 113 due to the breakage of the heat transfer tube of the isolation condenser 112, etc., the pipeline 10
Since the inside of 1, the heat transfer tube 106, and the pipeline 102 is shielded from the outside, the radioactive material in the reactor containment vessel 10 is not released to the outside.

Further, as compared with the first embodiment, the heat transfer from the heat transfer tube 106 to the cooling water in the cooling water pool 107 is boiling heat transfer, so that the heat transfer coefficient is high and the cooling water pool 113 is high.
And the heat transfer area of the heat transfer tube 106 can be reduced.

Therefore, according to this embodiment, in the event of an accident, it is possible to remove heat from the reactor containment vessel for a long period of time by the isolation condenser, so the safety of the reactor is improved. Even if an accident such as a breakage of the heat transfer tube of the condenser during isolation is assumed, the safety of the reactor is further improved because the substance in the reactor containment vessel is not released to the outside. In addition, since the size of the reactor containment vessel can be reduced, the economical efficiency of manufacturing the reactor is improved. In addition, since the cooling water can be supplied to the cooling water pool of the condenser during isolation by gravity, which is a natural force, the reliability of the device is improved. Furthermore, since the capacity of the cooling water pool and the heat transfer area of the heat transfer tubes can be reduced, the economical efficiency of manufacturing the nuclear reactor is further improved.

A third embodiment of the present invention will be described with reference to FIG. In the nuclear reactor containment facility shown in the first embodiment, the pipes 101 and 102 are fitted with the permissible plugs 108 and 109, and the heat transfer pipes 106 are filled with cooling water in advance. A material that melts at a high temperature is used for the compatible plug 108 and the compatible plug 109, and particularly, the cooling water pool 1
When the cooling water in 13 boils, it should be completely melted at the steam temperature. A vacuum break valve 140 is provided in the pipe line 101, and has a function of introducing air into the pipe line 101 to maintain the cooling water pool 113 at the atmospheric pressure when the cooling water pool 113 has a negative pressure.

At the time of an accident, as the cooling water pool 113 boils, the allowable plugs 108 and 109 melt, and the pipe 101, the heat transfer pipe 106, the pipe 102 and the cooling water pool 113 communicate with each other. . By this, the pipeline 10
1, the cooling water in the heat transfer tube 106 and the pipe 102 flows into the cooling water pool 113, and the steam flows into the heat transfer tube 106 from the vapor phase space of the cooling water pool 113 to start condensation.

Before the accident, since there is no non-condensable gas such as air in the pipe 101, the heat transfer pipe 106 and the pipe 102, the heat transfer performance in the heat transfer pipe 106 at the time of the accident is acceptable. Compared with the case where neither the stopper 108 nor the tolerable stopper 109 is used, it is significantly improved.

By improving the heat transfer performance, the cooling water pool 1
Since the capacity of 13 and the capacity of the condenser including the heat transfer tube 106 and the air cooling duct 104 can be reduced, the economical efficiency of the nuclear reactor is improved.

According to this embodiment, since the heat removal performance of the reactor containment vessel by the cooling water pool is improved, the safety of the reactor is further improved. Further, since the size of the containment vessel and the size of the condenser can be reduced, the economical efficiency of manufacturing the reactor is further improved.

In this embodiment, the storage facility of the first embodiment is provided with the soluble plug, but the second embodiment may be provided with the soluble plug. Although the heat transfer tube 106 is filled with cooling water in advance, the heat transfer tube 106 may be placed in a low pressure state instead. In this case also, before the accident, the pipe 101 and the heat transfer pipe 1
06, since the non-condensable gas such as air is less in the pipe 102, the heat transfer performance in the heat transfer pipe 106 at the time of an accident is significantly improved.

A fourth embodiment of the present invention will be described with reference to FIG. In the reactor containment facility shown in the first embodiment, a condenser made up of the cooling water pool 107 is provided above the cooling water pool 113 outside the reactor containment vessel 10, and an opening is provided below the water surface of the cooling water pool 107. A steam blowing pipe 110 for blowing steam and an overflow pipe 111 having an opening near the water surface of the cooling water pool 107 are provided.
Vapor phase space of cooling water pool 113 and steam blow pipe 110
Through the pipe 101 and the cooling water pool 113 and the overflow pipe 111 through the pipe 102 having the check valve 103. The cooling water pool 107 has an upper part open to the atmosphere and a filter 10 that absorbs radioactive substances in that part.
7A is attached.

At the time of an accident, the steam generated by the boiling of the cooling water in the cooling water pool 113 is blown into the water of the cooling water pool 107 from the steam blowing pipe 110 through the pipe line 101. The injected steam is condensed, the water temperature in the cooling water pool 107 rises, and the water level in the cooling water pool 107 rises due to the condensed water. The cooling water that overflows due to the rise of the water level returns to the cooling water pool 113 through gravity through the overflow pipe 111 and the pipe line 102.

