JPH0990081A - Nuclear plant - Google Patents

Abstract

PROBLEM TO BE SOLVED: To reduce the size of reactor building and production cost of plant. SOLUTION: A reactor building 1 has a height of 57m or less by limiting a pressure suppression chamber 18 height of 20m or less, an upper drywell 14 height of 11m or less, a spent fuel pool 8 depth of 11m or less, a component laying tentative pool 10 depth of 8m or less, or an operation floor 6 height of 17m or less and the minimum width of the reactor building of 55m or less. By this, the building 1 can be not only small-sized but also improved in the aseismicity of the whole reactor building by realizing an independent and selfstanding structure of the building between the reactor containment and the reactor building. Furthermore, the space for spent fuel storage can be increased and simultaneously the pool height can be reduced.

Description

Detailed Description of the Invention

[0001]

BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a nuclear power plant, and more particularly to a reactor containment vessel, a reactor building and a nuclear power plant suitable for application to a boiling water reactor (BWR) plant.

[0002]

2. Description of the Related Art In a nuclear power plant, the cost of constructing a reactor building accounts for a large proportion of the total construction cost of a nuclear power plant. Therefore, the cost of constructing a nuclear power plant can be reduced by reducing the height of the containment vessel and the reactor building. There are many aimed inventions, and known techniques relating to a method for downsizing a reactor building and a reactor containment vessel of a nuclear power plant include, for example, the following.

(1) Japanese Patent Laid-Open No. 55-59392 In this known technique, a spent fuel pool, an equipment temporary storage pool, and a pressure suppression chamber are provided integrally with the inner peripheral portion of the dry well to simplify the structure. At the same time, the plan dimensions of the building have been reduced.

(2) Japanese Patent Laid-Open No. 63-48498 In this known technique, the upper part of the reactor building is reduced stepwise with respect to the lower part, and the reactor containment vessel is housed in the lower part and used in the upper part. The spent fuel pool and the equipment temporary storage pool are provided, and the outdoor wall of the upper building and the outer wall of each pool are integrally formed, reducing the dead space above the reactor building and downsizing the reactor building.

(3) Japanese Patent Application Laid-Open No. 57-587,588 In this known technique, a support tool is provided on the outer periphery of the upper portion of the reactor pressure vessel, and the support tool is supported on the upper end portion of the reactor shielding wall.
The diameter of the reactor shielding wall and the pedestal can be reduced to the extent that the nozzles do not interfere with each other when the pressure vessel is installed, thus downsizing the entire reactor.

(4) JP-A-4-125495 In this known technique, the reactor containment vessel is made of steel, and the operating floor space, the spent fuel pool, and the equipment temporary storage pool are included together with the reactor containment vessel. As a result, the reactor cooling equipment is downsized despite the large containment vessel.

[0007]

In all of the above-mentioned known techniques, it is possible to reduce the size of the reactor containment vessel, a part of the reactor building, or equipment / equipment.
It is not intended to downsize the entire reactor building.

The dimensions (height, width, volume) of each room in the reactor containment vessel / reactor building are determined as follows.

(1) Upper dry well Due to the thermal expansion margin of the high temperature part of the reactor pressure vessel and the main steam pipe, a space where the main steam pipe is routed is secured in the upper dry well and The upper space for the upper dry well is secured for the work of the main steam isolation valve (MSIV) and the relief safety valve (SRV) provided, and the upper space is provided for the work of the main steam pipe and the water supply pipe arranged under the lower dry well. A space under the dry well is secured.

(2) Lower Dry Well The lower dry well is an internal pump (RIP) or control rod drive mechanism (C) installed below the reactor pressure vessel.
(RD) etc. to ensure the workability of replacement and assembly, and the size of equipment such as RIP and CRD depends on the reactor pressure vessel / core height, so the lower drywell height also depends on them. To do. Further, since the pressure suppression chamber is arranged around the lower dry well, the matching with the pressure suppression chamber height is also taken into consideration.

(3) Pressure suppression chamber In the design of a nuclear power plant, the piping connected to the reactor pressure vessel should be broken and the high temperature and high pressure steam spouts into the containment vessel at the time of the loss of coolant accident (LOCA). Assume the matter.
At the time of LOCA, first, high-temperature high-pressure steam is jetted and filled in the upper and lower drywells, and the nitrogen filled in these drywells is entrained and released into the pressure suppression pool water via the vent pipe. Here, the steam is condensed, the pool water temperature rises, the non-condensable gas nitrogen accumulates in the wet well, and the pressure in the wet well rises. In this way, at the time of LOCA, the heat and pressure of the coolant in the reactor pressure vessel are relaxed and suppressed inside the reactor containment vessel without using dynamic equipment, thus maintaining the integrity of the nuclear power plant. Designed to be.

For the above reason, the volumes of the upper and lower dry wells are secured to alleviate the initial pressure rise during LOCA, and the wet well volume is determined from the dry well volume. Since the drywell / wetwell pressure rises during LOCA, it is designed to ensure the pressure resistance of these chambers. In addition, considering the cooling water (steam) amount in the reactor pressure vessel, enthalpy, and water temperature rise during condensation, etc., the pressure suppression chamber pool volume (water amount) is designed to be secured.

