JPH09166684A - Structure of pool in reactor building - Google Patents

Abstract

PROBLEM TO BE SOLVED: To reduce the radiation exposure of reactor inspection workers and strengthen the capacity of the reactor containment in case of accident. SOLUTION: A reactor building is constituted of an operation floor 8, a spent fuel storage pool 17, reactor well 7, a component pool 5 for tentatively placing a steam dryer and steam water separator in a reactor building 4 placing a cylindrical ferroconcrete reactor containment 9. In the structure of the pool, two body walls 14 positioning between the operation floor 8 and the upper surface of the reactor containment 9 and including a pool guarder on the upper surface of the reactor containment 9, are rigidly connected. On this wall body 14, a ferroconcrete shielding wall 11 laying metal liner is placed. By this shielding wall 11, radiation from the components in the component pool 5 to the operation floor 8 is shielded and the bearing force to bending as beam is strengthened by increasing the height of the pool guarder.

Description

Detailed Description of the Invention

[0001]

BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a cylinder type reinforced concrete reactor containment vessel (hereinafter referred to as RC
(CV) Adopting a structure of a reactor building pool arranged in the reactor building.

[0002]

2. Description of the Related Art The structure of a conventional reactor building pool is shown in FIG.
Starting from FIG. FIG. 9 is a vertical sectional view schematically showing the structure of a conventional reactor building pool and its vicinity.
FIG. 11 is a perspective view showing a state in which a part between the equipment pool 5 and the reactor well 7 in FIG. 9 is partially cut away, and FIG. 11 is a cross-sectional view taken along the line AA in FIG. 9 showing a steam dryer. FIG. 12 is a plan view showing a suspended state, and FIG. 12 is a plan view showing a canal arrangement state between the reactor well 7 and the equipment pool 5 in FIG.

In FIG. 9, a reactor pressure vessel 1 is erected in a primary reactor containment vessel 6, and the primary reactor containment vessel 6 is installed in a reactor building 4. Reactor building 4
Above the reactor primary containment vessel 6 inside, an equipment pool 5 in which a steam dryer 2 and a steam separator 3 are temporarily placed, and a spent fuel storage pool 17 in which a reactor well 7 and a fuel rack 24 are stored.
Is being built. An operation floor 8 such as a fuel handling floor is installed above the equipment pool 5 and the spent fuel storage pool 17.

In a nuclear power plant, when regularly inspecting the inside of the reactor pressure vessel 1, the top cover shown by the dotted line is removed, the steam dryer 2 and the steam separator 3 are taken out from the inside of the reactor pressure vessel 1, and these are removed. During inspection and refueling of the reactor pressure vessel 1, the reactor pressure vessel 1 is transferred and temporarily stored in the equipment pool 5. As shown in FIGS. 10 and 12, the equipment pool 5 is arranged adjacent to the reactor well 7 above the primary reactor containment vessel 6 so that the periodic inspection work can be performed efficiently.

[0005]

In the periodic inspection work of a nuclear power plant, the reactor pressure vessel 1 which mainly contains a fuel assembly (hereinafter, referred to as fuel) is opened, and the inside of the reactor pressure vessel 1 is opened. There is a periodical inspection work inside the reactor well 7 that inspects and replaces the fuel of 1, and then restores it. In this work, in order to inspect and replace the fuel in the reactor pressure vessel 1, the steam dryer 2 and the steam separator 3 installed above the reactor core in the reactor pressure vessel 1 are installed outside the reactor pressure vessel 1. Need to take out.

However, when the steam dryer 2 is to be taken out of the reactor pressure vessel 1, it is necessary to move the steam dryer 2 in the air. Therefore, as shown in FIG. The oblique radiation from the upper part of the steam dryer 2 to the upper corner of the pool wall structure 14
There is a problem of receiving and exposing a lot of radiation. On the other hand, also in the spent fuel storage pool 17, there is a problem similar to the above in the case of the operation of handling the spent fuel.

The present invention has been made to solve the above-mentioned problems, and its purpose is to perform equipment such as a steam dryer or a steam separator transferred into the equipment pool 5 during a periodical inspection work of the reactor pressure vessel. Another object of the present invention is to provide a structure of a reactor building indoor pool that can reduce the exposure of workers on the operation floor from the spent fuel from the spent fuel storage pool 17.

[0008]

According to the invention of claim 1, an operation floor, a spent fuel storage pool, a reactor well, a steam dryer and steam are provided in a reactor building in which a cylinder type reinforced concrete reactor containment vessel is installed. In a structure of a reactor building indoor pool in which an equipment pool in which a separator or the like is temporarily placed is constructed, two skeletons rigidly joined to at least one of the equipment pool and the spent fuel storage pool on the upper surface of the reactor containment vessel. It is characterized in that a shield wall of reinforced concrete provided with a metal liner including walls is provided.

