JP2903819B2 - Reactor containment pressure suppression equipment - Google Patents

Description

DETAILED DESCRIPTION OF THE INVENTION

[0001]

BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention removes heat energy emitted from a reactor outside a containment vessel when a coolant is supposed to be assumed in a safety design of the reactor, and removes the heat energy from the containment vessel. The present invention relates to a technique suitable for suppressing an increase in pressure.

[0002]

2. Description of the Related Art In a containment vessel having a pressure suppression function in the event of coolant loss, which is assumed in a safety design of a reactor, a static method using natural force to utilize decay heat during long-term cooling. JP-A-63-19
A natural heat radiating type storage container employing the outer pool cooling system described in Japanese Patent No. 1096 has been proposed. It is equipped with a cooling water pool on the outer periphery of the reactor containment vessel.The steam generated by the decay heat of the reactor core is guided from the vent pipe and condensed, and from the pressure suppression chamber, which becomes high temperature, through the steel containment wall. By transmitting heat to the outer peripheral pool, the containment vessel is cooled, and the pressure rise in the containment vessel is suppressed.

[0003]

When the natural heat radiation type containment vessel employing the peripheral pool type cooling system described in the above-mentioned patent publication is applied to a reactor having a relatively large output, the reactor is removed from the reactor core when the coolant is lost. As the decay heat released into the containment vessel increases in proportion to the reactor power, the amount of heat released outside the containment vessel also needs to be increased.

One of the methods for increasing the amount of heat radiation from the natural heat radiating type storage container is to increase the heat transfer area from the pressure suppression chamber to the outer peripheral pool. When a steel containment vessel wall is used as a heat transfer surface, the heat transfer area can be increased by increasing the diameter of the reactor containment vessel or increasing the vent pipe water depth to expand the area effective for heat transfer in the height direction. . However, an increase in the diameter of the containment vessel is not preferable because the pressure capacity of the containment vessel decreases. When the depth of the vent pipe is increased, a large amount of steam that has flowed out of the rupture into the dry well rapidly suppresses the pressure during the blowdown process in which the non-condensable gas in the dry well flows into the pressure suppression pool from the vent pipe. Since the rise of the pool water becomes large, it is necessary to increase the space above the pool water or to increase the strength of the structure in the pressure suppression chamber, which is not preferable.

SUMMARY OF THE INVENTION It is an object of the present invention to reduce a pressure increase in a reactor containment vessel due to a coolant loss accident without relying only on an increase in the diameter of the containment vessel or the depth of the vent pipe.

[0006]

According to a first aspect of the present invention, there is provided a reactor containment vessel having a heat transfer surface from a pressure suppression pool in a reactor containment vessel to an outer peripheral pool outside the reactor containment vessel. Water supply means for the two pools having a water supply source outside the containment vessel is provided, the water supply means is a pressurizing means for applying pressure to the water of the water supply source, the pressure suppression pool from the water supply source, A pressure suppression facility for a reactor containment vessel, comprising: a water supply passage to an outer peripheral pool.

The second means is the first means, wherein the water supply source is makeup water stored in a makeup water pool formed airtight outside the reactor containment vessel, and the pressurizing means is the reactor containment vessel. And a pressurized gas stored in the accumulator tank and connected to the gas phase space of the make-up water pool via a valve, and a pressurized gas stored in the accumulator tank. A first pipe provided with a valve in the liquid phase region and provided with a discharge port facing the pressure suppression pool, and a suction port provided in the liquid phase region of the makeup water pool on the way, and a discharge port provided with an outer peripheral pool; A pressure suppression system for a reactor containment vessel, characterized in that it is a second pipe facing the vessel.

The third means is the second means, wherein the makeup water pool is divided into at least a plurality of water storage areas by partitions, and the first water supply area is provided in at least one of the partitioned water storage areas.
A pressure suppression device for a containment vessel, wherein a suction port of a second pipe is provided in at least one of other areas as a suction port of a pipe.

The fourth means is the third means, wherein the amount of makeup water stored in the section of the makeup water pool provided with the suction port of the first pipe and the makeup water provided with the suction port of the second pipe are provided. The reactor containment vessel is characterized in that the ratio of the amount of make-up water stored in the pool section is equal to the ratio of the normal amount of cooling water in the suppression pool to the normal amount of cooling water in the outer pool. This is a pressure suppression facility.

A fifth means is that, in the fourth means, a ratio of a water amount in each section of the makeup water pool is set by adjusting a position of a partition in the makeup water pool in a direction adjacent to each section. This is a pressure suppression facility for a containment vessel characterized by the following.

Sixth means is a reactor containment vessel having a heat transfer surface from a pressure suppression pool in the containment vessel to an outer peripheral pool outside the containment vessel, wherein a water supply source is provided outside the containment vessel. Water supply means for the two pools, wherein the water supply means is provided as a plurality of independent water supply sources, and is pressurized to apply pressure to water of at least one of the plurality of water supply sources. Means, a water supply path from the one water supply source to the pressure suppression pool, and at least one other water supply source of the water supply source is provided at a position higher than the outer peripheral pool and has a water supply path to the outer peripheral pool. A pressure control system for a reactor containment vessel, characterized in that a water supply path to the outer peripheral pool is provided with a valve.

A seventh means is the sixth means, wherein the water supply source to which pressure from the pressurizing means is applied is cooling water accumulated in an airtight makeup water pool, and the pressurizing means comprises: A pressure suppression system for a reactor containment vessel, characterized in that the pipe is connected to the makeup water pool via a reactor pressure vessel and a valve.

Eighth means is a reactor containment vessel having a heat transfer surface from a pressure suppression pool in the containment vessel to an outer peripheral pool outside the containment vessel, wherein a water supply source is provided outside the containment vessel. A water supply means for the two pools, the water supply means being connected to a reactor pressure vessel via a valve to receive drive steam, a suction side of the turbine drive pump and the water supply source, And a pipe from the discharge side of the turbine drive pump to the pressure suppression pool and the outer peripheral pool.

The ninth means is a reactor containment vessel having a heat transfer surface from the pressure suppression pool in the containment vessel to the outer peripheral pool outside the containment vessel, wherein a water supply source is provided outside the containment vessel. A water supply means for supplying water to the inside of the dry well of both the pool and the reactor containment vessel, and a spray nozzle arranged in the dry well is connected to the water supply means for supplying water to the inside of the dry well; Water supply means into the supply water supply water is stored in the makeup water pool airtightly configured outside the reactor containment vessel, and the makeup water pool disposed outside the reactor containment vessel and the makeup water pool An accumulator tank connected to the gas phase space via a valve, a pressurized gas accumulated in the accumulator tank, a suction port provided in a liquid phase region in the makeup water pool, and a discharge port provided in a spray nozzle. A pipe connected to a pressure suppression system for a reactor containment vessel that characterized in that it comprises a valve provided in the middle of the pipe.

The tenth means includes a heat exchanger provided in a cooling water pool above a core position installed in a reactor pressure vessel in a drywell, and a heat transfer tube of the heat exchanger. A pipe for passing steam from the reactor pressure vessel, a valve provided in the middle of both pipes, a pipe for returning condensed water from the heat exchanger into the reactor pressure vessel, and a reactor pressure from the heat exchanger. A pipe for passing a gas into the suppression chamber, a reactor containment vessel including the drywell, the suppression chamber, and the cooling water pool; and a pressure suppression chamber provided outside the containment vessel and provided in the suppression vessel. An outer peripheral pool provided thermally connected to the pool with heat transfer means interposed therebetween, and a vent pipe for guiding steam from the cooling water pool to the outside of the containment vessel. The reactor pressure vessel is connected to the heat transfer tube of the reactor. And a pipe communicating between at least one of the pipe portion or the heat exchanger and the drywell between the valve and the heat exchanger provided in the middle of the pipe through which the steam from is passed. This is the pressure suppression equipment for the containment vessel. Eleventh means is the reactor containment vessel provided with a heat transfer surface from the pressure suppression pool in the reactor containment vessel to the outer peripheral pool outside the reactor containment vessel, wherein the water supply source is provided outside the reactor containment vessel. A water supply means for supplying water to both pools and the dry well of the reactor containment vessel, wherein the reactor containment vessel is made of steel and has a concrete structure for partitioning the pressure suppression chamber and the dry well in the reactor containment vessel. Object and the operating floor space above the concrete structure are covered around the concrete structure with a space communicating with the operating floor space interposed therebetween, and the space communicating with the operating floor includes a gas phase in the pressure suppression chamber. The region and the liquid phase region are communicated with each other by a communication port, and the outer peripheral pool is provided around the lower outer periphery of the reactor containment vessel in contact with the outer wall surface of the reactor containment vessel. A ventilation passage in contact with an outer wall surface of the containment vessel above the cooling vessel, wherein a ventilation inlet is provided at a lower portion of the ventilation passage and an outlet is provided at an upper portion thereof. This is a pressure suppression facility.

The twelfth means includes a heat exchanger installed in a cooling water pool above a core position installed in a reactor pressure vessel in a drywell, and a heat exchanger tube of the heat exchanger. A pipe for passing steam from the reactor pressure vessel, a valve provided in the middle of both pipes, a pipe for returning condensed water from the heat exchanger into the reactor pressure vessel, and a reactor pressure from the heat exchanger. A pipe for passing a gas into the suppression chamber, a reactor containment vessel including the drywell, the suppression chamber, and the cooling water pool; and a pressure suppression chamber provided outside the containment vessel and provided in the suppression vessel. An outer peripheral pool provided thermally connected to the pool via a heat transfer means, and a vent pipe for guiding steam from the cooling water pool to the outside of the reactor containment vessel; Is made of steel and A concrete structure defining a pressure suppression chamber and a drywell in a containment vessel and an operating floor space above the concrete structure are interposed around the concrete structure with a space leading to the operating floor space. In the space leading to the operation floor, the gas phase region and the liquid phase region in the pressure suppression chamber are communicated by a communication port, and the outer periphery of the lower part of the containment vessel serves as the heat transfer means. The outer peripheral pool is provided in contact with an outer wall surface of the containment vessel, and a ventilation path is provided in contact with the outer wall surface of the containment vessel above the outer peripheral pool,
A pressure suppression facility for a containment vessel, wherein a ventilation inlet is provided at a lower part of the ventilation path and an outlet is provided at an upper part thereof.