(4) Spent fuel pool, equipment temporary storage pool The depth of the pool above these reactor containment vessels depends on the length of the fuel assembly and the equipment height of the steam dryer / water separator. . Both pools are located between the operation floor and the containment vessel to ensure workability during periodic inspections. Since the spent fuel assemblies are handled below the pool surface of the shielding material, the depth of the spent fuel pool is secured to be more than twice the fuel assembly height. In the current BWR, this height is the steam dryer / steam water. It is deeper than the temporary equipment pool because it is higher than the height of the separator.

(5) Operation floor Work on the fuel assembly by the fuel assembly assembly machine / exchanger, steam dryer, steam separator, top head, RIP
Operation floor space and height are secured due to handling and workability by overhead cranes when loading and unloading equipment such as impellers.

Due to such constraints, the reactor containment vessel and the reactor building cannot be simply downsized due to the downsizing of the reactor pressure vessel, and by overcoming the constraints of each room / space. The challenge is to reduce the size of each room and eventually the reactor containment vessel and reactor building as a whole.

Further, downsizing of the entire reactor containment vessel / reactor building poses a problem of improving the vibration resistance of the building. Nuclear power plants are designed to lower the center of gravity of buildings in order to improve vibration resistance, and areas that have been divided according to function (groups of rooms) may be combined to create a single building. . However, in this case, since the plane of the entire building expands, it is necessary to take a larger area at the same leveling level, which makes the location conditions severe and construction costs are high.

An object of the present invention is to provide a nuclear power plant having a downsized reactor containment vessel and a reactor building.

Another object of the present invention is to provide a reactor containment vessel for reducing the size of the reactor containment vessel and the reactor building, a partial structure of the reactor building, and a reactor pressure vessel.

[0019]

In order to achieve the above-mentioned object, the present invention is a reactor building, wherein the height of the reactor building from the upper end of the mat to the upper end of the operation floor space is 57 m or less, or the reactor building. The first means is to provide a nuclear power plant having a minimum width of 55 m or less.

Preferably, in the reactor building of the first means, the height of the reactor containment vessel is 32 m or less, or the height from the upper end of the mat to the operation floor surface is 39 m or less, or the outer diameter of the side wall of the reactor containment vessel. A nuclear power plant, which is the second means, is provided in which the height is set to 28 m or less.

Further, preferably, in the reactor building of the first means and the second means, the height of the pressure suppression chamber is 20 m or less, or the height of the upper dry well is 11 m or less, or the depth of the spent fuel pool is A nuclear power plant is provided as a third means in which the depth of the equipment temporary storage pool is 11 m or less, the depth of the equipment temporary storage pool is 8 m or less, or the height of the operating floor is 17 m or less.

Further, preferably, in the reactor building of the first means, there is provided a reactor containment vessel which is a fourth means in which a side wall and a top slab of the reactor containment vessel have a structure made of prestressed concrete. .

More preferably, in the reactor building of the fourth means, an area including the reactor containment vessel, the operating floor, the spent fuel pool, the equipment temporary storage pool and the reactor well, and the reactor building equipment working room. A reactor building is provided as a fifth means, which has a building structure that is independent and independent of the area including the.

Further preferably, in the reactor pressure vessel of the first means, the sixth structure provides a partial structure of the reactor pressure vessel, which is a projecting position higher than the core in which the reactor pressure vessel skirt is built. To be done.

Further preferably, in the reactor pressure vessel of the first means, the reactor containment vessel of the seventh means is provided in which the pedestal is at a projecting position higher than the diaphragm floor.

Preferably, the reactor pressure vessel of the third, fourth, fifth, sixth or seventh means has an effective core height of 3.5 m.
An eighth aspect of the present invention provides a reactor pressure vessel.

Further, preferably, in the reactor containment vessel of the first means, the crane monorail above the upper dry well is laid out except directly above the main steam pipe, and the relief safety valve can be horizontally carried out by the ninth means. A reactor containment vessel is provided.

Further preferably, in the reactor containment vessel of the first means, a partition bed is arranged below the lower dry well, and a pressure suppression chamber pool is provided between the partition bed and the mat.
A means, a reactor containment vessel, is provided.

Further, preferably, in the reactor containment vessel of the first means, a plurality of pools are arranged on the outer periphery of the reactor well, and each pool has a first bottom surface on which the fuel assembly taken out from the reactor pressure vessel is arranged. An eleventh means is to have a second bottom surface shallower than the first bottom surface, and the second bottom surface has an area such that the reactor internals in the reactor pressure vessel can be temporarily placed when the fuel assembly is replaced. A reactor containment vessel is provided.

Further preferably, in the reactor containment vessel of the first means, a twelfth means is provided in which the deepest depths of the spent fuel pool and the equipment temporary storage pool are the same. .

[0031]

[Operation] According to the first means, the height of the reactor building is 57 m.
Below, or by setting the minimum width of the reactor building to 55 m or less, the reactor building can be downsized.