According to a second aspect of the present invention, a frame for temporarily placing an upper lattice plate on at least one of the steam dryer and the steam separator temporarily placed in the equipment temporary pool is attached to and detached from the equipment pool. The height from the bottom of the equipment pool to the upper end of the shielding wall is freely set, and the height at which the upper lattice plate is temporarily placed on the frame and the water depth required to shield radiation from the upper lattice plate. It is characterized by being set to a height determined by and.

According to a third aspect of the present invention, the height from the bottom of the spent fuel storage pool to the upper end of the shielding wall is set when the spent fuel is stored in a fuel storage rack installed in the spent fuel storage pool. It is characterized in that it is set to a height determined by the height and the water depth necessary to shield the radiation from the spent fuel.

In the equipment pool having the above-mentioned structure, a worker on the operation floor is provided by a shielding wall provided on the wall body of the equipment pool when the steam dryer or the like is taken out of the air during the periodic inspection of the reactor pressure vessel. It is possible to reduce the radiation received from devices such as the steam dryer and the steam separator. Further, similarly, the radiation exposure from the spent fuel in the spent fuel storage pool can be reduced.

Further, when the top slab on the upper part of the cylinder type reinforced concrete reactor containment vessel receives a pressure load due to discharge of high-pressure fluid inside the reactor containment vessel at the time of accident of the reactor pressure vessel, the top slab and the cylindrical part In the present invention, in order to reduce the stress concentration, the pool girder that is a side wall integrally formed from the equipment pool that functions as a beam that restrains the top slab from the upper side to the fuel storage pool that faces directly in order to reduce this stress concentration. The proof stress against bending can be improved by providing the shielding wall.

[0013]

BEST MODE FOR CARRYING OUT THE INVENTION A first embodiment of the structure of a reactor building pool according to the present invention will be described with reference to FIGS. 1 to 4. 1 is a vertical cross-sectional view schematically showing the structure of a reactor building indoor pool according to the present embodiment, FIG. 2 is a cross-sectional view taken along the line AA of FIG. 1, and FIG. 3 is a cylinder-type reinforced concrete atom in FIG. FIG. 4 is a longitudinal sectional view of the reactor containment vessel, and FIG. 4 is a perspective view showing the structures of the reactor containment vessel and the pool girder in FIG. In each drawing, the same parts as those in FIGS. 9 to 12 are designated by the same reference numerals, and the overlapping description will be omitted.

The part of this embodiment different from the conventional example is shown in FIG.
And as shown in FIG. 4, the cylindrical portion 15 of the reactor containment vessel 9 is placed in the equipment pool 5 located between the operation floor 8 and the cylinder type reinforced concrete reactor containment vessel 9.
The pool girder 18 including the two wall frames 14 rigidly joined to the top slab 12 is provided, and the reinforced concrete shielding wall 11 is provided on the pool girder 18. Note that reference numeral 13 in FIG. 1 denotes a joint portion between the top slab 12 and the cylindrical portion 15.

In the periodic inspection of the nuclear reactor, however, when the steam dryer 2 in the reactor pressure vessel 1 is lifted and moved in the air, as shown in FIG.
There is an effect of radiation from the steam dryer 2 on the upper worker. As a countermeasure against this, in the present embodiment, as described above, the shield wall 11 made of reinforced concrete with a metal liner for shielding the radiation from the steam dryer 2 to the workers on the operation floor 8 on the wall frame 14 of the equipment pool 5 is used. Has been installed.

The shielding wall 11 shields most of the radiation from the steam dryer 2 to reduce the influence of the radiation from the steam dryer 2, and thus the radiation exposure dose to the worker working on the operation floor 8. Can be reduced. Reference numeral 19 denotes radiation that is obliquely dissipated from the upper end of the steam dryer 2, and 20 denotes radiation that is shielded by the shield wall 11.

When the top slab 12 above the reactor containment vessel 9 receives a pressure load 16 due to the discharge of high-pressure fluid inside the reactor containment vessel 9 at the time of the accident of the reactor pressure vessel 1, the top slab 12 is Stress concentration occurs at the joint portion 13 of the cylindrical portion 15 and.

In order to reduce this stress concentration, according to the present embodiment, a side wall integrally formed from the equipment pool 5 which serves as a beam for restraining the top slab 12 from the upper side to the spent fuel storage pool 17 which directly faces it. The bending resistance of a certain pool girder 18 can be improved by the shielding wall 11.