The thirteenth means includes a heat exchanger installed in a cooling water pool above a core position installed in a reactor pressure vessel in a dry well, and a heat exchanger tube of the heat exchanger. A pipe for passing steam from the reactor pressure vessel, a valve provided in the middle of both pipes, a pipe for returning condensed water from the heat exchanger into the reactor pressure vessel, and a reactor pressure from the heat exchanger. A pipe for passing a gas into the suppression chamber, a reactor containment vessel including the drywell, the suppression chamber, and the cooling water pool; and a pressure suppression chamber provided outside the containment vessel and provided in the suppression vessel. An outer peripheral pool provided thermally connected to the pool via a heat transfer means, and a vent pipe for guiding steam from the cooling water pool to the outside of the reactor containment vessel; The reactor pressure stored in A gravity drop water tank equipped at a position higher than the position of the core built in the vessel and the position of the pressure suppression chamber in the containment vessel was communicated with the reactor pressure vessel via a valve. A pressure storage injection system in which a gravity drop injection system, a pressure storage injection tank filled with cooling water at a high pressure exceeding a pressure corresponding to a head difference from the reactor core to the gravity drop water tank, and the reactor pressure vessel are connected via a valve. Three types of emergency systems: a water system, and a flooded system in which the intake port located at a position higher than the upper end of the core in the pressure suppression chamber in the containment vessel and the inside of the reactor pressure vessel are connected via a valve. A pressure suppression device for a containment vessel, wherein a water injection system is provided in the containment vessel.

Fourteenth means is a reactor containment vessel provided with a heat transfer surface from the pressure suppression pool in the containment vessel to the outer peripheral pool outside the containment vessel, wherein a water supply source is provided outside the containment vessel. Water supply means for supplying water to the inside of the dry well of the both containment pool and the reactor containment vessel, wherein the containment vessel is made of steel and forms a pressure suppression chamber and a dry well in the containment vessel. The concrete structure and the operating floor space above the concrete structure are covered around the concrete structure with a space leading to the operating floor space interposed therebetween, and the space leading to the operating floor includes the pressure suppression chamber. The gas phase region and the liquid phase region are communicated with each other through a communication port, and the position of the core built in the reactor pressure vessel stored in the reactor containment vessel and the reactor A gravity drop water injection system that communicates with the reactor pressure vessel via a valve a gravity drop water tank equipped at a position above the pressure suppression pool in the reactor containment vessel, and cools water from the core. A pressure accumulating water injection system in which a pressure accumulating water injection tank sealed at a high pressure exceeding a pressure corresponding to a head difference to the gravity falling water tank and the reactor pressure vessel are connected via a valve, and a pressure suppression in the reactor containment vessel. The reactor containment vessel is equipped with three types of emergency water injection systems, i.e., a flooding system in which an intake port located at a position higher than the upper end of the core in the pool and the inside of the reactor pressure vessel are connected via a valve. It is a pressure containment system for a reactor containment vessel characterized in that:

[0019]

[0020]

[0021]

[0022]

[0023]

[0024]

According to the first means, water is supplied from outside the containment vessel to the pressure suppression pool in the containment vessel and to the outer peripheral pool outside the containment vessel to raise the water level, thereby increasing the water-cooled heat transfer surface. The effect of expanding is obtained, and in obtaining the effect, the water level of the water supply source is pressurized to increase the water level by applying dynamic pressure to the water supply, so it is necessary to obtain the effect without using a dynamic device such as a pump. Can be.

According to the second means, in addition to the action of the first means, by opening the valve, the pressure in the accumulator tank is easily applied to the replenishing water level to make up the replenishing water into the pressure suppression pool and the outer peripheral pool. Water can be supplied, the water level of both can be raised, and the valve prevents the make-up water from flowing back due to the pressure in the pressure suppression chamber, ensuring that the raised water level is maintained and the atmosphere in the reactor containment vessel And prevents leakage from the container.

According to the third means, in addition to the action of the second means, the total amount of water supplied by the first and second pipes is determined by the section of the water storage area. The rise of the water level does not easily deviate from the assumed amount, and the rise of the water level can be accurately controlled.

According to the fourth means, in addition to the operation of the third means, the makeup water pool is configured such that the quantity of water supplied to the pressure suppression pool and the quantity of water supplied to the outer peripheral pool become the same in both pools. Since the makeup water in the inside is partitioned, the rise of the water level can be controlled to the same rise amount, and the effect of suppressing the deformation of the heat transfer surface by making the water pressure on both sides applied to the heat transfer surface the same can be obtained.

According to the fifth means, in addition to the operation of the fourth means, each section of the makeup water pool is set by adjusting the position of the partition in the makeup water pool in a direction adjacent to each section. Thus, the effect that the water amount ratio in each section can be set can be obtained.

According to the sixth means, water is supplied from outside the containment vessel into the pressure suppression pool inside the containment vessel and into the outer peripheral pool outside the containment vessel to raise the water level, thereby increasing the water-cooled heat transfer surface. The effect of expanding is obtained by raising the water level by supplying make-up water to the suppression pool by pressurizing the water surface of the water supply source, and by gravity from another water supply source by opening the valve and by gravity. This is achieved by supplying make-up water into the interior.

According to the seventh means, in addition to the action of the sixth means, since the water supply source has an airtight structure, the gas pressure can be used for the pressurizing means, so that it is easy to use. By opening and closing a valve in the middle of the water supply pipe, the water supply to the pressure suppression pool and the effect of preventing the atmosphere in the containment vessel from leaking outside and the backflow of the water supply can be obtained.

According to the eighth means, water is supplied from outside the containment vessel into the pressure suppression pool inside the containment vessel and into the outer peripheral pool outside the containment vessel to raise the water level, and the water-cooled heat transfer surface is provided. By opening the valve, the steam generated in the reactor pressure vessel is supplied to and driven by the turbine drive pump, and the water is raised by the turbine drive pump. By applying pressure, a function of supplying makeup water to the suppression pool and the outer pool is obtained, and the water level of the suppression pool and the outer pool rises.

According to the ninth means, water is supplied from outside the containment vessel into the pressure suppression pool inside the containment vessel and into the outer peripheral pool outside the containment vessel to raise the water level, and the water-cooled heat transfer surface is provided. The effect of expanding is obtained.Furthermore, the replenishment water of the water supply source which receives the pressure from the accumulator tank by opening each valve is sent to the spray nozzle side through the pipe, and water is sprayed from the spray nozzle into the dry well. The sprinkling water condenses the vapor leaking into the dry well and has the effect of cooling it.By closing the valve provided in the middle of the aforementioned pipe, the inside of the dry well that became high pressure by accident The effect of preventing the atmosphere from leaking to the water supply source is obtained.

According to the tenth means, the reactor containment vessel transfers heat from the pressure suppression pool to the outer peripheral pool to dissipate heat, and further receives the steam in the reactor pressure vessel into the heat exchanger and cools it with cooling water. The condensed water is returned to the reactor pressure vessel and used for cooling the core. The cooling pool water heated by the condensing action evaporates and is discharged from the vent pipe to the outside of the reactor containment vessel to be radiated. In this way, water cooling by the outer peripheral pool from the outside and the action of removing heat in the reactor containment vessel from the inside by condensation by the heat exchanger can be obtained. When a large pressure or a large amount of steam tries to enter the heat exchanger, part of the pressure escapes through the piping into the drywell to accelerate the depressurization in the reactor pressure vessel, and also increases the pressure in the reactor pressure vessel. When the drywell pressure rises relatively and the drywell pressure rises relatively, the vapor in the drywell flows back through the piping and condenses into the heat exchanger, condensing into the heat exchanger. The effect of continuing is obtained.

According to the eleventh means, water is supplied from outside the containment vessel into the pressure suppression pool inside the containment vessel and into the outer peripheral pool outside the containment vessel to raise the water level, and the water-cooled heat transfer surface is provided. The expanded and expanded heat transfer surface takes water from the lower part of the containment vessel, which is made of steel and has improved heat dissipation, and is water-cooled, the upper part is cooled by air, and the pressure is reduced during an accident. By diffusing the steam in the pressure suppression chamber into the operating floor space to suppress the condensation of steam and the partial rise in pressure. The effect of improving the pressure resistance of the device is obtained.

According to the twelfth means, the containment vessel transfers heat from the pressure suppression pool to the outer peripheral pool to radiate heat, and further receives steam in the reactor pressure vessel into the heat exchanger and cools it with cooling water. The condensed water is returned to the reactor pressure vessel and used for cooling the core. The cooling pool water heated by the condensing action evaporates and is discharged from the vent pipe to the outside of the reactor containment vessel to be radiated. Furthermore, heat is radiated from the lower part of the containment vessel, which is made of steel, which has improved heat dissipation, to the outer peripheral pool and water-cooled, and the upper part is cooled by air cooling. Diffusion to the space side, and diffusion of steam in the pressure suppression chamber to the operating floor space to suppress condensation of steam and partial rise in pressure. Thus, water cooling and air cooling from outside and heat inside The effect of improving the pressure resistance of the containment vessel is obtained by the synergistic effect of the condensation action by the exchanger and the widespread action of pressure and steam.

According to the thirteenth means, the reactor containment vessel transfers heat from the pressure suppression pool to the outer peripheral pool to dissipate heat, and further receives steam in the reactor pressure vessel into the heat exchanger and cools it with cooling water. The condensed water is returned to the reactor pressure vessel and used for cooling the core. The cooling pool water heated by the condensing action evaporates and is discharged from the vent pipe to the outside of the reactor containment vessel to be radiated. In this way, the function of removing the heat inside the reactor containment vessel from outside by water cooling by the outer peripheral pool and from the inside by condensation by the heat exchanger is obtained, and further, by opening the valve connected to the accumulator injection tank, The water in the high pressure sealed accumulator injection tank is injected into the relatively high pressure reactor pressure vessel immediately after the accident. Then, the water in the gravity falling water tank is injected by gravity into the reactor pressure vessel which has become relatively low in pressure.
Thereafter, water in the pressure suppression chamber is injected into the reactor pressure vessel at a lower pressure through the flooding system to cool the core in the reactor pressure vessel. As described above, in the reactor containment vessel, in addition to the depressurizing action by the heat exchanger, the cooling system is sequentially relayed so that long-term cooling is performed and the long-term depressurizing action can be continuously performed.