Until boiling starts in the cooling water pool 107, there is almost no evaporation of the cooling water from the cooling water pool 107, and the water level of the cooling water pool 113 is maintained. Therefore, by increasing the capacity of the cooling water pool 107, the heat removal performance of the cooling water pool 113 is maintained and the reactor can be cooled for a long period of time. Further, as a result, the required amount of cooling water in the cooling water pool 113 is also reduced, so that the containment vessel 10 can be downsized. Since the cooling water pool 107 of this embodiment can be installed at any location outside the reactor containment vessel 10, it is easy to increase the capacity of the cooling water pool 107.

Further, as compared with the first and second embodiments, the heat transfer from the steam blowing pipe 110 to the cooling water in the cooling water pool 107 is a direct condensation heat transfer, so that the heat transfer coefficient is high and the cooling The capacity of the water pool 113 can be reduced.

Even if the radioactive substance in the reactor containment vessel 10 leaks into the cooling water pool 113 due to the breakage of the heat transfer tube of the condenser 112 during isolation, the filter 1
Since the radioactive substance is adsorbed by 07A, it is possible to prevent the radioactive substance in the reactor containment vessel 10 from being released to the outside.

According to this embodiment, in the event of an accident, it is possible to remove heat from the reactor containment vessel for a long period of time by the isolation condenser, so the safety of the reactor is improved. Even if an accident such as a breakage of the heat transfer tube of the condenser during isolation is assumed, the safety of the reactor is further improved because the substance in the reactor containment vessel is not released to the outside. Since the size of the containment vessel can be reduced, the economical efficiency of manufacturing the reactor is improved. In addition, since the cooling water can be supplied to the cooling water pool of the condenser during isolation by gravity, which is a natural force, the reliability of the device is improved. Moreover, since the capacity of the cooling water pool can be further reduced, the economical efficiency of manufacturing the reactor is further improved.

Although not shown, the soluble plug of the third embodiment can be applied to this embodiment.

A fifth embodiment of the present invention will be described with reference to FIG. In the nuclear reactor containment facility shown in the first embodiment, a condenser composed of the cooling water tank 119 is provided, and the vicinity of the water surface of the cooling water pool 113 and the vapor phase space of the cooling water tank 119 are connected by the pipe line 117. Further, the liquid phase portion of the cooling water tank 119 and the liquid phase portion of the cooling water pool 113 are connected by a pipe line 118. A vacuum break valve 140 is provided in the pipeline 101, and when the cooling water pool 113 has a negative pressure, air is supplied to the pipeline 101.
Has a function of maintaining the cooling water pool 113 at atmospheric pressure.

At the time of an accident, when the cooling water in the cooling water pool 113 boils and evaporates, and the liquid level of the cooling water pool 113 descends from the opening of the pipeline 117 on the cooling water pool 113 side, the cooling water pool 113 Steam flows from the vapor phase portion into the vapor phase space of the cooling water tank 119. As a result, the cooling water in the cooling water tank 119 flows into the cooling water pool 113 through the pipe 118 by the hydrostatic head. Further, the steam flowing into the vapor phase space of the cooling water tank 119 is
Cooling water tank 11 condensed by natural heat dissipation into the atmosphere of 19
It becomes the cooling water in 9. On the other hand, the water level in the cooling water pool 113 rises due to the inflow of the cooling water, and reaches the opening of the pipeline 117 on the cooling water pool 113 side. Since the water level is formed in the pipe 117 and the inflow of the gas phase into the cooling water tank 119 is stopped, the inflow of the cooling water from the pipe 118 to the cooling water pool 113 is stopped. With the above operation, the water level in the cooling water pool 113 is maintained constant, and the cooling water pool 1
A decrease in the heat removal performance of the reactor containment vessel 10 due to a decrease in the water level of 13 is prevented.

The cooling water tank 119 of this embodiment can be installed at any place outside the reactor containment vessel 10. Therefore, the cooling water tank 119 can have a large capacity and the reactor can be cooled for a long period of time.

According to this embodiment, in the event of an accident, it is possible to remove heat from the reactor containment vessel for a long period of time by the isolation condenser, so the safety of the reactor is improved. Even if an accident such as a breakage of the heat transfer tube of the condenser during isolation is assumed, the safety of the reactor is further improved because the substance in the reactor containment vessel is not released to the outside. In addition, since the size of the reactor containment vessel can be reduced, the economical efficiency of manufacturing the reactor is improved. Furthermore, since the cooling water can be supplied to the cooling water pool of the condenser during isolation by gravity, which is a natural force, the reliability of the device is improved.

Although not shown, the soluble plug of the third embodiment can be applied to this embodiment.

The sixth embodiment of the present invention will be described with reference to FIG. In the nuclear reactor containment facility shown in the first embodiment, a pressure adjusting pipe 134 is provided, one end of which communicates with the pipeline 102 and the other end of which communicates with the atmosphere above the uppermost portion of the heat transfer pipe 106. Since the pressure adjusting pipe 134 is for adjusting pressure, a pipe having a small diameter may be used.