Further, as shown in FIGS. 3 and 4, the top slab 12 subjected to the pressure load 16 is bent, and as shown in FIG.
Pool girder rigidly joined to the reactor containment vessel 9 shown in
Although a bending load is also applied to 18, the provision of the shielding wall 11 according to the present embodiment increases the height direction of the beam cross-sectional area of the pool girder 18, which is a beam, so that the bending resistance of the pool girder 18 is increased. Can be improved.

Next, the second embodiment of the present invention will be described with reference to FIGS.
An embodiment will be described. In this embodiment, as shown in FIG. 5, a detachable mount 21 for temporarily placing the upper grid plate 10 is horizontally installed above the steam dryer 2 and the steam separator 3 in the equipment pool 5. is there.

The height of the equipment pool 5 from the pool bottom and the height of the upper lattice plate 10 temporarily placed on the mount 21 and the upper lattice plate
The height is determined by the depth of about 4 m that can shield the radiation from 10. The outer wall of the equipment pool 5 is provided with the wall frame 14 and the shielding wall 11 shown in FIG. 1 as in the first embodiment.

In the equipment pool 5, however, the upper lattice plate 10
A pedestal 21 for temporary placement can be installed above the steam dryer 2 and steam separator 3 temporarily placed in the pool 5, and the upper grid plate 10
Can be temporarily placed. Also, the conventional surrounding wall frame 14
The total height of the height of the building and the height of the shielding wall 11 should be about 4 m, which is necessary for the radiation from the upper lattice plate 10 on the operation floor 8 level, due to the water filling up to near the operation floor 8 level. The height is possible.

Next, the operation of the second embodiment will be described. As shown in FIG. 12, the equipment pool 5 has conventionally required an area large enough to arrange the upper grid plate 10 in addition to the steam dryer 2 and the steam separator 3 at the bottom of the pool. According to the form, it is not necessary.

That is, as shown in FIG. 5, the pedestal 21 is provided and the shielding water depth H of about 4 m is provided above the upper lattice plate 10, so that the operation floor 8 is provided in addition to the effect of the first embodiment. The effect of radiation on the level is the same as before, and the area required for temporary equipment of the pool bottom can be reduced.

Further, the movement path of the steam dryer 2 and the steam separator 3 from the reactor well 7 is changed by changing the position of the canal 22 as indicated by the hatched area 23 in FIG. 6 or 7. Thus, the plane area of the equipment pool 5 itself can be reduced.

In this case, since the plane area of the equipment pool 5 can be reduced in the direction of the reactor well 7 as shown in FIG. 6 or 7, the beam length of the pool girder 18 can be shortened as compared with the conventional case, and the reactor containment can be reduced. It is possible to increase the bending resistance of the pool girder 18 which has a role of restraining the top slab 12 of the container 9 from above.

When the flat area of the equipment pool 5 on the operation floor 8 of the reactor building 4 is reduced, the temporary equipment area or work area on the operation floor 8 is shown in FIG. 6 and FIG. It is possible to increase only (shaded portion) 23, and it is possible to improve the work efficiency of normal regular inspection work.

Here, the case of the regular periodical inspection work is when the upper lattice plate 10 does not need to be taken out from the reactor pressure vessel 1, but a failure in the reactor pressure vessel 1 or a reactor pressure When repairing the lower part of the vessel 1, it is necessary to take out the upper lattice plate 10 from the reactor pressure vessel 1.

Next, a third embodiment of the present invention will be described with reference to FIG. 8 corresponds to FIG. 9. Therefore, in FIG. 8, the same parts as those in FIG. 9 are designated by the same reference numerals, and the description of the overlapping parts will be omitted.

The present embodiment is different from the conventional example in that the height of the equipment pool 5 from the pool bottom is the height when the spent fuel 25 is stored in the spent fuel storage rack 24 and the spent fuel.
Approximately 2 heights of 25 and shielding of radiation from spent fuel 25
The height is the same as the height of the fuel storage pool 17, which is determined by the water depth of about m. That is, in FIG. 8, the spent fuel storage pool 17 that faces the reactor well 7 is arranged above the reactor containment vessel 9 like the equipment pool 5.

Here, the height of the equipment pool 5 is from the bottom of the conventional spent fuel storage pool 17 to the operation floor 8
Of the spent fuel 25 on the spent fuel storage rack 24 and the height L of the spent fuel 25 passing on the spent fuel storage rack 24. The height of the spent fuel 25 moving on the storage rack 24 is determined by the height of the shield water depth D of about 2 m up to the vicinity of the operation floor 8 so that the spent fuel 25 can be safely handled.

As a result, the level of the bottom slab 26 of the spent fuel storage pool 17 is changed to the top slab of the reactor containment vessel 9.
Match 12 levels. In the spent fuel storage pool 17 having the above-mentioned configuration, the level of the bottom slab 26 is the reactor containment vessel 9
By matching the top slab 12 levels of
It is possible to improve construction workability by integrating slabs.