According to the fourteenth means, water is supplied from outside the containment vessel to the pressure suppression pool in the containment vessel and to the outer peripheral pool outside the containment vessel to raise the water level, and the water-cooled heat transfer surface is increased. The expanded and expanded heat transfer surface steals heat from the steel containment vessel, which has improved heat dissipation, and further diffuses the pressure to the operating floor space via the pressure suppression chamber in the event of an accident. By diffusing the steam in the pressure suppression chamber into the operation floor space, it suppresses the condensation of steam and the partial rise in pressure, and the synergistic effect of these effects improves the pressure resistance of the containment vessel. First, by opening the valve connected to the accumulator injection tank, the water in the accumulator injection tank filled with high pressure is first injected into the reactor pressure vessel still in a relatively high pressure state immediately after the accident. Then, the water in the gravity falling water tank is injected by gravity into the reactor pressure vessel which has become relatively low in pressure.
Thereafter, water in the pressure suppression chamber is injected into the reactor pressure vessel at a lower pressure through the flooding system to cool the core in the reactor pressure vessel. In this way, cooling from the outside of the reactor containment vessel can be performed efficiently, and inside the reactor, the cooling system can be relayed and activated in order to achieve long-term cooling and continue long-term depressurization. Can be

[0038]

[0039]

[0040]

[0041]

[0042]

[0043]

DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS First, a first embodiment will be described with reference to FIGS.

The containment vessel 8 is generally made of steel having better heat conductivity than concrete, and the inside thereof is filled with an inert gas for safety. The concrete structure in the containment vessel 8 defines a gravity falling water tank 21, a dry well 3, and a pressure suppression chamber 4 (not shown).

The annular space formed between the concrete structure and the containment vessel 8 communicates with the space on the operation floor above the concrete structure. The suppression chamber 4 includes a suppression pool 5 containing cooling water and a wet well 6 as a gas phase. The dry well 3 communicates with the pressure suppression pool 5 through a vent pipe 7. In the concrete wall 11 of the pressure suppression chamber 4, communication ports 14, 12, and 13 are opened, and the communication port 13 is disposed below the water surface of the pressure suppression pool 5 in a normal state and as close to the pool bottom as possible. The communication port 12 is provided at a position higher than the normal water level and lower than the water level of the pressure suppression pool 5 at the time of the accident, and the communication port 14 is provided further above the water level. Because of the arrangement of the communication ports, the cooling water in the suppression pool 5 also exists in the lower region of the annular space through the communication ports 13 and is in contact with the inner surface of the containment vessel 8.

The containment vessel 8 is surrounded by a concrete structure wall 80 with an annular space 83 interposed therebetween. The lower region of the annular space 83 is formed as an outer peripheral pool 9 below the horizontal partition 101, and cooling water is filled therein. The water level of the cooling water is the same as the water level of the pressure suppression pool 5, and the water pressure to the reactor containment vessel is considered to be the same from the inside and the outside, and the water pressure balance is considered, and the deformation of the containment wall due to the water pressure is suppressed. . Then, the water level at the normal time is raised by the high pressure steam or non-condensable gas discharged from the vent pipe 7 into the water of the pressure suppression pool 5 for several tens of seconds in the early stage of the accident, and the water surface of the pressure suppression pool 5 rises and the ceiling of the pressure suppression chamber 4 Is set low so as not to damage the. Along with this, the water level of the outer peripheral pool 9 is set low from the water pressure balance. The gas phase region of the outer peripheral pool 9 communicates with the outside world through a vent pipe 102.

The concrete structure wall 80 is provided so as to surround the containment vessel 8, and an air intake 81 leading to the annular space 83 slightly above the horizontal partition 101 is provided to the outside. At the top of the concrete structure wall 80, an air exhaust port 82 communicating from the annular space 83 to the outside is provided.

The reactor pressure vessel 2 is provided in the dry well 3. Cooling water is contained in the reactor pressure vessel 2, and a reactor core 1 in which nuclear reaction is controlled by a control rod is provided.

The cooling water in the reactor pressure vessel 2 which is heated in the reactor core 1 is converted into high-temperature and high-pressure steam, and the steam is sent to the turbine generator side. Is connected. A part of the main steam pipe 10 passes through the inside of the dry well 3.

An automatic pressure reducing system 26 having a relief safety valve which opens automatically when the pressure in the reactor pressure vessel 2 becomes excessive is connected to the main steam pipes 10 for each main steam pipe 10. The high-pressure steam discharge pipe 103 of the automatic pressure reducing system 26 is opened in the water of the suppression pool 5, and has a configuration in which excess high-temperature and high-pressure steam is condensed by the suppression pool water.

A concrete structure wall 80 containing the containment vessel 8 has an air intake 81 and an exhaust port 82 for cooling the outer surface of the containment vessel 8 above the outer peripheral pool 9 by natural ventilation. Have.

An emergency cooling system is housed in the reactor containment vessel 8 so that the emergency cooling system does not penetrate the wall of the reactor containment vessel 8 and the radioactivity is reduced through the emergency cooling system. Care is taken not to leave the storage container 8.

A pressure accumulating water injection system having a pressure accumulating water injection tank 20 which is located above the reactor pressure vessel 2 and communicates with the reactor pressure vessel 2 via a check valve 23 by piping as an emergency core cooling system; A gravity injection system having a gravity falling water tank 21 connected by piping to the reactor pressure vessel 2 via a check valve 24, and piping between the pressure suppression pool 5 and the reactor pressure vessel 2 via a check valve 25 And a submergence system 22 communicating with the submersion system.

A make-up water pool 30 is provided below the reactor containment vessel 8. The cooling water in the makeup water pool 30 is partitioned into an inner peripheral portion 31 and an outer peripheral portion 32 by a partition 33. However, the gaseous space 34 above both compartments communicates in both compartments. Pits 104 are provided at the bottom of the makeup water pool 30 at the inner peripheral portion 31 and the outer peripheral portion 32, respectively.

A pressure storage tank 35 in which a non-condensable gas (nitrogen or air) is filled at a high pressure is provided below the reactor containment vessel 8.

The inside of the pressure accumulation tank 35 and the inside of the gas phase space 34 of the makeup water pool 30 are connected by a pipe 36, and an opening / closing valve 37 is provided in the middle of the pipe 36.

The cooling water in the inner peripheral portion 31 of the makeup water pool 30 is communicably connected to the inside of the wet well 6 of the pressure suppression chamber 4 by a pipe 38. A check valve 40 for preventing a flow from the pressure suppression chamber 4 side to the makeup water pool 30 side is mounted in the middle of the pipe 38, and the reactor containment vessel is moved from inside the reactor containment vessel 8 to the makeup water pool 30 side. 8 is prevented from getting out. An opening of the pipe 38 on the side of the makeup water pool 30 is provided in a pit 104 in the inner peripheral portion 31.

The cooling water in the outer peripheral portion 32 of the make-up water pool 30 is communicably connected to the gas phase region in the outer peripheral pool 9 by a pipe 39. An opening of the pipe 39 on the side of the makeup water pool 30 is provided in a pit 104 in the outer peripheral portion 32.

The operation of the first embodiment will now be described with reference to FIGS.

In the event of a loss of coolant assumed in the safety design of the reactor, the coolant in the reactor pressure vessel 2 heated in the reactor core 1 is converted into high-temperature, high-pressure steam, for example, from the break point of the main steam pipe 10 to the dry well. Flow out to 3.

At the time of the accident, a control rod is inserted into the reactor core 1 so that the nuclear fission reaction in the reactor core 1 is stopped. In the reactor core 1, decay heat is generated for a long time after the control. When a decrease in the water level in the reactor pressure vessel 2 is detected by a water level gauge attached to the reactor pressure vessel 2 due to the outflow of the coolant from the break point, the water level is provided in the main steam pipe 3 based on the detection signal. The relief safety valve of the automatic pressure reducing system 26 operates in the opening direction in response to the operation signal to release the steam in the reactor pressure vessel 2 into the water in the suppression pool 5 through the exhaust pipe 103 to reduce the pressure in the reactor pressure vessel 2. Facilitate.

When the pressure in the reactor pressure vessel 2 becomes equal to the pressure stored in the accumulator injection tank 20 as the pressure in the reactor pressure vessel 2 decreases, the cooling water in the accumulator injection tank 20 becomes non-return valve. After passing through 23, injection into the reactor pressure vessel 2 starts. Immediately before the end of the water injection, the water falls from the gravity falling water tank 21 due to the difference between the water head in the gravity falling water tank 21 and the water head in the reactor pressure vessel and starts to be injected into the reactor pressure vessel 2. Immediately before the end of the injection, the pressure suppression pool 5 is caused by the head difference through the flooding system 22.
The cooling water in the reactor starts to be injected into the reactor pressure vessel 2. In this way, each emergency core cooling system and the like relays and injects cooling water into the reactor pressure vessel to maintain the flooding of the core 1 for a long time. Decay heat in the core 1 is removed by the evaporation of the cooling water. Evaporated vapor is dry well 3
Will be released. As a result, the pressure in the dry well 3 rises and pushes down the water in the vent pipe 7, and the steam flows into the suppression pool 5 and is condensed in the suppression pool water. Due to this condensation action, the amount of water in the pressure suppression pool 5 is increased, but the increased water is also used for water injection into the reactor pressure vessel 2 by the flooding system 22. The non-condensable gas in the dry well 3 at the time of the condensation is pushed out and entrained by the released steam, flows into the suppression pool, rises in the pool, and accumulates in the wet well 6. Although the water surface of the suppression pool 5 rises due to the rise, the ceiling of the suppression chamber 4 is not damaged because the water level is still close to the normal water level at this time.

After the blowdown process is completed, the opening / closing valve 37 is opened in response to an operation signal to the relief safety valve of the automatic pressure reducing system 26. This can be achieved by using the on-off valve 37 as a motor-operated valve and causing the motor-operated valve drive control unit to receive the operation signal to drive the valve in the valve opening direction.

When the on-off valve 37 is opened, the high-pressure gas stored in the pressure storage tank 35 is supplied to the gas-phase space 34 of the makeup water pool 30 through the pipe 36. As a result, the pressure of the gas phase space 34 increases, and the cooling water level on both the inner and outer peripheral portions of the makeup water pool 30 is pushed down. In such a state, the cooling water in the inner peripheral portion 31 of the makeup water pool 30 is injected into the pressure suppression chamber 4 through the pipe 38, and the outer peripheral portion 3
The cooling water in 2 is injected into the outer peripheral pool 9 through the pipe 39.