In the event of an accident, if the heat removal performance of the condenser consisting of the heat transfer tube 106 and the air-cooling duct 104 is temporarily reduced, the steam generated in the cooling water pool 113 will not condense in the heat transfer tube 106 and will be cooled. The pressure in the water pool 113 may rise slightly. In addition, when the heat removal performance of the condenser is temporarily improved, the amount of condensation in the heat transfer tube 106 may increase and the pressure of the cooling water pool 113 may slightly decrease. At the time of pressurization, steam is released into the atmosphere by the pressure adjusting pipe 134, so that the pressure rise of the cooling water pool 113 can be prevented, and at the time of depressurizing, the pressure adjusting pipe 13 is released.
The pressure drop can be prevented by the cooling water in 4 flowing into the cooling water pool 113.

Since the pressure adjusting pipe 134 can be made small in diameter, even if the radioactive substance in the reactor containment vessel 10 leaks into the cooling water pool 113 due to breakage of the heat transfer pipe of the condenser 112 during isolation, etc. It is possible to substantially prevent the radioactive material in the furnace containment vessel 10 from being released to the outside. In order to further prevent the emission of the radioactive substance, a filter that absorbs the radioactive substance may be attached to the outlet of the pressure adjusting pipe 134.

According to this embodiment, pressurization and depressurization of the cooling water pool 113 can be prevented, so that the safety of the nuclear reactor is further improved.

Although not shown, the soluble plug of the third embodiment can be applied to this embodiment. Also, the second
The embodiment may be provided with the pressure adjusting pipe of this embodiment.

The seventh embodiment of the present invention will be described with reference to FIG. In the reactor containment facility shown in the first embodiment, a condenser including a condensation tank 119A, a tank support 105A, and a cooling duct 104A is provided above the surface of the cooling water pool 113 outside the reactor containment vessel 10, The vapor phase space of the cooling water pool 113 and the upper part of the condensation tank 119A are communicated with each other by a pipe line 101, and the cooling water pool 113 and the condensation tank 11
The lower part of 9A communicates with a pipe line 102 having a check valve 103. A vacuum break valve 140 is provided in the pipeline 101, and when the cooling water pool 113 has a negative pressure, air is supplied to the pipeline 101.
Has a function of maintaining the cooling water pool 113 at atmospheric pressure. The cooling duct 104A has an upper part and a lower part open to the atmosphere, and has a structure that allows air to flow.

At the time of an accident, the steam generated by the boiling of the cooling water in the cooling water pool 113 flows through the pipe 101 into the condensing tank 119A. Condensation tank 119
The air in the duct 104A passing through the inside of A is the condensing tank 11
The air heated by the steam in 9A rises in the duct 104A due to buoyancy. Duct 104A
The vapor in the condensing tank 119A cooled by the air inside condenses, accumulates in the lower part of the condensing tank 119A, and returns by gravity to the cooling water pool 113 through the pipe line 102.

Therefore, according to this embodiment, the same effect as that of the first embodiment can be obtained.

Although not shown, the soluble plug of the third embodiment can be applied to this embodiment. Further, the pressure adjusting pipe of the sixth embodiment may be provided in this embodiment.

The eighth embodiment of the present invention will be described with reference to FIG. In the reactor containment facility shown in the first embodiment, a condenser composed of the heat transfer pipes 106 and seawater 137 is provided above the surface of the cooling water pool 113 outside the reactor containment vessel 10, and the vapor phase of the cooling water pool 113 is provided. The space and the upper part of the heat transfer tube 106 are communicated with each other by the conduit 101, and the cooling water pool 113 and the lower part of the heat transfer tube 106 are communicated with each other by the conduit 102 having the check valve 103. A vacuum break valve 140 is provided in the pipeline 101, and when the cooling water pool 113 has a negative pressure, air is supplied to the pipeline 10
1 has the function of maintaining the cooling water pool 113 at atmospheric pressure.

At the time of an accident, the steam generated by boiling of the cooling water in the cooling water pool 113 flows into the heat transfer tube 106 through the pipe 101. The steam in the heat transfer tube 106 exchanges heat with the seawater 137 to condense, and the gravity causes the heat transfer tube 1 to move.
06 inside, cooling water pool 11 through pipeline 102
Return to 3.

In the present embodiment, the air condensing means is water-cooled using seawater, the condensing efficiency is high, and since the seawater is almost inexhaustible, the steam can be condensed semipermanently.

Therefore, according to the present embodiment, in the event of an accident, the isolation condenser 112 can remove heat for a long period of time, further improving the safety of the nuclear reactor.

Although not shown, the soluble plug of the third embodiment can be applied to this embodiment. Further, the pressure adjusting pipe of the sixth embodiment may be provided in this embodiment.

The ninth embodiment of the present invention will be described with reference to FIG. This example illustrates the present invention by a BW having a steel containment vessel.
It was applied to the R-type reactor containment facility.

In FIG. 10, the reactor containment equipment of this embodiment has a structure with a concrete structure wall 16 and a steel reactor containment vessel 10A covering this structure. A dry well 11 and a pressure suppression chamber 14 are formed by the reactor containment vessel 10A. The upper surface of the concrete structure wall 16 is
The operating floor 30 is used for handling the nuclear fuel elements and the like existing in the reactor pressure vessel 1 with the handling device 80.