According to the second means, the height of the reactor containment vessel of the reactor building of the first means is 32 m or less, or the height from the upper end of the mat to the operation floor surface is 39 m or less, or the side wall of the reactor containment vessel. By setting the outer diameter of the reactor to 28 m or less, the reactor containment vessel can be downsized.

According to the third means, the height of the pressure suppression chamber of the reactor building of the first and second means is 20 m or less, or the height of the upper dry well is 11 m or less, or the depth of the spent fuel pool is 11 m. By setting the depth of the equipment temporary storage pool to be 8 m or less or the height of the operating floor to be 17 m or less, the height of each room space can be reduced and the reactor containment vessel can be downsized.

According to the fourth means, since the side wall of the reactor containment vessel and the top slab of the reactor building of the first means have a structure made of prestressed concrete, the pressure resistance and vibration resistance of the containment vessel are improved. The reactor containment vessel can be downsized.

According to the fifth means, an area including the reactor containment vessel, the operating floor, the spent fuel pool, the equipment temporary storage pool and the reactor well of the reactor building of the fourth means, and the reactor building By having a building structure in which the area including the equipment work room is independent and independent, the vibration resistance of the entire reactor building is improved and the reactor building can be downsized.

According to the sixth means and the seventh means, by supporting the reactor pressure vessel at a position above the reactor core, thermal expansion of the reactor pressure vessel is relaxed, and the height of the upper dry well and thus the reactor containment vessel is reduced. The height can be reduced.

According to the eighth means, the effective core height is 3.5.
By providing a reactor pressure vessel of m or less, it is possible to reduce the height of all the room spaces of the reactor containment vessel, the spent fuel pool, the equipment temporary storage pool, and the operating floor that are contained in the reactor building. The height of the reactor building can be reduced.

According to the ninth means, the monorail of the crane above the upper dry well is laid outside the main steam pipe, and the relief safety valve can be carried out horizontally, so that it is conventionally provided above the valve. It is possible to reduce the carry-out space, and it is possible to reduce the height of the upper dry well and hence the height of the reactor containment vessel.

According to the tenth means, the height of the pressure suppression pool can be reduced and the height of the reactor containment vessel can be reduced by using the portion below the lower dry well as the pressure suppression chamber pool.

According to the eleventh means and the twelfth means, the first bottom surface on which the fuel assemblies are arranged and the reactor internals are temporarily arranged at the time of exchanging the fuel assemblies in the plurality of pools arranged on the outer periphery of the reactor well. By having a second bottom surface that is shallower than the first bottom area that can be placed, the space for installing these structures due to the high depth of the spent fuel pool and equipment temporary storage pool in the conventional reactor building It is possible to reduce the height of each pool and to reduce the height of the reactor containment vessel while relaxing the restriction of (1) and increasing the spent fuel storage space in particular.

[0041]

【Example】

(Embodiment 1) A boiling water nuclear power plant which is a first embodiment of the present invention will be described by comparing FIGS. 3 and 4 of a conventional example with FIGS. 1 and 2 of the present invention.

The reactor containment vessel 2 shown in FIG. 1 is made of reinforced concrete with a liner inside to provide pressure resistance against the gas generated inside, the side wall 30 of the containment vessel is the side surface, the lower surface is the mat 34, and the upper surface. Is a structure having a cylindrical shape in which a dome-shaped top head 24 is a top slab 26 projecting upward. A pedestal 32 is provided so as to project inward from a cylindrical space at the center of the reactor containment vessel 2, and the reactor pressure vessel 4 is installed on the top of the pedestal, and the pressure vessel skirt 124 is installed. The pressure vessel 4 is supported via the pressure vessel 4. A cylindrical pressure vessel shielding wall 36 is provided above the pedestal 32 so as to project around the reactor pressure vessel 2. The reactor containment vessel 2 is divided into an upper dry well 14, a lower dry well 16 and a pressure suppression chamber 18 by a diaphragm floor 28 and a pedestal 32. Furthermore, the pressure suppression chamber 18 has a pressure suppression pool 20 filled with cooling water.
Then, it is divided into a wet well 22 which is an upper space of the pool 20. The pressure suppression chamber 18 is provided with a plurality of access tunnels 42 from the outside of the storage container 2 to the lower dry well 16 for accessing workers and carrying in and out of equipment.

Various equipment is installed in the reactor containment vessel 2 assuming the following events.

At the time of LOCA, the vent pipe 44 for discharging the high-temperature high-pressure steam ejected to the upper dry well 14 and the lower dry well 16 together with nitrogen into the pressure suppression pool 20 water.
A horizontal vent 46 is installed to change the outflow direction of steam to a horizontal direction. Further, a vacuum breaker 40 for preventing a pressure drop due to vapor condensation in the dry wells 14 and 16 is
It is provided between the pressure suppression chamber 18 and the lower dry well 16. The reactor pressure vessel 4 is connected with pipes such as a main steam pipe 50 for taking out steam and a water supply pipe 52.
In order to isolate the environment inside and outside the reactor containment vessel 2 when the main steam pipe 50 is broken, a main steam isolation valve 54 is installed inside the containment vessel 2 of the pipe penetration portion 66 and on the main steam tunnel 64 side. A relief safety valve 56 is installed in the main steam pipe to release steam when the pressure inside the reactor pressure vessel 4 becomes high, and the steam discharged from the valve 56 is condensed in the pressure suppression pool 20 via the quencher 58. .