The makeup water pool 30 is divided into an inner peripheral portion 31 and an outer peripheral portion 32 by a partition 33, and the sectional area ratio between the inner peripheral portion 31 and the outer peripheral portion 32 is determined by dividing the sectional area ratio between the pressure suppression pool 5 and the outer peripheral pool 9. By making the area ratio equal, the water level rise amounts of the pressure suppression pool 5 and the outer peripheral pool 9 after water injection can be made equal. This suppresses the sudden deformation of the reactor containment vessel 8 due to the relative water level difference.

FIG. 2 shows a state in which the coolant of the makeup water pool 30 has been injected into the pressure suppression pool 5 and the outer peripheral pool 9 after the occurrence of the coolant loss accident from the normal operation state of the nuclear reactor. In this case, by measuring the water level at the insertion portion of the pipe 38 and closing the on-off valve 37 when the water level reaches the bottom of the makeup water pool, the high-pressure gas in the accumulator tank 35 is prevented from entering the pressure suppression chamber. I have. In addition, a non-condensable gas in the wet well 6 and a check valve 40 provided in the pipe 38
The pool water in the suppression pool 5 after the water level rises does not flow back into the makeup water pool 30. In addition, piping 38, 39
Is located in the pit 104 at the bottom of the make-up water pool 30, so that the cooling water in the make-up water pool can be injected in the direction of the water injection purpose as much as possible. Further, if cooling water remains in the pit 104, the non-condensable gas in the gas phase space 34 is prevented from flowing into the wet well 6 and the outer peripheral pool 9 by a water seal using the remaining water.

On the other hand, a part of the cooling water in the emergency cooling system, in particular, the cooling water in the gravity falling water tank 21 is poured into the reactor pressure vessel, and then overflows from the break point to submerge the lower space of the dry well 3. Let it. Therefore, in the gravity fall water tank 21 disposed above the reactor pressure vessel 2, only the amount of water necessary for cooling the reactor core 1 and submerging the lower space of the dry well 3 is secured, and the pressure suppression pool 5 and the outer peripheral pool 9 are secured. A large amount of cooling water required for raising the water level of the water is secured in a make-up water pool 30 disposed below the reactor containment vessel 8.

FIG. 3 is an enlarged view of the state after the water levels of the pressure suppression pool 5 and the outer peripheral pool 9 have risen by L ₁ due to the cooling water in the makeup water pool 30. That is, the water levels of the pressure suppression pool 5 and the outer peripheral pool 9 rise from the water level during normal operation indicated by the broken line in FIG.

In such a state, the pressure suppression pool 5
The rise in the water level between the pool and the outer peripheral pool 9 achieves an increase in the heat transfer surface height of the water cooling area of each pool and the heat capacity absorbed by the cooling water of each pool.

In addition, the following effects can be obtained by the communication ports 12 and 13 provided in the concrete structure wall 11 that partitions the pressure suppression pool 5 into the inner peripheral portion and the outer peripheral portion. That is, the pressure suppression pool 5 that has been heated to a high temperature due to the latent heat of condensation of the steam flowing from the vent pipe 7 passes through the communication port 12 installed above the water level of the pressure suppression pool during normal operation.
It flows out to the inner wall surface side of the steel containment vessel 8 and is cooled by the outer peripheral pool 9. Thereafter, the fluid flows into the inner peripheral portion of the suppression pool 5 from the communication port 13 provided close to the bottom of the suppression pool, and mixes with the low-temperature water stagnated at a position lower than the outlet of the vent pipe 7. Thus, the temperature stratification phenomenon in the pressure suppression pool 5 can be reduced. As a result, the high-temperature region effective for heat radiation to the outer peripheral pool 9 can be expanded to a position lower than the vent pipe, and the amount of heat radiation from the reactor containment vessel 8 can be greatly increased.

The heat in the reactor containment vessel 8 is transferred to the suppression pool 5 in the form of steam to heat the cooling water in the pool 5. The heated cooling water has a high temperature and generates a large temperature difference from the cooling water temperature in the outer peripheral pool 9. The region in which the large temperature difference occurs is as shown by an arrow in FIG. Can be expanded to

For this reason, the entire area of the pressure suppression pool 5 can be used as an area for accumulating heat in the reactor containment vessel 8, and the amount of heat stored in the pool 5 can be expanded. Then, a large amount of heat can be transferred to the cooling water in the outer peripheral pool 9 via the wall of the reactor containment vessel 8 due to the expansion of the region where a large temperature difference occurs with respect to the outer peripheral pool 9. The cooling water in the outer peripheral pool 9 receives heat from the containment vessel 8, evaporates when it reaches 100 degrees under the atmospheric pressure, and is released to the outside from the vent pipe 102, and accordingly, heat is also released to the outside. The Rukoto.

When the vent pipe 7 is at a deep position,
When the cooling water is convected by the fluid discharged from the pool, the rising of the water surface of the pool 5 caused by the gas blown into the cooling water from the vent pipe 7 at the time of the initial condensation action becomes large, so that the height of the pressure suppression chamber is increased. As a result, the reactor containment vessel 8 is increased in size. In this embodiment, a large amount of heat can be efficiently radiated to the outside without increasing the size.

The wet well 6 communicates with the upper space of the operation floor (operation floor) through the communication port 14, so that the substantial volume of the wet well 6 increases, and the pressure inside the containment vessel 8 increases. Suppress.

Further, as time elapses after the accident, the temperatures of the pressure suppression pool 5 and the wet well 6 rise, and a temperature difference from the outside air occurs. The hot air in the wet well 6 escapes into the annular space along the inner wall surface of the containment vessel 8 through the communication port 14 after the water is increased in the pressure suppression chamber, moves to the upper space of the operation floor, and moves to the upper space of the containment vessel 8. Heat. The heated containment vessel 8 is
The heat is dissipated to the annular space 83 between the concrete structure wall 80 and the annular space 83.

Upon receiving the heat radiation, the atmosphere in the annular space 83 is heated and becomes an updraft. The rising air current rises and is exhausted to the outside from the air exhaust port 82, and heat is also radiated to the outside at the same time. Along with the exhaust, outside air naturally flows into the annular space 83 from the air intake 81. Annular space 8
The temperature of the air flowing into the reactor 3 increases due to heat radiation from the wall of the containment vessel 8, and the air is discharged from the exhaust port 82, so that an air cooling function by natural ventilation is continuously generated.

As described above, the outer peripheral pool cooling system below the reactor containment vessel 8 and the natural ventilation type cooling system above it can be used together. This promotes efficient heat radiation from the entire periphery of the reactor containment vessel and suppresses the pressure inside the reactor containment vessel.

As described above, the accumulator tank 35 filled with the high-pressure gas is connected to the make-up water pool 30, and the coolant in the make-up water pool 30 is used by utilizing the pressure of the gas in the accumulator tank 35 at the time of the loss of the coolant. Suppression pool 5 and outer pool 9
By increasing the water level of both pools by increasing the water level, the heat transfer area between the cooling waters of both pools and the heat capacity of the pools due to the large amount of cooling water can be increased. For this reason, the heat radiation characteristic of the outer peripheral pool type cooling system is improved, and it can be applied to a plant with a higher output. In addition, since it is not necessary to inject water from the gravity fall water tank 21 to the pressure suppression pool 5, the gravity fall water tank 21 holds only the amount of water necessary for cooling the reactor core 1 and submerging the space below the dry well 3. Therefore, the amount of water held in the gravity falling water tank 21 can be greatly reduced, and the position of the center of gravity of the containment vessel 8 is lowered, thereby improving the earthquake resistance.

Next, a second embodiment will be described with reference to FIG. The differences from the first embodiment are as follows.
The description of the common parts with the first embodiment is omitted.

The inner peripheral portion 31 of the make-up water pool 30 is enlarged from the center of the reactor storage area to increase the amount of cooling water retained in the inner peripheral portion 31. A pipe 3 communicating from the inner peripheral portion 31 of the makeup water pool 30 to the dry well 6 of the pressure suppression pool 5
A pipe 41 branched from the middle of 8 is provided to extend to an upper region of the dry well 3. A spray facility having a spray nozzle 42 is connected to the pipe 41, and the spray facility is provided in an upper region of the dry well 3.

In this embodiment, at the time of an accident, the makeup water pool 3
In addition to injecting the cooling water in the inner peripheral part 31 of the water supply pool 5 into the pressure suppression pool 5, a part of the cooling water in the inner peripheral part 31 of the makeup water pool 30 is passed through the pipe 41 and the nozzle 42 into the dry well 3. Can be sprayed on.

As a result, the vapor filled in the dry well 3 at the time of the accident is condensed, and the pressure rise in the dry well 3 is suppressed. Since the sprayed cooling water accumulates in the lower space of the dry well 3, the amount of water held in the gravity falling water tank 21 used for flooding the lower dry well can be further reduced.

The other operations are the same as those of the first embodiment, so that the description thereof is omitted here.

Next, a third embodiment will be described with reference to FIG. The differences from the first embodiment are as follows.
The description of the common parts with the first embodiment is omitted.

The steam generated in the reactor core 1 is changed to the pressure suppression pool
The exhaust pipe 103 of the automatic pressure reducing system 26 that opens to the
One end of a pipe 43 having a pipe 4 is provided in communication. The other end of the pipe 43 is connected to the gas-phase space 34 of the makeup water pool 30.

A cooling water pool 45 is provided in the annular space 83 between the containment vessel 8 and the concrete structure wall 80 and above the horizontal partition 101. The cooling water pool 45 is connected to the outer peripheral pool 9 from the bottom thereof through a pipe 46 provided with an on-off valve 47 on the way. And make-up water pool 30
The inner partition is eliminated, and there is no section between the inner peripheral portion and the outer peripheral portion.