The reactor pressure vessel 1 is installed in the dry well 11. A core 2 made of nuclear fuel is built in the reactor pressure vessel 1, and steam generated in the core 2 is supplied to a turbine outside the reactor containment vessel 10 through a main steam pipe 3 to serve as a drive source for the turbine. Condensed water of the used steam is supplied to the reactor pressure vessel 1 through the water supply pipe 4. Circulation of cooling water in the core 2 is performed by a circulation pump 166.

The pressure suppression chamber 14 is composed of the suppression pool 12 holding cooling water and the wet well 13 in the vapor phase above the suppression pool 12. Suppression pool 1
2 and the dry well 11 are connected by a number of vent pipes 17. The suppression pool 12 and the wet well 13 are surrounded by the concrete structure wall 16 and have outer peripheral portions 12a and 13a.
And outer peripheral portions 12b and 13b. The outer peripheral portions 12a, 13a and the outer peripheral portions 12b, 13b of the suppression pool 12 and the wet well 13 are respectively formed with a plurality of communication holes 1 formed in the concrete structure wall 16.
8 and 18a communicate with each other, and the pool water and the vapor phase have communication holes 1
It is possible to circulate in the inner and outer circumferences through 8, 18a.

The outer periphery of the reactor containment vessel 10A is surrounded by the outer periphery pool 15, and the cooling water in the suppression pool 12 is cooled by heat transfer from the steel wall surface of the reactor containment vessel 10A to the outer periphery pool 15. In addition, from the center to the upper part of the reactor containment vessel 10A, the reactor containment vessel 10
An air cooling duct 33 is provided outside A, and the air intake 3
The outer wall surface of the reactor containment vessel 10 </ b> A is air-cooled by the air entering from 2 and entering from the duct 87.

Wet well 13a on the outer periphery and operating floor 3
The space portion of 0 is partitioned by the pressure release plate 31, and when the pressure of the wet well 13 rises at the time of an accident, the pressure release plate 31 is broken and the wet well 13 and the space portion of the operating floor 30 communicate with each other. It is structured to be. As a result, the volume of the wet well 13 increases, and the pressure increase at the time of an accident can be further suppressed.

An automatic pressure reducing valve 23 is provided in the dry well 11.
Also, an automatic depressurization system including an exhaust pipe 25 for blowing the exhaust gas into the pool water in the suppression pool 12 is provided. The automatic depressurizing system includes a control system that opens the automatic depressurizing valve 23 when the cooling water level in the reactor pressure vessel 1 becomes a low water level dangerous to the core 2.

Further, the suppression pool 12 and the reactor pressure vessel 1 are communicated with each other by a core submersion system pipe 22 having a valve 83 and a check valve 84, and the water level of the suppression pool 12 and the reactor pressure vessel are used during long-term cooling in the event of an accident. A submersion system for pouring cooling water into the reactor pressure vessel 1 by the water head difference and submersing the core 2 is provided.

Inside the reactor containment vessel 10, a cooling water tank 21, a water injection pipe 25 having a valve 82 and a check valve 27 is provided as a gravity drop water injection device. Further, as a pressure accumulation type water injection device, a pressure accumulation tank 20, a valve 18 and a check valve 26
Is provided.

Outer gas pool 15 outside the reactor containment vessel 10
Above the water surface of the heat transfer tube 106, the air cooling duct 10
4. A condenser comprising a duct supporting part 105 is provided, and the gas phase space of the outer peripheral pool 15 and the upper part of the heat transfer tube 106 are connected to the conduit 101.
And the outer peripheral pool 15 and the lower portion of the heat transfer pipe 106 are communicated with each other through a pipe line 102 having a check valve 103. The pipe 101 is provided with a vacuum break valve 140, and when the outer peripheral pool 15 has a negative pressure, air is introduced into the pipe 101 and the outer peripheral pool 1
It has the function of keeping 5 at atmospheric pressure. Air cooling duct 104
The upper and lower parts of the are open to the atmosphere, and the structure allows air to flow.

Next, the operation of the reactor containment equipment according to this embodiment will be described. Assuming an accident such as main steam pipe breakage,
The steam that has flowed out of the main steam pipe 3 to the dry well 11 flows into the suppression pool 12 from the vent pipe 17 and is condensed. The temperature of the cooling water in the suppression pool 12 rises due to the condensation of the steam, and the reactor containment vessel 10
The pressure in A rises. Heat is transferred from the suppression pool 12 to the outer peripheral pool 15 through the steel wall surface of the reactor containment vessel 10A, the water temperature of the outer peripheral pool 15 rises, and boiling starts. The heat transfer to the outer peripheral pool 15 removes heat from the suppression pool 12 and suppresses the pressure inside the reactor containment vessel 10A.

The steam generated by the boiling of the cooling water in the outer peripheral pool 15 passes through the pipe 101 and flows into the heat transfer pipe 106. The air around the heat transfer tube 106 is heated by the steam in the heat transfer tube 106, and the heated air rises in the air cooling duct 104 due to buoyancy. Air cooling duct 10
The vapor in the heat transfer tube 106 cooled by the air in the condenser 4 condenses and descends in the heat transfer tube 106 due to gravity, so that the pipeline 1
Return to the outer pool 15 through 02.

Boiling of cooling water in the outer pool 15,
The outer pool 15 is removed by vapor condensation in the heat transfer tubes 106, and the cooling water is semipermanently supplied by gravity, which is a natural force, so that the outer pool 15 can be cooled for a long period of time.

Further, the heat exchanger comprising the heat transfer tube 106, the air-cooling duct 104, and the duct supporting portion 105 according to the present embodiment requires the inside of the outer pool 15 as compared with the case where the heat exchanger according to the present embodiment is not used. Since the amount of cooling water is reduced, the diameter of the reactor containment vessel 10 can be reduced.

Further, the heat exchanger of this embodiment can be installed in any place outside the reactor containment vessel 10, and the size of the reactor containment vessel is limited to the size of the heat exchanger of this embodiment. It can be designed without

The outer peripheral pool 115 is separated from the inside by the steel containment vessel 10A, and the pipeline 101,
Since the insides of the heat transfer tube 106 and the pipe 102 are shielded from the outside, the radioactive substance in the reactor containment vessel 10A is not released to the outside.

Therefore, according to the present embodiment, it is possible to remove heat from the reactor containment vessel for a long period of time by the outer pool in the event of an accident, thus improving the safety of the reactor. Further, since the substance in the reactor containment vessel is not released to the outside, the safety of the reactor is further improved. In addition, since the size of the reactor containment vessel can be reduced, the economical efficiency of manufacturing the reactor is improved. Further, since the cooling water can be supplied to the outer peripheral pool by gravity, which is a natural force, the reliability of the equipment is improved.

Although not shown, the condenser, the cooling water tank 119, the permissible plugs 108, 109 and the like shown in the second to eighth embodiments may be applied to the outer peripheral pool 15 of this embodiment. it can.

The tenth embodiment of the present invention will be described with reference to FIG. In the reactor containment facility shown in the first embodiment, a blower 141 is provided in the pipe line 101 to transfer steam to the heat transfer tube 1.
06, the pump 142 is provided in the pipe 102 to supply the condensed water to the condenser including the air cooling duct 104, and the condensed water is cooled by the cooling water pool 1.
Supply to 13. By using the pump 142 to supply the condensed water to the cooling water pool 113, the condenser can be installed below the reactor containment vessel 10. As a result, the condenser can be installed at any place, so that the degree of freedom regarding the design of the nuclear reactor can be increased, and the civil engineering work for installing the nuclear reactor can be reduced.

The blower 141 is not necessarily provided, but it is preferable to use it for forcibly transporting steam especially when the pressure loss in the pipe 101 is large.

According to this embodiment, the economical efficiency of installing a nuclear reactor can be improved.

Although not shown, the pump 1 of this embodiment
The forced circulation system composed of the air blower 42 and the blower 141 is also applicable to the second to eighth embodiments and the ninth embodiment of the outer circumference pool system.

An eleventh embodiment of the present invention will be described with reference to FIG. In the reactor containment facility shown in the first embodiment, a condenser composed of a cooler 143 is installed in the cooling water pool 113 so as to be located in the pool water and the vapor phase space, and the cooler 143 is installed by the blower 145. Air is blown inside, and the air is exhausted to the atmosphere by the exhaust pipe 144. The cooler 143 condenses the steam in the cooling water pool 113 and cools the cooling water in the cooling water pool 113.
As a result, the long-term cooling of the reactor containment vessel 10 by the isolation condenser 112 and the cooler 146 and the cooling water pool 113 are performed.
The capacity can be reduced.

According to this embodiment, in the event of an accident, the isolation condenser can remove heat from the reactor containment vessel for a long period of time, thus improving the safety of the reactor. Since the size of the containment vessel can be reduced, the economical efficiency of manufacturing the reactor is improved. Further, even if an accident such as breakage of the heat transfer tube of the condenser during isolation is assumed, the substance in the reactor containment vessel is not released to the outside, so the safety of the reactor is further improved.

Although not shown, the coolant flowing in the cooling air 14 may be seawater. In addition, the cooler 1 of this embodiment
The cooling system including 43, the exhaust pipe 144, and the blower 145 can be applied to the outer pool of the outer pool type reactor containment facility shown in the ninth embodiment.

The twelfth embodiment of the present invention will be described with reference to FIG. The present embodiment is an application of the present invention to a reactor containment facility having an outer peripheral pool type reactor containment vessel of a new-type converter.

In FIG. 13, the cooling water supplied from the water drum 128 by the circulation pump 166 enters the reactor 127 from the inlet pipe group 129, flows to the outlet pipe group 126, and is separated into steam and water by the steam drum 124. A fuel exchange device 131, a temperature control unit 122, a circulation blower 123, and the like are installed in the steel reactor containment vessel 120. An outer peripheral pool 133 is provided on the outer periphery of the reactor containment vessel 120, and the vapor discharge pool 132 in the reactor containment vessel 120 is provided.
The heat is transferred to the outer peripheral pool 133 to remove the heat from the reactor containment vessel 120.

The heat transfer tube 10 is provided outside the containment vessel 120.
6, a heat exchanger including an air-cooling duct 104 and a duct support portion 105 is provided, and the vapor phase space of the outer peripheral pool 133 and the upper portion of the heat transfer tube 106 are communicated with each other by a pipe line 101.
And a pipe 10 having a check valve 103 at the bottom of the heat transfer tube 106.
Connect with 2. The air cooling duct 104 has an upper part and a lower part open to the atmosphere, and has a structure that allows air to flow.

Assuming an accident such as breakage of the inlet pipe group 129, the steam flowing out into the reactor containment vessel 120 flows into the steam discharge pool 132 and is condensed. Due to the condensation of the steam, the temperature of the cooling water in the steam discharge pool 132 rises and the pressure in the reactor containment vessel 120 rises. Steam release pool 1
Heat is transferred from 32 to the outer peripheral pool 133 through the wall surface of the reactor containment vessel 120, the water temperature of the outer peripheral pool 133 rises, and boiling starts. This heat transfer to the outer peripheral pool 133 removes heat from the vapor discharge pool 132, and the pressure inside the reactor containment vessel 120 is suppressed.

The steam generated by boiling the cooling water in the outer peripheral pool 133 flows into the heat transfer tube 106 through the pipe line 101. The air around the heat transfer tube 106 is heated by the steam in the heat transfer tube 106, and the heated air rises in the air cooling duct 104 due to buoyancy. Air cooling duct 1
The steam in the heat transfer tube 106 cooled by the air in 04 is condensed, descends in the heat transfer tube 106 by gravity, and returns to the outer peripheral pool 133 through the pipe line 102.

Due to the boiling of the cooling water in the outer peripheral pool 133 and the vapor condensation in the heat transfer tube 106, the outer peripheral pool 1
33 is heat-removed and the cooling water is semi-permanently supplied by gravity which is a natural force.
Enables long-term cooling. Further, the heat transfer tube 106, the air cooling duct 104, and the duct support portion 10 according to the present embodiment.
Since the heat exchanger of No. 5 reduces the required amount of cooling water in the outer peripheral pool 133 as compared with the case where the heat exchanger of this embodiment is not used, the diameter of the reactor containment vessel 120 can be reduced. The heat exchanger of this embodiment is the same as the reactor containment vessel 12
It can be installed in any place other than 0, and the size of the reactor containment vessel can be designed without being limited by the size of the heat exchanger of this embodiment.

The outer peripheral pool 133 is isolated from the inside by the steel containment vessel 120, and the pipeline 101,
Since the insides of the heat transfer tube 106 and the conduit 102 are shielded from the outside world, the radioactive substances in the reactor containment vessel 120 are not released to the outside world.

Therefore, according to the present embodiment, in the event of an accident, it is possible to remove heat for a long period of time by the outer pool, which improves the safety of the nuclear reactor. Further, since the substance in the reactor containment vessel is not released to the outside, the safety of the reactor is further improved. In addition, since the size of the reactor containment vessel can be reduced, the economical efficiency of manufacturing the reactor is improved. Furthermore, since the cooling water can be supplied to the outer peripheral pool by gravity, which is a natural force, the reliability of the equipment is improved.

Although not shown, the tenth embodiment of the present invention is used.
Also, the eleventh embodiment may be applied. Further, instead of the outer peripheral pool, a condenser for isolation may be installed, and the first to eighth embodiments may be applied to the cooling water pool.

[0121]

According to the present invention, it is possible to remove heat from the containment vessel for a long period of time in the event of an accident, thus improving the safety of the reactor. Even if an accident such as a breakage of the heat transfer tube of the condenser during isolation is assumed, the safety of the reactor is further improved because the substance in the reactor containment vessel is not released to the outside. In addition, since the size of the reactor containment vessel can be reduced, the economical efficiency of manufacturing the reactor is improved. Moreover, since the cooling water can be supplied to the cooling water pool by gravity, which is a natural force, the reliability of the device is improved.

[Brief description of drawings]

FIG. 1 is a vertical sectional view of a reactor containment facility according to a first embodiment of the present invention.

FIG. 2 is a vertical cross-sectional view of the reactor containment facility when the core submersion system is arranged in the first embodiment of the present invention.

FIG. 3 is a vertical sectional view of a reactor containment facility according to a second embodiment of the present invention.

FIG. 4 is a vertical cross-sectional view of a reactor containment facility according to a third embodiment of the present invention.

FIG. 5 is a vertical sectional view of a reactor containment facility according to a fourth embodiment of the present invention.