On the operation floor 6 above the reactor containment vessel 2,
The spent fuel storage pool 8 and the equipment temporary storage pool 10 are
One on each side of the reactor well 24 above the reactor containment vessel 2. The equipment temporary storage pool 10 is filled with water for shielding radiation, and is a unit of a steam separator 110, a steam dryer 112, and an internal pump 120 taken out from the reactor pressure vessel 4 during a periodic inspection. It has a space for temporary placement. The spent fuel storage pool 8 is
The inside is filled with cooling water that also functions as a radiation shield.
It has a bottom surface 8B and a second bottom surface 8C that is shallower than the first bottom surface. The spent fuel assemblies taken out of the reactor pressure vessel 4 are arranged on the first bottom surface 8B while being inserted into a spent fuel storage rack (not shown). The second bottom surface 8C has an area for temporarily placing the control rod 116 taken out of the reactor pressure vessel 4 at the time of refueling.

During operation of the reactor, the reactor well 12 has the top head 24 as a part of the bottom. Reactor well 1
In Fig. 2, a concrete shield plug 38 that functions as a radiation shield for the operation floor 6 during operation of the reactor is installed on the operation floor surface, and the inside of the reactor well 12 is filled with water. A part of the second bottom surface 8C of the spent fuel storage pool 8 and the equipment temporary storage pool 10 are located right above the reactor containment vessel 2. Further, during operation of the reactor, the spent fuel storage pool 8 and the reactor well 12 are used fuel storage pool gates 8A, and the equipment temporary storage pool 10 and the reactor well 12 are equipment temporary storage pool gates 10A. Each is divided.

A refueling machine 60 for exchanging fuel in the core used at the time of periodic inspection is installed together with a pair of rails on the surface of the operation floor 6, and an overhead crane 62 is provided above the operation floor 6 for carrying in / out equipment. Is installed.

Generally, a boiling water reactor is constructed as shown in FIG.

That is, a shroud 104 is provided in the reactor pressure vessel 4, and a core 100 containing a large number of fuel assemblies 102 is housed inside the shroud 104. The cooling water 130 flowing into the core 100 is heated by the fuel in the fuel assembly 102 and boils, and flows into the shroud head 106 as a mixed two-phase flow of water and steam. A large number of stand pipes 108 and a steam separator 110 are connected above the shroud head 106, and a steam dryer 112 is installed above the steam separator 110. Then, the mixed two-phase flow of water and steam is first subjected to the steam separator 110.
It is separated into water and steam. The steam 140 separated by passing through the water / water separator 110 is dried by the steam dryer 112 and then collected by the upper plenum 113 and discharged from the main steam nozzle 114 as shown by an arrow 142 to a turbine (not shown). It is configured to be delivered. On the other hand, feed water for replenishing the cooling water discharged as steam from the main steam nozzle 114 is sent from the water feed nozzle 115. The water separated by the steam separator 110 is the steam separator 1
10 is returned to the downcomer 103, mixed with the water supply supplied from the water supply nozzle 115 in the downcomer 103, sent to the lower part of the core 100 by the internal pump 120, and recirculated to the core 100 as indicated by an arrow 132. There is. The phenomenon of the core 100 is monitored by the neutron flux instrumentation pipe 122 and the like, and the control rod driving mechanism 118 inserts and pulls out the control rod 116 from the lower portion of the reactor pressure vessel 4 to generate heat output of the fuel assembly 102. Is configured to control.

The mat 3 is provided with the reactor area 80 containing the above-mentioned equipment and structures, a plurality of reactor building equipment working rooms installed outside the reactor containment vessel 2, and the reactor containment vessel 2.
4 and the reactor building 1 contains these.

In the reactor building of FIG. 1, the reactor pressure vessel 4
Is provided as an upper support, and the reactor containment vessel 4 is made of prestressed concrete, so that the containment vessel side wall base 31 is provided and fixed in the mat 34, and the containment vessel upper dry well 14 and the pressure suppression chamber 18 are The height is being reduced.