In this embodiment, the on-off valve 44 is opened in response to the operation signal of the relief safety valve of the automatic pressure reducing system 26. This allows
Part of the high-pressure steam generated in the reactor core 1 to be exhausted through the exhaust pipe 103 at the time of the accident flows from the exhaust pipe 103 of the automatic pressure reducing system 26 to the gas phase space 34 of the makeup water pool 30 through the pipe 43. As a result, as in the embodiment shown in FIG. 1, the pressure in the gas phase space 34 increases, and the liquid level in the makeup water pool 30 is pushed down. Therefore, the cooling water is injected into the pressure suppression pool 5 from the pipe 38 inserted into the cooling water of the makeup water pool 30. Since the steam supplied to the makeup water pool 30 through the pipe 43 is primary cooling water having radioactivity, it is used for injecting water into the outer peripheral pool 9 which leads to the outside as in the embodiment shown in FIG. Can not. For this reason, the cooling water pool 45 located above the outer peripheral pool 9
The opening and closing valve 47 is opened at the same time as the operation of the opening and closing valve 44 so that the cooling water is injected into the outer peripheral pool 9 through the pipe 46 due to the gravity difference. In order to operate the opening / closing valves 44 and 47, the operation signals supplied to the relief safety valves are also supplied to the opening / closing valves 44 and 47 to adjust the operation timing. The other operations are the same as those of the first embodiment, so that the description thereof is omitted here.

Next, a fourth embodiment will be described with reference to FIG. The differences from the first embodiment are as follows.
The description of the common parts with the first embodiment is omitted.

The turbine drive pump 50 is provided below the pressure suppression chamber 4. In order to supply steam to the turbine section of the turbine drive pump 50, the main steam pipe 10 and the turbine section are connected by a pipe 48 provided with an on-off valve 49 in the middle.
The pump suction side of the turbine drive pump 50 and the cooling water of the makeup water pool 30 are connected by a pipe 51 so as to communicate. The pump discharge side of the turbine drive pump 50 and the inside of the pressure suppression chamber 4 are connected to each other by a pipe 52. Similarly, the pump discharge side of the turbine drive pump 50 and the inside of the outer peripheral pool 9 are connected to each other by a pipe 53.

In the present embodiment, the operation signal to the relief safety valve of the automatic pressure reducing system 26 is received by the opening / closing valve 49, and the opening / closing valve 49 is opened. By doing so, a part of the steam generated in the still high pressure core 1 immediately after the accident can be supplied to the turbine of the turbine drive pump 50 through the pipe 44. As a result, the steam turbine rotates, the cooling water in the makeup water pool 30 is sucked through the pipe 51 by the turbine drive pump 50, and the cooling water flows into the pressure suppression pool 5 and the outer peripheral pool 9 via the pipes 52 and 53 on the pump discharge side. Water is injected. The other operations are the same as those of the first embodiment, so that the description thereof is omitted here.

Next, a fifth embodiment will be described.

The containment vessel 8 is made of steel and is filled with an inert gas. A concrete structure in the containment vessel 8 defines a gravity falling water tank 21, a cooling water pool 61, a dry well 3, and a pressure suppression chamber 4.

The annular space formed between the concrete structure and the containment vessel 8 communicates with the space on the operation floor above the concrete structure. The suppression chamber 4 includes a suppression pool 5 containing cooling water and a wet well 6 as a gas phase. The dry well 3 communicates with the pressure suppression pool 5 through a vent pipe 7. In the concrete wall 11 of the pressure suppression chamber 4, communication ports 14, 12, 13 are opened. The communication port 13 is disposed below the water surface of the pressure suppression pool 5 in a normal state and as close to the pool bottom as possible. The communication port 12 is provided at a position below the normal water surface and above the communication port 13. The communication port 14 is provided further above the water surface. Because of the arrangement of the communication ports, the cooling water in the pressure suppression pool 5 also exists in the lower region of the annular space through the communication ports 12 and 13 and is in contact with the inner surface of the containment vessel 8.

The containment vessel 8 is surrounded by a concrete structure wall 80 with an annular space 83 interposed therebetween. The lower region of the annular space 83 is the outer peripheral pool 9 below the horizontal partition 101. Cooling water is put in the outer peripheral pool 9. The water level of the cooling water is the same as the water level of the pressure suppression pool 5, and the water pressure to the reactor containment vessel is considered to be the same from the inside and the outside, and the water pressure balance is considered, and the deformation of the containment wall due to the water pressure is suppressed. . And
Normally, the water level is at the early stage of the accident for several tens of seconds.
The pressure suppression pool 5 is set low so that the water surface of the suppression pool 5 rises due to high-pressure steam or inert gas discharged into the water and does not damage the ceiling of the suppression chamber 4. Along with this, the water level of the outer peripheral pool 9 is set low from the water pressure balance. The gas phase region of the outer peripheral pool 9 communicates with the outside world through a vent pipe 102.

The concrete structure wall 80 is provided so as to surround the containment vessel 8, and an air intake port 81 communicating with the outside world is provided slightly above the horizontal partition 101 so as to communicate with the annular space 83. At the top of the concrete structure wall 80, an air exhaust port 82 communicating from the annular space 83 to the outside is provided.

The reactor pressure vessel 2 is provided in the dry well 3. Cooling water is contained in the reactor pressure vessel 2, and a reactor core 1 in which nuclear reaction is controlled by a control rod is provided.

The cooling water in the reactor pressure vessel 2 which is heated by the reactor core 1 is converted into high-temperature and high-pressure steam, and the steam is sent to the turbine generator side. Is connected. A part of the main steam pipe 10 passes through the inside of the dry well 3.

An automatic pressure reducing system 26 having a relief safety valve which opens automatically when the pressure in the reactor pressure vessel 2 becomes excessive is connected to each main steam pipe 10. The high-pressure steam discharge pipe 103 of the automatic pressure reducing system 26 is opened in the water of the suppression pool 5, and has a configuration in which excess high-temperature and high-pressure steam is condensed by the suppression pool water.

An emergency cooling system is accommodated in the reactor containment vessel 8 so that the emergency cooling system does not penetrate the wall of the reactor containment vessel 8 and the radioactivity is reduced through the emergency cooling system. Care is taken not to leave the storage container 8.

As an emergency core cooling system, a pressure accumulating water injection system including a pressure accumulating water injection tank 20 which is located above the reactor pressure vessel 2 and is connected to the reactor pressure vessel 2 via a check valve 23 by piping, A gravity injection system having a gravity falling water tank 21 connected by piping to the reactor pressure vessel 2 via a check valve 24, and piping between the pressure suppression pool 5 and the reactor pressure vessel 2 via a check valve 25 And a submergence system 22 communicating with the submersion system.

The cooling water pool 61 is sealed by a concrete structure, and the gas phase space above the pool is solely connected to the outside world by the exhaust pipe 70. In the cooling water of the cooling water pool 61, a plurality of heat exchangers 60 of a steam condensation type cooling system are provided in contact with the cooling water. The heat exchanger 60 of the steam condensing type cooling system equipment is a shell and tube type heat exchanger, and includes a plurality of heat transfer tubes 65 and plenums 64 and 66 connected to upper and lower portions of the heat transfer tubes 65. The upper plenum 64 is connected to the main steam pipe 10 via a pipe 62 via an on-off valve 63. In the lower plenum 66,
A pipe 67 is connected from the bottom of the lower plenum 66 to the reactor pressure vessel 2 via a check valve 68. A pipe 69 communicates with the cooling water in the pressure suppression pool 5 from an intermediate height of the lower plenum 66.

In the event of a loss of coolant assumed in the safety design of the reactor, the coolant in the reactor pressure vessel 2 heated in the reactor core 1 is converted into high-temperature and high-pressure steam, for example, from the break point of the main steam pipe 10 to the dry well. Flow out to 3.

At the time of the accident, a control rod is inserted into the reactor core 1 so that the nuclear fission reaction in the reactor core 1 is stopped. In the reactor core 1, decay heat is generated for a long time after the control. When a decrease in the water level in the reactor pressure vessel 2 is detected by a water level gauge attached to the reactor pressure vessel 2 due to the outflow of the coolant from the break point, the water level is provided in the main steam pipe 3 based on the detection signal. The relief safety valve of the automatic pressure reducing system 26 operates in the opening direction in response to the operation signal to release the steam in the reactor pressure vessel 2 into the water in the suppression pool 5 through the exhaust pipe 103 to reduce the pressure in the reactor pressure vessel 2. Facilitate.

When the pressure in the reactor pressure vessel 2 becomes equal to the pressure stored in the accumulator injection tank 20 as the pressure in the reactor pressure vessel 2 decreases, the cooling water in the accumulator injection tank 20 becomes non-return valve. After passing through 23, injection into the reactor pressure vessel 2 starts. Immediately before the end of the water injection, the water falls from the gravity falling water tank 21 due to the difference between the water head in the gravity falling water tank 21 and the water head in the reactor pressure vessel and starts to be injected into the reactor pressure vessel 2. Immediately before the end of the injection, the pressure suppression pool 5 is caused by the head difference through the flooding system 22.
The cooling water in the reactor starts to be injected into the reactor pressure vessel 2. In this way, each emergency cooling system relays and injects cooling water into the reactor pressure vessel to maintain the flooding of the reactor core 1 for a long time. Decay heat in the core 1 is removed by the evaporation of the cooling water. Evaporated vapor is released to the dry well 3 from the break. As a result, the pressure in the dry well 3 rises, pushing down the water in the vent pipe 7, and the steam is released from the pressure suppression pool 5.
And is condensed in the suppression pool water. Due to this condensation action, the amount of water in the pressure suppression pool 5 is increased, but the increased water is also used for water injection into the reactor pressure vessel 2 by the flooding system 22. The non-condensable gas in the dry well 3 at the time of the condensation is pushed out and entrained by the released steam, flows into the suppression pool, rises in the pool, and accumulates in the wet well 6. Due to the rise, the suppression pool 5
Although the water surface rises, the ceiling of the pressure suppression chamber 4 is not damaged at this point because the water level is still close to the normal water level.

After the blowdown process is completed, the on-off valve 63 is opened in response to an operation signal to the safety relief valve of the automatic pressure reducing system 26. This can be achieved by using the on-off valve 63 as a motor-operated valve and causing the motor-operated valve drive control unit to receive the operation signal to drive the valve in the valve opening direction.