FIG. 6 is a vertical cross-sectional view of a reactor containment facility according to a fifth embodiment of the present invention.

FIG. 7 is a vertical cross-sectional view of a reactor containment facility according to a sixth embodiment of the present invention.

FIG. 8 is a vertical cross-sectional view of a reactor containment facility according to a seventh embodiment of the present invention.

FIG. 9 is a vertical sectional view of a reactor containment facility according to an eighth embodiment of the present invention.

FIG. 10 is a vertical cross-sectional view of a reactor containment facility according to a ninth embodiment of the present invention.

FIG. 11 is a longitudinal sectional view of a reactor containment facility according to a tenth embodiment of the present invention.

FIG. 12 is a vertical sectional view of a reactor containment facility according to an eleventh embodiment of the present invention.

FIG. 13 is a vertical sectional view of a reactor containment facility according to a twelfth embodiment of the present invention.

[Explanation of symbols]

 1: Reactor pressure vessel 2: Core 3: Main steam pipe 4: Water supply pipe 10: Reactor containment vessel 11: Dry well 12: Suppression pool 13: Wet well 15: Perimeter pool 16: Concrete structure wall 17: Vent pipe 18 : Communication hole 20: High pressure storage tank 21: Cooling water tank 22: Core submersion system piping 23: Automatic pressure reducing valve 24: Pipe line 25: Pipe line 26: Check valve 27: Check valve 28: Valve 30: Operating floor 31 : Pressure release plate 32: Air intake 33: Air cooling duct 81: Valve 82: Communication passage 83: Valve 84: Check valve 87: Duct 90: Cooling water tank 93: Water injection pipe 97: Check valve 99: Valve 101 : Pipeline 102: Pipeline 103: Check valve 104: Air cooling duct 105: Duct support part 106: Heat transfer pipe 107: Cooling water pool 108: Soluble stopper 109: Soluble stopper 11 0: Steam injection pipe 111: Overflow pipe 112: Isolation condenser 113: Cooling water pool 114: Pipe line 115: Valve 116: Pipe line 117: Pipe line 118: Pipe line 119: Cooling water tank 120: Reactor containment vessel 121: Reactor Building Crane 122: Temperature Control Unit 123: Circulating Blower 124: Steam Drum 125: Control Rod Drive Plug 126: Outlet Pipe Group 127: Reactor 128: Water Drum 129: Inlet Pipe Group 130: Fuel Exchanger 131: Upper part of refueling device 132: Vapor discharge pool 133: Perimeter pool 134: Atmosphere opening pipe 137: Underwater 140: Vacuum break valve 141: Blower 142: Pump 143: Cooler 144: Exhaust pipe 145: Blower 166: Circulation pump

Claims (18)