The pressure vessel of FIG. 2 shown in the present embodiment is a next-generation pressure vessel that aims to realize long-term stable energy supply by using the technology of the current light water reactor and by greatly reducing the fuel cycle cost by increasing the burnup and effectively using plutonium. RBWR (Resource- Renewable Boiling Water R) which is a boiling water type light water reactor
eactor) (Japanese Patent Application No. 6-156989).
In this RBWR, the plutonium breeding ratio is higher than that of the conventional BWR, and it is possible to set the fissionable plutonium breeding ratio at the time of reactor operation to about 1. In order to achieve this core-nucleus characteristic, the fuel density is increased as a dense hexagonal fuel assembly in which depleted uranium is enriched with plutonium in a triangular array, and the fuel density is also increased. The flow rate of light water is reduced to reduce the volume ratio of water to fuel in the fuel assembly, and the void ratio is slightly increased compared to the current BWR to improve plutonium conversion by fast neutrons. The core structure is to have a combination with Y-shaped control rods that are densely arranged at the ratio of the books. Further, in order to achieve core characteristics, the fuel assembly length, that is, the core height is reduced by 1 m or more from the conventional BWR pressure vessel 5a of FIG. 4, and the control rod length is also reduced by the same degree. The height of the reactor pressure vessel 4 is B
The total pressure can be reduced by 2 m or more from the pressure container 4a for WR.
Further, since the height of the pressure vessel 4 is small, in order to prevent the strength of the welded portion from being lowered, the pressure vessel skirt 1 should be prevented from coming to the side of the same height as the core.
24 is attached to a position above or below the core position. Compared with the reactor containment vessel 4a shown in FIG. 3, it is possible to improve the pressure resistance of the containment vessel 3 using the pre-stressed concrete of the current technology by about two times or more. Therefore, the height of the wet well 22 can be reduced by about 6 m from the conventional wet well 22a.

By supporting the reactor pressure vessel 4 on the upper side, it is possible to reduce the length of the piping route due to the relaxation of thermal expansion of the pressure vessel and the piping, and further to use the clean monorail for carrying out the relief safety valve 56 as the main steam piping 50. Since the relief safety valve 56 can be horizontally carried out by laying it in a place other than above, the relief safety valve work space can be reduced, and the height of the upper dry well 14 is about 1
It can be reduced by about m.

A reactor capable of shortening the core / fuel assembly and reducing the height of the pressure vessel by 1 m or more than the BWR pressure vessel 4a, such as the RBWR pressure vessel of the present embodiment.
When using a pressure vessel that can reduce the radius by 2.5 m,
It looks like this: Since the CRD work space can be reduced and the amount of water held by the reactor can be reduced, the pressure suppression pool 20
The amount of water can be reduced. As described above, the height of the pressure suppression chamber 18 can be reduced, and if the height of the pressure suppression chamber 18 is matched with that of the lower dry well 16, the height of the diaphragm floor 28 can be reduced by about 7 m compared with the conventional diaphragm floor 28a.

Further, in the RBWR, since the fuel assembly 102 is shortened, the depth of the spent fuel pool 8 can be greatly reduced, and if the height of the spent fuel pool 8 is matched with the temporary equipment pool 10,
Pools 8, 10 from top slab 26 to driving floor 6
Is about 3m deeper than the conventional pools 8a and 10a
It can be reduced. As shown in FIG. 1, in the present embodiment, the first bottom surface 8B, the second bottom surface 8C of the spent fuel pool 8 and the spent fuel pool 8 and the equipment temporary storage pool 10 have the same depth. The fuel storage amount is more than doubled, and the effective space of the spent fuel pool 8 can be increased. Further, in the RBWR, the height of the space of the operation floor 6 can be reduced by about 1 m or more as compared with the conventional operation floor 6a by downsizing the internal structure of the furnace.

In this embodiment, the pressure vessel 4, the upper dry well 14 and the lower dry well 1 in the reactor containment vessel 2 are used.
6, pressure suppression chamber 18, and spent fuel pool 8,
The height of the room of each floor of the equipment temporary storage pool 10 and the operation floor 6 has been reduced by several meters, and the height of the entire reactor building 1 can be reduced by about 12 m (for one floor of the reactor building). The building and containment vessel can be significantly downsized.

Further, the containment vessel 3 made of prestressed concrete is made independent and independent from the reactor building 1, and at the same time, the upper part of the reactor building 1 is reduced in a stepwise manner with respect to the lower part, and the reactor containment is provided in the lower part. The container 4 is housed, and the spent fuel pool 8 and the equipment temporary storage pool 10 are arranged on the upper part of the container 4, and the outer wall of the upper building and the outer wall of each pool are integrally formed to reduce the dead space in the upper part of the reactor building 1. do it,
The reactor building 1 is downsized.

The miniaturization of the reactor containment vessel and the reactor building has the following derivative effects in addition to the reduction of the initial construction cost.

(1) The influence of the downsizing of the reactor containment vessel and the reactor building on the design and strength conditions of the building is considered as follows. Nuclear power plants are designed to lower the center of gravity of buildings to improve vibration resistance,
At that time, areas that were divided by function (group of rooms)
In some cases, a complex building is created by fusing the above into a single building. However, in this case, since the plane of the entire building expands, it is necessary to take a larger area at the same leveling level, which makes the location conditions severe and construction costs increase. However, by reducing the height of the reactor containment vessel and reactor building, the center of gravity can be lowered by downsizing, the seismic margin can be expanded compared to the conventional one, and the same level of vibration resistance as the conventional one can be achieved. The strength of each part of the storage container can be reduced. Further, the downsizing of the reactor containment vessel and the reactor building relaxes the vibration resistance condition, reduces the need for complex building, and relaxes the building design condition. In other words, the location conditions for nuclear power plants can be eased. In other words, due to the miniaturization of the reactor containment vessel and the reactor building, the building design conditions and strength conditions are superior to conventional ones.

(2) It is possible to reduce the hierarchy of the reactor building. In addition, the reactor building and the reactor containment vessel can be made into a large module, and the modularization can improve product reliability. Furthermore, it is possible to reduce the amount of construction on site by manufacturing the module factory, and to construct a parallel construction with the reactor containment vessel of the reactor building, which can shorten the construction period and process of the nuclear power plant. Therefore, it is possible to rationalize the construction by making the atom and the containment vessel independent and independent, and there is an advantage of the ripple effect by downsizing the reactor building and the containment vessel.

(3) The influence on the ventilation air conditioning equipment for ventilating each room in the reactor building by reducing the floor area and volume of the room is considered as follows. Since the scale of the reactor body is the same, the installed equipment installed in each room and the operating conditions are the same in the present invention as before, and the heat load and the generated radioactivity generated from these equipment are also the same. Therefore, the temperature
Conditions for maintaining radioactivity concentration (heat removal conditions / concentration conditions)
Is also unchanged and has no effect on ventilation and air conditioning equipment.

This embodiment is the most modified example of the present invention in comparison with the conventional example. However, due to the RBWR-specific modification of shortening the core / fuel assembly due to changes in the reactor pressure vessel, the reactor containment vessel・ Reactor building changes, so it can be realized with current technology.

(Second Embodiment) FIG. 5 shows a reactor building according to a second embodiment of the present invention.

This embodiment is a modification of the first embodiment and is the same as the first embodiment except for the points described below.

That is, the third embodiment is an embodiment of the current ABWR rather than the RBWR, and the reactor pressure vessel is the ABWR pressure vessel 4a shown in FIG. And
Driving floor, spent fuel pool 8a, equipment temporary storage pool 1
0a is the same as in FIG. 3, and the height is not reduced as in FIG.

On the other hand, the height A is larger than that of RBWR.
Since the BWR pressure vessel 4a is adopted, the pressure vessel 4a is lowered by about 1 m in the containment vessel 2a in order to reduce the height of the upper dry well 14a, thereby ensuring the space of the lower dry well 16a. There is no difference in height between the bottom surface 150 of the lower dry well and the bottom surface of the pressure suppression chamber 18a as shown in FIG.

The present embodiment is the smallest change in the present invention as compared with the conventional example, and changes in the reactor pressure vessel and reactor building for the current ABWR are small. However, the height of the upper and lower dry wells and the pressure suppression chamber can be reduced by about 3 m, which has the effect of reducing the construction cost.

(Embodiment 3) A reactor building according to a third embodiment of the present invention is shown in FIG.

This embodiment is a modification of the first embodiment and is the same as the first embodiment except for the points described below.

That is, a method of supporting the lower portion of the RBWR reactor pressure vessel 4b in which the pressure vessel skirt is installed below the core is adopted. Since the storage container 4b is not made of prestressed concrete, the heights of the upper dry well 14b, the lower dry well 16b, and the pressure suppression chamber 18b are not reduced. Also, the reactor containment vessel 2b and the reactor building 1b
It does not adopt independence and independence with. Furthermore, RBWR
The height of the lower dry well is reduced by downsizing the pressure vessel 4b for use, and the lower dry well partition wall 154 is provided below the lower dry well to provide the partition floor 154 and the mat 3
4 as the pressure suppression pool 20b, and the pressure suppression chamber 1
It has a structure communicating with 8. The upper part of the partition floor 154 is the lower drywell working floor 152, where RIP and CRD are provided.
Can be maintained.

Therefore, by reducing the size of the RBWR pressure vessel, the amount of pool water is reduced and the pressure suppression pool 20b is reduced.
The height of the pool 20b and the reactor containment vessel 1b can be reduced by about 2 m in order to increase the volume.

(Fourth Embodiment) FIG. 7 shows a reactor building according to a fourth embodiment of the present invention.

This embodiment is a modification of the third embodiment and is the same as the third embodiment except for the points described below.

That is, the method of supporting the upper portion of the RBWR reactor pressure vessel 4 in which the pressure vessel skirt is installed above the core is adopted. Further, the relief safety valve working space can be reduced by laying the monorail of the crane for unloading the relief safety valve of the upper dry well 14c at a position other than directly above the main steam pipe so that the relief safety valve can be horizontally carried out.
The height of 4c can be reduced by about 1 m. Therefore, the height of the reactor building 1c can be reduced by about 3 m.

(Embodiment 5) A reactor building according to a fifth embodiment of this embodiment is shown in FIG.

This embodiment is a modification of the fourth embodiment and is the same as the fourth embodiment except for the points described below.

That is, since the storage container 2d made of prestressed concrete is adopted, the upper dry well 14
The heights of d, the lower dry well 16d, and the pressure suppression chamber 18d can be reduced by about 7 m. Since these height reducing effects are sufficiently large, formation of a pressure suppression pool below the lower dry well such as the storage container 4b in the figure is performed by the lower dry well 16d.
Has not been adopted in. Therefore, the height of the reactor building 1d can be reduced by about 9 m.

(Embodiment 6) A reactor building according to a sixth embodiment of this embodiment is shown in FIGS. 9 and 10.

This embodiment is a modification of the first embodiment and is the same as the first embodiment except for the points described below.

That is, the pressure vessel 4 for RBWR of the sixth embodiment.
In e, the steam-water separator 110e (for example, Japanese Patent Application No. 5-58766) and the steam dryer 112, in which the height of each unit is reduced by improving the performance of the steam-water separator and the steam dryer.
e (for example, Japanese Patent Application No. 6-122206). Therefore, the height of the operation floor 6e can be further reduced by about 2 m as compared with the first embodiment, so that the reactor building height 1e is about 1 m.
It can be reduced by 4 m. In addition, due to the reduction of the unit height of the steam separator / steam dryer, the placement restrictions on the placement in the spent fuel pool 8e and the equipment temporary placement pool 10e are eased when the equipment for the periodic inspection is temporarily placed. . As described above, the present embodiment provides the reactor containment vessel and the reactor building which have the greatest height reduction effect among the embodiments shown in the present invention.

(Embodiment 7) A reactor building according to a seventh embodiment of this embodiment is shown in FIG.

This embodiment is a modification of the first embodiment and is the same as the first embodiment except for the points described below.

That is, although the containment vessel 2f made of prestressed concrete is adopted, the reactor containment vessel 2f and the reactor building 1f are integrated, and they are not independent. Further, it is adopted that the spent fuel pool 8f and the temporary equipment storage pool 10f have the same sectional shape. As a result, the fuel storage volume in the spent fuel pool 8f can be expanded about twice as compared with the first embodiment. Although the first bottom surface 8Ba and the second bottom surface 8Ca of the spent fuel pool as shown in FIG. 5 are not distinguished in this embodiment, the first bottom surface and the second bottom surface as shown in FIG. Is provided, the fuel storage volume in the spent fuel pool can be expanded even if a plurality of pool shapes are the same.

[0084]

According to the invention of claim 1, the effects of downsizing the reactor building and reducing the plant manufacturing cost can be obtained.

According to the invention of claim 2, the effect of miniaturizing the reactor containment vessel can be obtained.

According to the invention of claim 3, the height of each room space in the reactor containment vessel can be reduced, and the effect of the reactor containment vessel can be obtained.

According to the fourth aspect of the present invention, the effect of reducing the size of the reactor containment vessel can be obtained by improving the pressure resistance and vibration resistance of the containment vessel by the prestressed concrete reactor containment vessel.

According to the invention of claim 5, since the reactor building of claim 4 has the independent / independent building structure of the reactor containment vessel and the reactor building, the vibration resistance of the entire reactor building is improved. It can be improved and the effect of downsizing the reactor building can be obtained.

According to the sixth and seventh aspects of the invention, the thermal expansion of the reactor pressure vessel is moderated by the upper support of the reactor pressure vessel, and the effect of reducing the height of the reactor containment vessel can be obtained.

According to the invention of claim 8, by providing a reactor pressure vessel which is smaller than the current BWR pressure vessel, the height of the room space of all the reactor building and the reactor containment vessel can be reduced, The effect of reducing the height of the reactor building can be obtained.

According to the invention of claim 9, by laying the crane monorail of the upper dry well in which the relief safety valve can be carried out horizontally, the relief safety valve carry-out space can be reduced and the height of the containment vessel can be reduced. .

According to the tenth aspect of the present invention, the pressure suppression chamber pool is formed in a portion below the lower dry well, so that the pressure suppression pool height can be reduced, and the effect of reducing the height of the reactor containment vessel can be obtained. To be

According to the eleventh and twelfth aspects of the present invention, the restriction on the installation space of the structure due to the difference in depth between the spent fuel pool and the equipment temporary storage pool is relaxed, and especially the spent fuel storage space is increased. The height of each pool can be reduced, and the effect of reducing the height of the reactor containment vessel can be obtained.

[Brief description of drawings]

FIG. 1 is a vertical cross-sectional view of a reactor building for a boiling water nuclear power plant according to a first embodiment of the present invention.

2 is a vertical cross-sectional view of the reactor pressure vessel of FIG.

FIG. 3 is a vertical cross-sectional view of a conventional reactor building.

4 is a vertical cross-sectional view of the reactor pressure vessel of FIG.

FIG. 5 is a vertical sectional view of a reactor building according to a second embodiment of the present invention.

FIG. 6 is a vertical sectional view of a reactor building according to a third embodiment of the present invention.

FIG. 7 is a vertical sectional view of a reactor building according to a fourth embodiment of the present invention.

FIG. 8 is a vertical sectional view of a reactor building according to a fifth embodiment of the present invention.