Until the blow-down process, the pressure increase pool 5 absorbs the initial pressure rise of the dry well 3.
Thereafter, when the on-off valve 63 is opened, a part of the steam generated in the reactor core 1 flows into the heat exchanger 60 through the pipe 62 connected to the main steam pipe 10, whereby the steam condensing cooling system operates. The steam flowing into the heat exchanger 60 is supplied to the upper plenum 6.
4, is distributed into the heat transfer tubes 65, and is cooled and condensed by the cooling water in the pool 61. The condensed water flows down to the lower plenum 66 along the inner surface of the heat transfer tube 65, and some uncondensed steam and non-condensable gas also flow into the lower plenum 66.
The lower plenum 66 has a pipe 67 at the bottom and a pipe 6 at the middle.
8 are provided, and condensed water and non-condensable gas are separated according to the height difference between these pipe inlets. The condensed water returns to the reactor pressure vessel 2 by gravity through the pipe 67, while the non-condensable gas flows from the pipe 68 into the suppression pool 5 and accumulates in the wet well 6. The temperature of the shell-side pool 61 water, which condenses the steam flowing through the heat transfer tube 65, rises due to the latent heat of condensation. The cooling water pool 61 is open to the atmosphere and reaches a saturation temperature at 100 ° C., after which the water of the pool 61 evaporates and is discharged from the exhaust pipe 70 to the outside of the reactor containment vessel 8, and is generated in the reactor core 1. Decay heat can be removed.

Further, as in the sixth embodiment shown in FIG. 8, a pipe 62 connecting one end to the dry well 3 is connected to a pipe 62 connecting the main steam pipe 10 and the heat exchanger 60.
In a modification of the embodiment, when the pressure in the reactor pressure vessel 2 is high in the early stage after the accident, a part of the steam generated in the reactor core 1 flows out into the dry well 3 through the pipe 71 branched from the pipe 62. As a result, depressurization of the reactor pressure vessel 2 is promoted, so that water can be quickly injected from the accumulator water injection tank 20 or the gravity falling water tank 21. When the pressure in the dry well 3 rises later in the accident, the steam containing the non-condensable gas in the dry well 3 flows into the heat exchanger 60 through the pipe 71, and the steam condensing ability is improved. Further, even when the on-off valve 63 fails, the steam in the dry well 3 flows into the heat exchanger 60 from the pipe 71.
The reliability of the cooling system using the heat exchanger 60 is improved.

On the other hand, the dry well 3
A part of the steam containing the non-condensable gas in the pressure suppression pool 5
As a result, the heat transferred to the pressure suppression pool 5 is contacted with the reactor containment wall by the convection of the cooling water in the pressure suppression pool 5 through the communication ports 12 and 13 so that the heat transferred to the inside of the outer peripheral pool 9. Transfer heat into cooling water. Outer pool 9
The cooling water inside evaporates due to the heat and evaporates.
02, the heat is also released to the outside. Such an outer pool cooling system also operates.

Further, the wet well 6 is connected to the communication port 1.
4 communicates with the upper space of the operation floor, the substantial volume of the wet well 6 increases, and the pressure inside the containment vessel 8 is suppressed from rising.

Further, with the lapse of time after the accident, the temperatures of the pressure suppression pool 5 and the wet well 6 rise, and a temperature difference from the outside air occurs. The hot air in the wet well 6 escapes into the annular space along the inner wall surface of the containment vessel 8 through the communication port 14 after the water is increased in the pressure suppression chamber, and moves to the upper space of the operation floor, and the wall surface of the containment vessel 8 Heat. The heated containment vessel 8 is
The heat is dissipated to the annular space 83 between the concrete structure wall 80 and the annular space 83.

Upon receiving the heat radiation, the atmosphere in the annular space 83 is heated and becomes an updraft. The rising air current rises and is exhausted to the outside from the air exhaust port 82, and heat is also radiated to the outside at the same time. With the exhaust, outside air naturally flows into the annular space 83 from the air intake 81. Annular space 8
The temperature of the air flowing into the reactor 3 increases due to heat radiation from the wall of the containment vessel 8, and the air is discharged from the exhaust port 82, so that an air cooling function by natural ventilation is continuously generated.

As described above, the steam condensing type cooling system, the outer peripheral pool type cooling system below the containment vessel 8, and the natural ventilation type cooling system above it can be used together. This promotes efficient heat radiation from the entire periphery of the reactor containment vessel and suppresses the pressure inside the reactor containment vessel. The temperature change of the embodiment shown in FIG. 7 will be described with reference to FIGS. FIG. 9 shows the change in the amount of decay heat generated in the reactor core 1 after the coolant loss accident. The steam condensing type cooling system, the outer peripheral pool type cooling system, and the natural ventilation type cooling system for cooling the reactor containment vessel 8 are shown in FIG. FIG. 10 conceptually shows a change in the temperature of the pressure suppression pool 5 when used together. Also in the present embodiment, when a decrease in the water level in the reactor pressure vessel 2 is detected due to the outflow of the coolant from the break point,
The automatic pressure reducing system 26 provided in the main steam pipe 3 is operated, and the steam in the reactor pressure vessel 2 is opened to the suppression pool 5,
Depressurization of the reactor pressure vessel 2 is promoted. Reactor pressure vessel 2
As the pressure decreases, the cooling water is sequentially injected into the reactor pressure vessel 2 by the pressure difference and the gravity difference from the pressure accumulating water injection tank 20, the gravity falling water tank 21 and the flooding system 22, and the flooding of the reactor core 1 is maintained. The decay heat in the reactor core 1 is removed by the evaporation of the cooling water, and the steam is released to the dry well 3 from the fracture. As a result, the pressure in the dry well 3 rises and pushes down the water in the vent pipe 7, and the steam flows into the suppression pool 5 and condenses in the pool water, so that the temperature of the suppression pool 5 increases (see FIG. 9A). Up to the point). After the blowdown process is completed, the steam condensing type cooling system is operated by opening the on-off valve 63 in response to the operation signal of the automatic pressure reducing system 26, and a temperature difference between the pressure suppression pool 5 and the outer peripheral pool 9 is generated. Therefore, the outer pool cooling system also operates to cool the containment vessel 8. In the steam condensing type cooling system, since the water of the pool 61 evaporates after the water of the pool 61 reaches the saturation temperature, the water level of the pool 61 decreases with the lapse of time after the accident, and the amount of heat radiation decreases. The heat exchange 60
The steam that cannot be condensed flows into the pressure suppression pool 5 from the pipe 69 together with the non-condensable gas in the dry well 3. As a result, the flow rate of steam flowing into the suppression pool 5 increases, the water temperature of the suppression pool 5 rises, and the temperature difference with the outer pool 9 increases, so that the outer pool 9 passes through the steel containment wall 8. By increasing the amount of heat radiation to the pressure suppression, the rise in the water temperature of the pressure suppression pool 5 is suppressed.

After the loss of the water in the pool 61 of the steam condensing type cooling system (at the time point b in FIG. 9), the water temperature of the outer peripheral pool 9 rises due to an increase in the heat radiation amount of the outer peripheral pool type cooling system. After the water temperature of the outer peripheral pool 9 reaches the saturation temperature of 100 ° C., the outer pool water 9 evaporates and the water level drops, so that the heat radiation amount of the outer peripheral pool cooling system decreases. As an example of a means for suppressing a decrease in the water level of the outer peripheral pool 9, a makeup water source (not shown) shared by several reactors is provided in the construction site,
There is a method of supplying cooling water to the outer peripheral pool 9 of the reactor where the accident has occurred. However, even if the makeup water source for the outer peripheral pool 9 is provided, there is a limit to the make-up water capacity, and the water level of the outer peripheral pool 9 decreases with the lapse of time after the accident, and the heat radiation amount of the outer peripheral pool cooling system decreases. Therefore, the temperature of the pressure suppression pool 5 and the temperature of the wet well 6 rise. Wet well 6
Communicates with the concrete structure wall 80 via the upper wall of the steel containment vessel 8 from the wet well 6 space, which has become hot, because it communicates with the upper space of the operating floor in the containment vessel 8. The heat is dissipated to the annular space 83 therebetween. From the space of the wet well 6 above the containment vessel 8 to the annular space 83
As a result, the temperature of the air flowing in from the intake 81 rises, and the air is exhausted from the exhaust port 82, so that the amount of heat released by natural ventilation cooling increases. As described above, in the latter half of the accident, the reactor containment vessel 8 can be cooled by using both the outer peripheral pool type cooling system and the natural ventilation type cooling system, so that the rise in the water temperature of the pressure suppression pool 5 is suppressed.

Outer pool 9 water lost (at time c in FIG. 9)
After that, the amount of decay heat generated in the reactor core 1 is considerably reduced, and the reactor containment vessel 8 can be cooled by the natural ventilation type cooling system alone. The temperature decreases. Therefore, by assuming a time when the amount of decay heat generated in the reactor core 1 and the amount of heat released by the natural ventilation cooling system alone are balanced, the amount of replenishment water in the outer peripheral pool 9 is determined, thereby eliminating the need for operator operation in the event of an accident. (Walk away time) can be made almost infinite.

A seventh embodiment will be described with reference to FIG. This embodiment is basically a combination of the embodiment shown in FIG. 1 and the embodiment shown in FIG. In the present embodiment, an outer pool cooling system and a steam condensing cooling system for injecting the cooling water of the makeup water pool 30 into the pressure suppression pool 5 and the outer pool 9 using the high-pressure gas in the accumulator tank 35 after the accident are provided. Thus, the heat radiation characteristics from the containment vessel 8 are further improved. Compared to the embodiment of FIG. 7, the heat dissipation capacity of the outer pool cooling system is increased, and when applied to a reactor plant of the same output, the number of heat exchangers 60 of the steam condensing cooling system is reduced. Or reactor containment vessel 8
Can be reduced in size. The reactor containment vessel 8
When the shapes of the reactors are the same, the output of the applicable nuclear power plant can be increased. Also, the embodiment shown in FIGS. 5 and 6 and the embodiment shown in FIG. 7 can be combined in the same manner, and an operation equivalent to that of the embodiment shown in FIG. 10 can be obtained.

As described above, even when applied to a plant having a large output, the steam condensing type cooling system and the natural ventilation type cooling system are provided above the reactor containment vessel 8 and the outer peripheral pool type cooling system is provided below the reactor containment vessel. By using the cooling system equipment of the system together, the reactor containment 8 can be efficiently cooled according to the attenuation of the decay heat generated in the reactor core 1 without excessively increasing the shape and the amount of the reactor containment 8. Pressure rise during an accident. In addition, by using a static containment cooling system together with the plant, safety and reliability of the plant can be improved, and the operation unnecessary time of the plant operator can be extended in the event of an accident. It is reduced.