Further, as shown in FIG. 10, the operation floor 8 is provided in the area 27 above the reactor containment vessel 9 where the spent fuel storage rack 24 could not be arranged due to lack of water depth.
Since the height up to the level is the height at which the spent fuel storage rack 24 is placed and the spent fuel 25 can pass through the spent fuel storage rack 24 underwater, the spent fuel storage rack 24 can be placed. As a result, in addition to the effects of the first and second embodiments, it is possible to increase the storage capacity of the spent fuel 25 in the spent fuel pool 17.

[0034]

According to the present invention, a metal liner-lined shield wall is provided on the peripheral wall of an equipment pool or a spent fuel storage pool so that a steam dryer, a steam separator, a spent fuel, etc. Radiation can be shielded to reduce the radiation exposure of workers, and the bending strength as a beam is increased by increasing the height of the pool girder.

Further, the plane area of the equipment pool can be reduced by providing the upper lattice plate temporary mount in the equipment pool, and the total height of the equipment pool can be made equal to the depth of the spent fuel storage pool. The storage area can be increased.

[Brief description of the drawings]

FIG. 1 is a first structure of a reactor building indoor pool according to the present invention.
FIG. 3 is a vertical cross-sectional view schematically showing the embodiment of FIG.

FIG. 2 is a vertical cross-sectional view taken along the line AA in FIG.

FIG. 3 is a vertical cross-sectional view showing the reactor containment vessel in FIG.

FIG. 4 is a perspective view showing a reactor containment vessel and a pool girder in FIG.

FIG. 5 is a second structure of the reactor building indoor pool according to the present invention.
FIG. 5 is a vertical cross-sectional view for explaining the embodiment of FIG.

FIG. 6 is a plan view for explaining the function and effect in FIG.

FIG. 7 is a plan view for explaining another example of the function and effect in FIG.

FIG. 8 is a vertical cross-sectional view schematically showing the structure of a reactor building indoor pool and its vicinity according to a third embodiment of the present invention.

FIG. 9 is a longitudinal sectional view schematically showing the structure of a conventional reactor building pool.

FIG. 10 is a perspective view showing the equipment pool in FIG. 9 with a part thereof cut away.

FIG. 11 is a vertical cross-sectional view taken along the line AA in FIG.

12 is a plan view showing the equipment pool in FIG. 9. FIG.

[Explanation of symbols]

1 ... Reactor pressure vessel, 2 ... Steam dryer, 3 ... Steam separator, 4 ... Reactor building, 5 ... Equipment pool, 6 ... Primary reactor containment vessel, 7 ... Reactor well, 8 ... Operation floor, 9 ... Cylinder type reinforced concrete reactor containment vessel, 10 ... Upper lattice plate, 11 ... Shielding plate, 12 ... Top slab,
13 ... Joined part, 14 ... Wall body, 15 ... Cylindrical part, 16 ... Pressure load, 17 ... Spent fuel storage pool, 18 ... Pool girder, 19
… Radiation, 20… Shielding radiation, 21… Stand, 22… Canal, 23
… Decreased area (hatched area), 24… Spent fuel storage rack, 25
… Spent fuel, 26… Bottom slab, 27… Area on RCCV, D… Shield water depth, H… Shield water depth, L… Fuel length, R
… The height of the fuel rack when storing spent fuel.

Claims (3)

[Claims] 1. An operation floor in a reactor building in which a cylinder-type reinforced concrete reactor containment vessel is installed,
At least one of the equipment pool or the spent fuel storage pool in a structure of a reactor building indoor pool in which an equipment pool in which a spent fuel storage pool, a reactor well, a steam dryer, a steam separator, etc. are temporarily placed is constructed. A structure of a pool for a reactor building, characterized in that a shield wall made of reinforced concrete provided with a metal liner including two frame walls rigidly joined to the upper surface of the reactor containment vessel is provided. 2. A pedestal for temporarily placing an upper grid plate on at least one of the steam dryer and the steam separator temporarily placed in the equipment temporary storage pool is detachably provided in the equipment pool, and The height from the bottom of the equipment pool to the upper end of the shielding wall is determined by the height at which the upper lattice plate is temporarily placed on the frame and the water depth required to shield the radiation from the upper lattice plate. The structure of the reactor building indoor pool according to claim 1, wherein 3. The height from the bottom of the spent fuel storage pool to the upper end of the shielding wall is the height when the spent fuel is stored in a fuel storage rack installed in the spent fuel storage pool, and The structure of the reactor building indoor pool according to claim 1, wherein the height is set to a height determined by a water depth required to shield radiation from spent fuel.