FIG. 9 is a vertical sectional view of a reactor building according to a sixth embodiment of the present invention.

10 is a vertical cross-sectional view of the reactor pressure vessel of FIG.

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

[Explanation of symbols]

1 ... Reactor building, 3 ... Reactor containment vessel, 4 ... Reactor pressure vessel, 6 ... Operating floor, 8 ... Spent fuel storage pool, 10
... Equipment temporary storage pool, 12 ... Reactor well, 14 ... Upper dry well, 16 ... Lower dry well, 18 ... Pressure suppression chamber, 20 ... Pressure suppression pool, 22 ... Wet well,
24 ... Top head, 26 ... Top slab, 28 ... Diaphragm floor, 30 ... Container side wall, 32 ... Pedestal, 34 ... Mat, 50 ... Main steam piping, 54 ... Main steam isolation valve, 56 ... Relief safety valve, 60 ... Fuel Exchanger, 62 ... Overhead crane, 100 ... Reactor core, 118 ... Control rod drive mechanism,
120 ... Internal pump, 124 ... Pressure vessel skirt.

─────────────────────────────────────────────────── ─── Continuation of the front page (51) Int.Cl. ⁶ Identification code Internal reference number FI technical display location G21C 19/06 GDBA

Claims (12)

[Claims] 1. A reactor pressure vessel having a built-in reactor core, an upper drywell centered around the reactor pressure vessel, a top slab, a side wall of a containment vessel, and an upper side, a side and a bottom defined by a diaphragm floor. Supports the dry weight of the reactor pressure vessel transmitted from the lower dry well communicating with the upper dry well and disposed below the reactor pressure vessel and the pressure vessel skirt protruding from the outside of the reactor pressure vessel. And a pedestal projecting from the diaphragm floor so as to be fixed and held in the space of the upper and lower drywells, and a flow path that is installed below the upper drywells and connects the holding water with the upper drywells. A pressure suppression chamber including a pressure suppression pool area and a wet well space, the top slab, the side wall of the storage container, and the mat. A reactor containment vessel whose upper end, side surface and lower end are defined, an operating floor installed above the reactor containment vessel, a spent fuel pool arranged between the operating floor and the containment vessel, and a scale A temporary storage pool, a reactor well, and a reactor area containing a plurality of reactor building equipment work rooms installed outside the containment vessel, and atoms equipped with all of the reactor area on the mat. In the reactor building, the height of the reactor building from the upper end of the mat to the upper end of the operation floor space is 57 m or less, or the minimum width of the reactor building is 55 m or less. 2. The height of the reactor containment vessel from the upper end of the mat to the upper end of the top slab of the reactor building is 32 m or less, or the height from the upper end of the mat to the operating floor surface according to claim 1. A nuclear power plant in which the outer diameter of the side wall of the reactor containment vessel is 39 m or less, or 28 m or less. 3. The pressure suppression chamber according to claim 1, wherein the height of the pressure suppression chamber from the upper end of the mat of the reactor building to the upper end of the diaphragm floor is 20 m or less, or from the upper end of the diaphragm floor to the upper end of the top slab. The dry well height is 11 m or less, or the depth of the spent fuel pool from the operation floor surface to the deepest part is 11 m or less, or the depth of the temporary equipment pool from the operation floor surface to the deepest part is 8 m or less, Alternatively, a nuclear power plant in which the height of the operation floor from the operation floor surface to the upper end of the operation floor space is 17 m or less. 4. The reactor containment vessel according to claim 1, wherein the side wall and the top slab of the reactor containment vessel have a structure made of prestressed concrete. 5. The area containing the reactor containment vessel, the operating floor, the spent fuel pool, the equipment temporary storage pool, and the reactor well, and the reactor building equipment work room according to claim 4. A reactor building with a building structure that is independent and independent of the enclosed area. 6. The reactor pressure vessel according to claim 1, wherein the reactor pressure vessel skirt is provided at a projecting position higher than the core in which the skirt is built. 7. The reactor containment vessel according to claim 1, wherein the pedestal is at a projecting position higher than the diaphragm floor. 8. The method of claim 3, 4, 5, 6, or 7,
A reactor pressure vessel having an effective core height of 3.5 m or less. 9. The reactor containment vessel according to claim 1, wherein the monorail of the crane above the upper dry well is laid out just above the main steam pipe, and the relief safety valve can be horizontally carried out. 10. The reactor containment vessel according to claim 1, wherein a partition floor is arranged below the lower dry well, and a pressure suppression chamber pool is provided between the partition floor and the mat. 11. A reactor according to claim 1, wherein a plurality of pools are arranged on an outer periphery of the reactor well, and each of the pools has a fuel assembly taken out from the reactor pressure vessel.
A bottom surface and a second bottom surface shallower than the first bottom surface,
The second bottom surface is a reactor containment vessel having an area such that a reactor internal structure in the reactor pressure vessel can be temporarily placed when the fuel assembly is replaced. 12. The reactor containment vessel according to claim 1, wherein the deepest depths of the spent fuel pool and the equipment temporary storage pool are the same.