[0117]

According to the first aspect of the present invention, the water cooling heat transfer surface after an accident can be enlarged by supplying water to the pressure suppression chamber and the outer peripheral pool from outside the reactor containment vessel. Effect of suppressing the pressure inside the reactor containment vessel after the accident and water supply by pressurizing means without increasing deterioration and earthquake resistance as much as possible. The arrangement relationship between the water source and the water supply destination can be made free without consideration, and this has an effect that is particularly effective in lowering the position of the water source and further improving the earthquake resistance.

According to the second aspect of the present invention, in addition to the effect of the first aspect of the present invention, since the makeup water can be sent to the water supply destination by gas pressure, the reliability in which a mechanical operating part such as a pump is not frequently used is provided. A good water supply effect is obtained, and the effect of improving the reliability of the function of suppressing the pressure in the containment vessel after the accident is obtained.

According to the invention of claim 3, in addition to the effect of the invention of claim 2, since the water source is divided into a plurality of water supply destinations, the amount of water supply to each water supply destination can be determined. There is an effect that there is no excess or deficiency in the amount of water supplied to the water supply destination, and it is possible to prevent the water supply to one of the water supply destinations from being excessively supplied or insufficient.

According to the invention of claim 4, in addition to the effect of the invention of claim 3, the water level of the pressure suppression pool and the outer peripheral pool can be made the same, so that the water pressure applied from both sides to the heat transfer surface between both pools is minimized. The same effect can be obtained that deformation of the heat transfer surface can be suppressed.

According to the fifth aspect of the present invention, in addition to the effect of the fourth aspect of the present invention, there is an effect that a configuration for determining the ratio of the amount of water which achieves the effect of the sixth aspect of the present invention can be specifically provided.

According to the sixth aspect of the present invention, the water cooling heat transfer surface after the accident can be enlarged by supplying water to the pressure suppression chamber and the outer peripheral pool from outside the reactor containment vessel. The effect of improving the function of suppressing the pressure inside the reactor containment vessel after the accident and the water supply to the outer peripheral pool outside the reactor containment vessel can be made using gravity without causing the deterioration of seismic resistance as much as possible. The effect that the water source to the outer peripheral pool is placed outside the reactor containment vessel while the fallen water is used as the supply means can further reduce the size of the reactor containment vessel.

According to the seventh aspect of the present invention, in addition to the effect of the sixth aspect of the present invention, the supply water is supplied to the pressure suppression chamber without using many dynamic devices such as pumps, and the reliability of the supply is increased. An effect that can be improved is obtained.

According to the invention of claim 8, the water cooling heat transfer surface after the accident can be enlarged by supplying water to the pressure suppression chamber and the outer peripheral pool from outside the reactor containment vessel. The effect of suppressing the pressure inside the reactor containment vessel after the accident was improved, and the pump driven by the steam generated inside the reactor pressure vessel was used outside the reactor containment vessel without causing deterioration of the earthquake resistance as much as possible. Therefore, it is possible to reliably assemble the water of the water supply source without borrowing external power from the outside and supply the water to the pressure suppression pool in the pressure suppression chamber and the outer peripheral pool outside.

According to the ninth aspect of the present invention, the water cooling heat transfer surface after the accident can be enlarged by supplying water to the pressure suppression chamber and the outer peripheral pool from outside the reactor containment vessel. The effect of improving the function of suppressing the pressure inside the reactor containment vessel after the accident and the inside of the dry well inside the reactor containment vessel were sprayed with water from the spray nozzle to reduce the steam inside the dry well without deteriorating the earthquake resistance. By condensing it, it exerts a better pressure-suppressing effect, and its watering speeds up the flooding condition in the lower part of the drywell and reduces the water source capacity in the containment vessel required to obtain the flooding condition. And the effects that are suitable for the construction of a containment vessel with small size and good seismic resistance, and their effects, while avoiding the frequent use of dynamic equipment such as pumps and avoiding backflow from the containment vessel side. Effect that the well can be achieved can be obtained.

According to the tenth aspect of the present invention, the decay heat of the reactor core is removed by the heat exchanger inside the reactor containment vessel to which the water cooling function outside the reactor containment vessel does not directly reach, and from the outside by water cooling. The effect of increasing the pressure suppression effect in the reactor containment vessel, and the effect of promoting the depressurization of the reactor pressure vessel and accelerating the injection of the emergency core cooling system,
The heat exchanger can also be used to condense the steam leaked into the drywell, and the effect of improving the pressure suppression effect inside the reactor containment vessel is obtained. The effect that the pressure suppression effect inside is increased.

According to the eleventh aspect of the present invention, the water cooling heat transfer surface after the accident can be enlarged by supplying water to the pressure suppression chamber and the outer peripheral pool from outside the reactor containment vessel. The effect of suppressing the pressure inside the reactor containment vessel after the accident was improved without the deterioration of the seismic resistance as much as possible.
After making the reactor containment vessel whose material and structure have a slowly increasing pressure and good heat dissipation, the lower part of the containment vessel is water-cooled, and the upper part is air-cooled without water pressure. And the effect that the reactor containment vessel is crushed by the cooling water and the deterioration of the seismic performance can be further suppressed.

According to the twelfth aspect of the invention, the decay heat of the reactor core is removed by the heat exchanger inside the reactor containment vessel to which the water cooling function outside the reactor vessel does not directly reach, and from the outside by water cooling. The effect of increasing the pressure suppression effect inside the reactor containment vessel, and the outer shell of the reactor containment vessel is made of steel even if the structure inside the reactor containment vessel is made of concrete with a high degree of freedom in forming compartments Therefore, the heat radiation to the outside is good, and the operating floor is also communicated with the pressure suppression chamber and is used for the pressure suppression function space, so that the pressure rise is slow, and the operation floor space is made of steel. It is possible to radiate heat to the outside via the containment vessel, and it has good heat dissipation properties as a whole, further improving the effect of pressure suppression, and utilizing the good heat dissipation property of the reactor containment vessel. Water-cool the lower part of the It is air-cooled without applying water pressure, and the whole reactor containment vessel can be actively cooled, so that the pressure suppression effect is further improved, and the high places are air-cooled. In addition, it is possible to prevent the seismic performance from being weakened, and to obtain the effect of improving the pressure suppressing effect in the reactor pressure vessel and the anti-vibration performance by the synergistic effect.

According to the thirteenth aspect of the present invention, the decay heat of the core is removed by the heat exchanger inside the reactor containment vessel to which the water cooling function outside the reactor vessel does not directly reach, and from the outside by water cooling. In the reactor pressure vessel, an emergency core cooling system with a plurality of systems is relayed over time between each system to maintain and cool the core for a long period of time, The effect of distributing the cooling effect inside and outside the reactor pressure vessel over a long period of time and achieving the long-term pressure suppression effect inside the containment vessel is obtained.

According to the fourteenth aspect of the present invention, the water cooling heat transfer surface after the accident can be enlarged by supplying water to the pressure suppression chamber and the outer peripheral pool from outside the reactor containment vessel. The effect of suppressing the pressure inside the reactor containment vessel after the accident was improved without the deterioration of seismic resistance as much as possible. The structure has good controllability, and its suppression function is further enhanced.Furthermore, in the reactor pressure vessel, an emergency core cooling system with multiple systems is relayed between each system with the passage of time, and the core is maintained for a long time. The effect of cooling by maintaining the submergence is provided, and the effect of reliably performing the cooling effect in the reactor pressure vessel over a long period of time and more reliably achieving the long-term pressure suppression effect in the containment vessel is obtained.

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[Brief description of the drawings]

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

FIG. 2 is a longitudinal sectional view of the reactor equipment showing a state after water injection into a pressure suppression pool and an outer peripheral pool in the first embodiment.

FIG. 3 is a vertical cross-sectional view of the vicinity of the suppression chamber showing a convection state of the suppression pool water after a rise in the water level of the suppression chamber according to the first embodiment.

FIG. 4 is a longitudinal sectional view of a reactor facility according to a second embodiment of the present invention.

FIG. 5 is a longitudinal sectional view of a reactor facility according to a third embodiment of the present invention.

FIG. 6 is a longitudinal sectional view of a reactor facility according to a fourth embodiment of the present invention.

FIG. 7 is a longitudinal sectional view of a reactor facility according to a fifth embodiment of the present invention.

FIG. 8 is a longitudinal sectional view of the vicinity of a cooling water pool of a nuclear reactor facility according to a sixth embodiment of the present invention.

FIG. 9 is a graph showing a change with time of a decay heat amount after a coolant loss accident in the fifth embodiment.

FIG. 10 is a graph showing a change with time of the pressure suppression pool water temperature after a coolant loss accident in the fifth embodiment.

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

[Explanation of symbols]

1 ... core, 2 ... reactor pressure vessel, 3 ... dry well, 5
... pressure suppression pool, 6 ... wet well, 7 ... vent pipe, 8 ... reactor containment vessel wall, 9 ... peripheral pool, 10 ... main steam pipe, 11 ... concrete structure wall, 12, 13, 14
... Communication port, 20 ... Pressure storage tank, 21 ... Gravity fall water tank, 22 ... Submergence system, 26 ... Automatic pressure reducing system, 30 ... Replenishment water pool, 34 ... Replenishment water pool gas phase space, 35 ... Pressure storage tank, 42 ... Spray nozzle, 43 ... branch pipe, 50 ... turbine drive pump, 60 ... steam condensing type heat exchanger, 61 ...
Cooling water pool, 65: heat transfer tube, 81: air intake, 82
… Air outlet.