[Claims] 1. A nuclear reactor pressure vessel containing a nuclear fuel core, a nuclear reactor containment vessel containing the nuclear reactor pressure vessel, and steam generated in the reactor core from the nuclear reactor pressure vessel to an outside of the nuclear reactor containment vessel. A pressure suppression chamber having a main steam pipe for transporting to the facility, a space dry well in the reactor containment vessel, a suppression pool holding cooling water, and a wet well that is a vapor phase portion above the suppression pool; A reactor containment facility having a vent pipe connecting the dry well and the suppression pool, and further having a cooling water pool for removing heat from the reactor containment vessel during a long-term cooling process after an accident, wherein the water surface of the cooling water pool The cooling water in the cooling water pool which is located above and is connected to the cooling water pool in a closed loop and is heated by the isolation condenser and boils. Reactor containment facility is characterized in that a condensing means for condensing the vapor return the condensed water in the cooling water pool. 2. The nuclear reactor containment facility according to claim 1, wherein the condensing means is a heat transfer tube installed outside the nuclear reactor containment vessel at a position above the water surface of the cooling water pool,
A means for cooling the heat transfer tube, wherein steam generated in the cooling water pool flows through the heat transfer tube to be condensed, and the condensed water is returned to the cooling water pool by the hydrostatic head. 3. The reactor containment facility according to claim 2, wherein the means for cooling the heat transfer pipe is a duct that contains the heat transfer pipe and through which air flows. 4. The reactor containment facility according to claim 2, wherein the means for cooling the heat transfer pipe is a cooling water pool containing the heat transfer pipe. 5. The reactor containment facility according to claim 2, wherein the means for cooling the heat transfer pipe is seawater containing the heat transfer pipe. 6. The nuclear reactor containment facility according to claim 1, wherein the condensing means is a condensing tank installed outside the nuclear reactor containment vessel at a position above the water surface of the cooling water pool, and in the condensing tank. And a duct through which the coolant flows, the steam generated in the cooling water pool flows through the condensing tank and condenses, and the condensed water is returned to the cooling water pool by the hydrostatic head. Facility. 7. The reactor containment facility according to claim 1, wherein the condensing means is a cooling water tank installed outside the reactor containment vessel at a position above the water surface of the cooling water pool, and the cooling water. A pipe that connects the vicinity of the water surface of the pool and the vapor phase space of the cooling water tank to supply steam from the cooling water pool to the cooling water tank, and communicates with water in the cooling water pool and water in the cooling water tank to cool A reactor containment facility comprising: a pipe for returning condensed water from a water tank to a cooling water pool. 8. The nuclear reactor containment facility according to claim 1, wherein the condensing means is provided in a pipe for supplying steam from the cooling water pool and a pipe for returning condensed water to the cooling water pool, and the cooling water pool. Has a soluble plug that can be melted in response to the temperature rise, and during normal operation of the reactor, the condensing means is filled with cooling water, and in the event of an accident the soluble plug melts and the pipes communicate with each other. Reactor containment facility characterized by: 9. The reactor containment facility according to claim 1, wherein the condensing means is provided in a pipe for supplying steam from the cooling water pool and a pipe for returning condensed water to the cooling water pool, and the cooling water pool. Has a flexible plug that melts in response to the temperature rise, and when the reactor is in normal operation, the inside of the condensing means is in a low pressure state, and in the event of an accident, the flexible plug melts and the pipes communicate with each other. Reactor containment facility characterized by the following. 10. The nuclear reactor containment facility according to claim 1, wherein the condensing means has one end communicating with a pipe for returning condensed water to the cooling water pool, and the other end located above the uppermost part of the condensing means. Reactor containment facility, further comprising a pressure adjusting pipe that is opened to the atmosphere at. 11. A nuclear reactor pressure vessel containing a nuclear fuel core, a nuclear reactor containment vessel containing the nuclear reactor pressure vessel, and steam generated in the nuclear reactor from the nuclear reactor pressure vessel to an outside of the nuclear reactor containment vessel. Having a main steam pipe to transport to the facility,
A space drywell in the reactor containment vessel, a suppression pool having a suppression pool holding cooling water and a wet well that is a vapor phase portion above the suppression pool, and a vent pipe connecting the dry well and the suppression pool. And a reactor containment facility having a cooling water pool for removing heat from the reactor containment vessel in the long-term cooling process after the accident, in a position above the water surface of the cooling water pool outside the reactor containment vessel. A water pool condenser that is installed and has an overflow pipe, a pipe that supplies steam from the cooling water pool to the water in the water pool condenser, and a pipe that returns condensed water from the overflow pipe to the cooling water pool Reactor containment facility characterized by the following. 12. A nuclear reactor pressure vessel containing a nuclear fuel core, a nuclear reactor containment vessel containing the nuclear reactor pressure vessel, and steam generated in the core from the nuclear reactor pressure vessel to outside the nuclear reactor containment vessel. Having a main steam pipe to transport to the facility,
A space drywell in the reactor containment vessel, a suppression pool having a suppression pool holding cooling water and a wet well that is a vapor phase portion above the suppression pool, and a vent pipe connecting the dry well and the suppression pool. And a reactor containment facility having a cooling water pool for removing heat from the reactor containment vessel in the long-term cooling process after the accident, wherein the cooling water pool is located inside the gas phase space A reactor containment facility characterized in that it has a condenser through which the steam generated in the cooling water pool is condensed by the condenser and the condensed water is returned to the cooling water pool. 13. The reactor containment facility according to claim 12, wherein the coolant flowing inside the condenser is air. 14. The reactor containment facility according to claim 12, wherein the coolant flowing inside the condenser is seawater. 15. A reactor pressure vessel containing a reactor core made of nuclear fuel, a reactor containment vessel containing the reactor pressure vessel, and steam generated in the core from the reactor pressure vessel to outside the reactor containment vessel. Having a main steam pipe to transport to the facility,
A space drywell in the reactor containment vessel, a suppression pool having a suppression pool holding cooling water and a wet well that is a vapor phase portion above the suppression pool, and a vent pipe connecting the dry well and the suppression pool. And a reactor containment facility having a cooling water pool for removing heat from the reactor containment vessel in the long-term cooling process after the accident, wherein the cooling water pool is connected in a closed loop and heated by the isolation condenser. Condensing means for condensing the cooling water vapor of the cooling water pool that boils, and a pump that is installed in a pipe that connects the condensing means and the cooling water pool and that returns condensed water from the condensing means to the cooling water pool Reactor containment facility characterized by the following. 16. The nuclear reactor containment facility according to claim 15, further comprising a blower installed in a pipe connecting the cooling water pool and the condensing means, and supplying steam from the cooling water pool to the condensing means. Characteristic reactor containment equipment. 17. The reactor containment facility according to claim 1, 11, 12, or 15, wherein the cooling water pool includes an isolation condenser installed in a reactor containment vessel, A reactor containment facility, wherein a steam inlet of the isolation condenser is connected to the main steam pipe, and a condensed water outlet of the isolation condenser is connected to the suppression pool. 18. The reactor containment facility according to claim 1, wherein the cooling water pool is installed on an outer periphery of the reactor containment vessel, and the cooling water pool is installed on an outer wall of the reactor containment vessel. A reactor containment facility characterized in that it is in contact with the pressure suppression chamber through the reactor containment facility.