Continuation of the front page (72) Inventor Kenji Tominaga 3-1-1 Kochicho, Hitachi-shi, Ibaraki Pref. Hitachi, Ltd. Inside Hitachi Plant (56) References JP-A-4-254795 (JP, A) JP-A-2 JP-A-281191 (JP, A) JP-A-3-246492 (JP, A) JP-A-64-16991 (JP, A) JP-A-63-173997 (JP, A) JP-A-59-107293 (JP, A) (58) Fields surveyed (Int. Cl. ⁶ , DB name) G21C 9/004 GDB G21C 13/00

Claims (14)

(57) [Claims] 1. A reactor containment vessel having a heat transfer surface from a pressure suppression pool inside a reactor containment vessel to an outer peripheral pool outside a reactor containment vessel, wherein the water supply source is provided outside the reactor containment vessel. Water supply means for both pools, the water supply means comprising a pressurizing means for applying pressure to the water of the water supply source, and a water supply path from the water supply source to the pressure suppression pool and the outer peripheral pool. Pressure suppression equipment for reactor containment vessels characterized by: 2. A water supply source according to claim 1, wherein the water supply source is makeup water accumulated in a makeup water pool formed airtight outside the reactor containment vessel, and the pressurizing means is provided outside the reactor containment vessel. A pressure storage tank that is provided and is connected to a gas phase space of the makeup water pool through a valve via a valve; and a pressurized gas stored in the pressure storage tank. A suction port is provided in the liquid phase region of the first pipe provided with a valve and a valve on the way, and the discharge port faces the pressure suppression pool, and the discharge port faces the outer peripheral pool. Pressure suppression equipment for a reactor containment vessel, characterized in that it is a second pipe. 3. The makeup water pool according to claim 2, wherein at least a plurality of water storage areas are partitioned by partitions, and at least one of the partitioned water storage areas is provided with a suction port of the first pipe at least in another area. Pressure suppression equipment for a containment vessel, wherein a suction port for a second pipe is provided on one side. 4. The makeup water pool according to claim 3, wherein the amount of makeup water accumulated in the makeup water pool section provided with the suction port of the first pipe and the makeup water pool section provided with the suction port of the second pipe. The ratio of the amount of make-up water stored in the tank to the normal amount of cooling water in the pressure suppression pool and the amount of cooling water in the outer peripheral pool during normal time is equal to the pressure suppression equipment for the containment vessel. . 5. The water supply ratio in each section of the makeup water pool according to claim 4, wherein a ratio of a partition in the makeup water pool is adjusted in a direction adjacent to each section. Reactor containment pressure suppression equipment. 6. A reactor containment vessel having a heat transfer surface from a pressure suppression pool inside a reactor containment vessel to an outer peripheral pool outside a reactor containment vessel, wherein the water supply source is provided outside the reactor containment vessel. Water supply means for both pools, wherein the water supply means is present as a plurality of independent water supply sources, and pressurizing means for applying pressure to water of at least one of the plurality of water supply sources, A water supply path from the one water supply source to the pressure suppression pool, and at least one other water supply source of the water supply source is provided at a position higher than an outer peripheral pool, and has a water supply path to the outer peripheral pool; Pressure suppression equipment for a reactor containment vessel, characterized by having a valve in the water path to the pool. 7. The water supply source to which the pressure from the pressurizing means is applied is cooling water accumulated in an airtight makeup water pool. A pressure suppression system for a containment vessel, wherein the pipe is connected to the makeup water pool via a vessel and a valve. 8. A reactor containment vessel having a heat transfer surface from a pressure suppression pool in a reactor containment vessel to an outer peripheral pool outside the reactor containment vessel, wherein the water supply source is provided outside the reactor containment vessel. A water supply means for both pools, said water supply means being provided between a turbine pump connected to the reactor pressure vessel via a valve to receive drive steam and a suction side of the turbine drive pump and the water supply source; A pressure suppression facility for a reactor containment vessel, comprising: a connected pipe; and a pipe from a discharge side of the turbine drive pump to the pressure suppression pool and the outer peripheral pool. 9. A reactor containment vessel having a heat transfer surface from a pressure suppression pool in a reactor containment vessel to an outer peripheral pool outside the reactor containment vessel, wherein the water supply source is provided outside the reactor containment vessel. Water supply means for both pools and the inside of the dry well of the containment vessel is provided, and a spray nozzle arranged in the dry well is connected to the water supply means for the inside of the dry well, and further to the inside of the dry well The water supply means includes: a makeup water stored in a makeup water pool whose water supply source is airtightly formed outside the reactor containment vessel; and a gas phase space of the makeup water pool arranged outside the reactor containment vessel and provided. An accumulator tank connected to the accumulator via a valve, a pressurized gas accumulated in the accumulator tank, and a suction port are provided in a liquid phase region in the makeup water pool, and a discharge port is connected to the spray nozzle. Piping and the pressure suppression system for a reactor containment vessel that characterized in that it comprises a valve provided in the middle of the pipe. 10. A heat exchanger mounted in a cooling water pool above a core position installed in a reactor pressure vessel in a drywell, and said reactor pressure vessel is connected to a heat transfer tube of said heat exchanger. From the heat exchanger, a pipe for returning condensed water from the heat exchanger into the reactor pressure vessel, and a pipe from the heat exchanger to the reactor pressure suppression chamber. A pipe for passing gas, a reactor containment vessel including the drywell, the suppression chamber, and the cooling water pool; and a pressure suppression pool provided outside the reactor containment vessel and inside the suppression chamber. An outer peripheral pool provided thermally connected with a heating means interposed therebetween; and a vent pipe for guiding steam from the cooling water pool to the outside of the containment vessel. Steam from the reactor pressure vessel into a heat tube A reactor containing a pipe communicating between at least one of the pipe portion or the heat exchanger and a drywell between the valve and the heat exchanger provided in the middle of the pipe through which the gas flows, and Container pressure suppression equipment. 11. A reactor containment vessel having a heat transfer surface from a pressure suppression pool in a reactor containment vessel to an outer peripheral pool outside the reactor containment vessel, wherein the water supply source is provided outside the reactor containment vessel. Water supply means for both the pool and the dry well of the containment vessel is provided, and the containment vessel is provided with:
A concrete structure which is made of steel, and forms a pressure suppression chamber and a drywell in the containment vessel, and an operating floor space above the concrete structure, and an operating floor space around the concrete structure. In the space leading to the operation floor, a gas phase region and a liquid phase region in the pressure suppression chamber are communicated through a communication port, and a space outside the lower part of the containment vessel is provided. The outer peripheral pool is provided in contact with the outer wall surface of the containment vessel, and a ventilation path is provided in contact with the outer wall surface of the containment vessel above the outer peripheral pool, and a ventilation inlet is provided at a lower portion of the ventilation path. Pressure suppression equipment for a reactor containment vessel, characterized in that outlets are provided at the top. 12. A heat exchanger provided in a cooling water pool above a core position installed in a reactor pressure vessel in a drywell, and said reactor pressure vessel installed in a heat transfer tube of said heat exchanger. From the heat exchanger, a pipe for returning condensed water from the heat exchanger into the reactor pressure vessel, and a pipe from the heat exchanger to the reactor pressure suppression chamber. A pipe for passing gas, a reactor containment vessel including the drywell, the suppression chamber, and the cooling water pool; and a pressure suppression pool provided outside the reactor containment vessel and inside the suppression chamber. An outer peripheral pool provided by being thermally connected with a heating means interposed therebetween, and a vent pipe for guiding steam from the cooling water pool to the outside of the reactor containment vessel, wherein the reactor containment vessel is made of steel. And its reactor containment A concrete structure that partitions and forms a pressure suppression chamber and a drywell in a container, and an operation floor space above the concrete structure are covered around the concrete structure with a space communicating with the operation floor space interposed therebetween. In the space leading to the operation floor, a gas phase region and a liquid phase region in the pressure suppression chamber communicate with each other through a communication port, and the reactor as the heat transfer means surrounds a lower outer periphery of the reactor containment vessel. The outer peripheral pool is provided in contact with the outer wall surface of the containment vessel, and a ventilation path is provided in contact with the outer wall surface of the reactor containment vessel above the outer peripheral pool, and a ventilation inlet is provided at a lower part of the ventilation path and an outlet is provided at an upper part thereof. A pressure containment facility for the reactor containment vessel, which is provided for each. 13. A heat exchanger provided in a cooling water pool above a core position installed in a reactor pressure vessel in a drywell, and said reactor pressure vessel being connected to a heat transfer tube of said heat exchanger. From the heat exchanger, a pipe for returning condensed water from the heat exchanger into the reactor pressure vessel, and a pipe from the heat exchanger to the reactor pressure suppression chamber. A pipe for passing gas, a reactor containment vessel including the drywell, the suppression chamber, and the cooling water pool; and a pressure suppression pool provided outside the reactor containment vessel and inside the suppression chamber. An outer peripheral pool provided thermally connected with a heating means interposed therebetween, and a vent pipe for guiding steam from the cooling water pool to the outside of the reactor containment vessel. Built in the reactor pressure vessel Gravity drop water supply system, which is connected to the reactor pressure vessel via a valve via a gravity drop water tank provided at a position above the set core and a position above the pressure suppression chamber in the reactor containment vessel. A pressure accumulating water injection system in which cooling water is sealed at a high pressure exceeding a pressure corresponding to a head difference from the reactor core to the gravity falling water tank and the reactor pressure vessel and a pressure accumulating water injection system connected via a valve; The three types of emergency water injection systems of a water intake system connected via a valve to a water intake port located at a position higher than the upper end of the core in the pressure suppression chamber in the containment vessel, and the inside of the reactor pressure vessel, Pressure suppression equipment for a reactor containment vessel, which is provided inside the reactor containment vessel. 14. A reactor containment vessel having a heat transfer surface from a pressure suppression pool in a reactor containment vessel to an outer peripheral pool outside the reactor containment vessel, wherein the water supply source is provided outside the reactor containment vessel. A water supply means for supplying water to both pools and the dry well of the reactor containment vessel, wherein the reactor containment vessel is made of steel and has a concrete structure for partitioning the pressure suppression chamber and the dry well in the reactor containment vessel. Object and the operating floor space above the concrete structure are covered around the concrete structure with a space communicating with the operating floor space interposed therebetween, and the space communicating with the operating floor includes a gas phase in the pressure suppression chamber. The region and the liquid phase region are communicated by a communication port, and the position of a core built in the reactor pressure vessel stored in the reactor containment vessel and the reactor containment volume A gravity-drop water injection system that communicates with the reactor pressure vessel via a valve a gravity-drop water tank equipped at a position above the pressure suppression pool in the vessel, and the gravity-drop water from the reactor core. A pressure accumulating water injection system in which a pressure accumulating water injection tank filled with a high pressure exceeding the pressure corresponding to the head difference up to the water tank and the reactor pressure vessel are connected via a valve, and a pressure suppression pool in the reactor containment vessel. The reactor containment vessel is equipped with three types of emergency water injection systems, i.e., a flooding system in which the intake port located at a position higher than the upper end of the core and the inside of the reactor pressure vessel are connected via a valve. Pressure suppression equipment for reactor containment vessels characterized by: