JPH0862368A - Carrying method at replacement of reactor pressure vessel and reactor internal structure, and reactor building - Google Patents

Abstract

PURPOSE: To shorten the operation stopping period accompanying the life extending work of a nuclear power station. CONSTITUTION: When a reactor pressure vessel 1, a reactor internal structure, a CRD housing 23, and a γ-shield 17 are carried out of the reactor building for replacement, the reactor pressure vessel 1 on which the internal structure and the CRD housing are still mounted is integrated with the γ-shield 17 to simultaneously carry out them. Thus, the time for disassembling the reactor pressure vessel, reactor internal structure, CRD housing and γ-shield within the reactor building is dispensed with, and the time required for the carrying-out is shortened, so that the operation stopping time accompanying the life extending work can be shortened.

Description

Detailed Description of the Invention

[0001]

BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to unloading a nuclear reactor pressure vessel of a nuclear power plant, a reactor internal structure, and a radiation shield which is arranged in a cylindrical shape around an RPV, and more particularly to a reactor pressure. The present invention relates to a unloading method for replacing a container and an internal structure of the reactor and equipment therefor.

[0002]

2. Description of the Related Art Reactor pressure vessel (hereinafter referred to as RPV)
Is the most important equipment of a nuclear power plant, and generally, the useful life of the nuclear power plant also depends on the design life of the RPV. When a nuclear power plant reaches the end of its useful life, it must be dismantled and decommissioned. In nuclear power plant decommissioning technology, RPVs, internal reactor structures, radiation shields (hereinafter referred to as γ shields) arranged in a cylindrical shape around RPVs, CRD housings, piping inside the reactor containment vessel After dismantling and other various equipment in the reactor building of the nuclear power plant, and then carrying them out to the outside of the reactor building.

Japanese Unexamined Patent Publication No. 60-91299 shows an example of a disassembling apparatus for dividing and dismantling an RPV by using a cutting machine in an example of the above decommissioning technology. Also, Japanese Patent Laid-Open No. 3-18799
The publication discloses an example of a system for disassembling an RPV by using a cutting device equipped with a swing drive device, a lift drive device, and a support drive device. A disassembling method for disassembling the furnace internal structure is disclosed in JP-A-60-24499.

On the other hand, in order to supply electricity, it is necessary to install a new power plant in order to supplement the power generation capacity of the decommissioned nuclear power plant. But to build a new power plant,
It requires a long construction period and enormous cost. In addition, in order to construct a new nuclear power plant, it is necessary to clear various issues such as a site candidate plan that meets the site conditions and the consent of local residents. Therefore, it has become an important issue to extend the service life of currently operating aged nuclear power plants.

At aged nuclear power plants, except for RPV and in-core structures, each facility and equipment is repaired and replaced in a timely manner, and it is refreshed and a life extension measure is taken. From the standpoint of operating the plant within its life, it was not necessary to replace the RPV and the reactor internals.

In order to extend the service life as described above, it is necessary to replace the RPV, in-core structure and CRD housing. The γ shield itself can be continuously used as it is, but in order to replace the RPV, the structure must be removed. In extending the service life, how to shorten the plant shutdown period and how to carry out "RPV and in-core structure replacement work" in a short period of time becomes an issue. The RPV and in-core structures that have been in service for a long period of time have strong radioactivity, so in order to carry out replacement work in a short period of time, first, "RPV and in-core structure unloading work" must be performed. The issue is how to do it in a short period of time.

[0007]

Regarding the decommissioning technology of a nuclear power plant, the technology as shown above is known, but the RPV and the reactor internal structure are replaced with new ones. There is no consideration for taking out the internal structure. For this reason, the above-mentioned conventional technique has the following problems when it is applied to a construction for extending the life of a nuclear power plant.

[0008] As a unloading method for extending the life of a nuclear power plant, a method of applying the decommissioning technology to dismantle and carry out equipment such as RPV, reactor internals, γ shield, and CRD housing in the reactor building is considered. However, this method requires a long construction period and enormous cost to carry out.

[0009]. When extending the useful life of a nuclear power plant, if the construction method of disassembling and carrying out by the above construction method is adopted, the plant suspension period becomes longer.

An object of the present invention is to shorten the plant shutdown period as much as possible when carrying out construction for extending the useful life of a nuclear power plant.

[0011]

Means for Solving the Problems The above-mentioned object is achieved by integrally forming an RPV, a reactor internal structure, a gamma shield, a CRD housing, etc. into a large block and simultaneously carrying them out to the outside of the reactor building using a large lifting machine. To be done.

The above-mentioned object is also to carry out the reactor pressure vessel to the outside of the reactor building using a large lifting machine with the reactor internals, CRD housing, etc. attached, and further to take a cylindrical shape without disassembling the γ shield. It can also be achieved by using a large lifting machine and carrying it out to the outside of the reactor building.

As a nuclear reactor building, an opening provided with a removable closing means is provided in the ceiling of the nuclear reactor building above the reactor pressure vessel, and the inside diameter of the opening is defined as the radiation shield of the nuclear reactor pressure vessel. It is desirable to make it larger than the outer diameter.

When carrying out the reactor pressure vessel,
Arranged a shield building for carrying out the reactor pressure vessel, which is adjacent to the reactor building and extends to the upper part of the reactor building to cover the opening.
The space between the ceiling lower surface of the reactor pressure vessel unloading upper part of the reactor building and the reactor building upper surface should be larger than the height of the reactor pressure vessel, and the reactor building side wall and the reactor pressure vessel unloading shielding. The distance between the building side walls should be larger than the outer diameter of the radiation shield of the reactor pressure vessel.

As a shield building for carrying out the reactor pressure vessel,
A part of the upper part of the side wall and a part of the ceiling part continuous with the part of the side wall can be opened and closed in stages, or the interior of the shield building for unloading the reactor pressure vessel can be opened continuously. It is desirable to be able to move gradually.

[0016]

According to the present invention, the reactor internals and the CRD are
The reactor pressure vessel with the housing still attached is integrated with the radiation shield of the reactor pressure vessel,
Since it is carried out to the outside of the reactor building at the same time using a large lifting machine, the time for dismantling those components of the reactor pressure vessel inside the reactor building is not necessary, and the R
The time required to carry out the PV, reactor internals, γ shield, CRD housing, etc. is shortened.

Further, the reactor pressure vessel is carried out to the outside of the reactor building by using a large lifting machine with the reactor internal structure, the CRD housing, etc. attached, and the γ shield is integrated into a cylindrical shape without disassembling. Even if it is carried out to the outside of the reactor building using a large lifting machine as it is, the number of times of carrying out is increased compared with the case where the whole is carried out as a unit, but the reactor pressure vessel and γ shield inside the reactor building Since the dismantling of is omitted, the time required for carrying out as a whole is shortened.

An opening with a removable closing means is provided in the ceiling of the reactor building above the reactor pressure vessel, and the inside diameter of the opening is made larger than the outside diameter of the radiation shield of the reactor pressure vessel. If this is done, the work of forming the opening of the ceiling when carrying out the reactor pressure vessel and the γ shield becomes easier, and the time required for the work is shortened.

A shield building for unloading the reactor pressure vessel adjacent to the reactor building and extending to the upper portion of the reactor building and covering the opening is provided, and a shield building for unloading the reactor pressure vessel at the upper portion of the reactor building is provided. The distance between the ceiling lower surface and the reactor building upper surface is made larger than the height of the reactor pressure vessel, and the distance between the reactor building side wall and the reactor pressure vessel carry-out shield side wall is adjusted to the radiation shield of the reactor pressure vessel. If it is larger than the outside diameter, the reactor pressure vessel hung outside the reactor building can be moved inside the shield building for unloading the reactor pressure vessel, and the reactor building and the reactor pressure vessel can be moved to the external environment. The amount of radioactive material released can be reduced.

As a shield building for carrying out a reactor pressure vessel (hereinafter, the same as the shield building), a part of the upper part of the side wall and a part of the ceiling part continuous with the side wall can be opened and closed for each part. When using a lifting machine equipped with a tilting jib, part of the upper part of the side wall of the shielded building and part of the ceiling that is continuous with the part of the side wall are opened and the jib is inclined so that the jib enters there. be able to. In this way, the lifting machine can be placed close to the reactor building, and the lifting radius of the lifting machine can be reduced. When the reactor pressure vessel is lifted and moved to the outdoor part of the reactor building, as the jib moves up, the part where the jib penetrates the ceiling part and side wall part of the shielded building moves, so open that part one by one and open the other parts one by one. If it is closed, the amount of radioactive materials released from the reactor building and the reactor pressure vessel to the external environment can be reduced. Also, rather than making it possible to open and close a part of the upper part of the side wall and a part of the ceiling part continuous to the part of the side wall, it is possible to connect the ceiling part and the side wall part where the jib enters the shielding building in a band shape. 20 and the wall surface parallel to the paper surface on the front side and the back side of the paper surface of FIG. The release of substances is even less.

[0021]

DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS An embodiment of the present invention will be described in detail below.
★ Fig. 1 is a cross-sectional view of the reactor pressure vessel and reactor internals of a boiling water type light water reactor. Each device in the reactor pressure vessel (RPV) 1 is generally called a reactor internal structure 2. The in-core structure 2 includes a steam dryer (dryer) 3, a separator (including a steam separator and a shroud head) 4, a core shroud 5, a core support plate 6, an upper lattice plate 7, a shroud support 8 and the like. Is a partition for guiding the flow of the reactor coolant that enters the core while accommodating each in-reactor device that forms the core part, and the reactor coolant flow path to the core and the steam-water mixture. A flow path and a necessary flow path for water and steam separated by a built-in steam separator are formed, thereby providing a circulation circuit for the reactor cooling water.

FIG. 2 is a sectional view of the reactor pressure vessel.
The RPV 1 is provided with a main steam nozzle 9, a water supply nozzle 10, a core spray nozzle 11, a recirculation inlet nozzle 12, a recirculation outlet nozzle 13, various instrumentation nozzles 14, and a drain / vent nozzle 15, and each nozzle is provided. Is connected to each system piping.

FIG. 3 is a sectional view of the reactor containment vessel.
In the containment vessel (hereinafter referred to as PCV) 16 of the reactor, RP
Radiation shield 17 (hereinafter referred to as γ shield) provided on the outer periphery of V1, RPV pedestal 1 that is the basis of RPV1
8. Bulkhead plate 1 that divides the upper part of the PCV into upper and lower parts
There are 9, a radial beam 27 and a support 28. Incidentally, R
In the PV pedestal 18, a beam 22, a CRD housing 23, I for supporting a control rod drive device 20 (hereinafter referred to as CRD) and a neutron flux detector 21 (hereinafter referred to as ICM).
There is a CM housing 24 and a CRD housing support 25 that supports the CRD housing 23.

The connecting portion between the γ shield 17 and the RPV pedestal 18 is fixed by two γ shield foundation bolts 29 on the γ shield circumference. γ shield 1
An RPV stabilizer, which is an RPV seismic support, and a PCV stabilizer 30, which is a PCV seismic support, are provided on the upper portion of the device 7.

FIG. 4 is a sectional view of the reactor building. Inside the reactor building 31, a spent fuel pool 33 and a dryer separator pool 34 (hereinafter referred to as D / S pool) are provided adjacent to the reactor well 32.

An embodiment of the present invention will be described with reference to FIG.

First, in step 40, the generator is disconnected, the periodical inspection of the nuclear power plant is started, and in step 41, nuclear reactor opening work is performed. The reactor opening work is a critical work required to handle the fuel in the core, and mainly the PCV head removing work for removing the reactor containment vessel lid and the reactor pressure vessel lid 37 (hereinafter referred to as RPV head) are performed. RP to remove
The V head removal work, the dryer removal work to remove the steam dryer 3 and the separator removal work to remove the separator 4 are performed.

Next, in step 42, the work of extracting all the fuel from the core is performed. The total fuel removal operation is an operation of moving all the fuel loaded in the core to the spent fuel rack 56 of the spent fuel pool 33. When carrying out the RPV and the reactor internals, the fuel itself is a radioactive source, so to carry the RPV and the reactor internals out of the reactor building with the fuel loaded, the There is a risk of radioactive contamination of the plant and 100% fuel removal work is carried out to reduce the surface dose of RPV.

When all the fuel has been taken out, step 4
Proceeding to the reactor recovery work of No. 3, the work of installing the dryer 3 and the separator 4 on the core shroud 5 and the work of installing the RPV head 37 are performed.

Next, in step 44, the RPV and the γ shield are disassembled. Procedure 44 is to cut the radial beam and the support for attaching the γ shield 44a, the RPV nozzle portion and the pipe cutting 44b, and to fix the γ shield to the RPV 44c
It includes a shield foundation bolt chip 44d, a duct, an operation floor carrying-out 44e, a bulkhead plate cutting 44f, a PCV stabilizer cutting 44g, and the like.

In parallel with procedure 44, procedure 45 is performed in the RPV pedestal. Step 45 is to remove CRD housing support 45a, cable removal 45b, CR
D housing and ICM housing removal 45c, CR
It includes a D housing beam detachment 45d and the like.

After the reactor recovery work in step 43 is completed, an opening 57 having an inner diameter larger than the outer diameter of the γ shield 17 is provided in the ceiling of the reactor building (step 4).
7). Before the opening 57 is provided, as shown in FIG. 20, a shield building for unloading the reactor pressure vessel (hereinafter referred to as a clean room) that is adjacent to the reactor building 31 and extends to a position covering the opening 57. ) 60 must be installed (procedure 46), but installation work may be started before the generator is disconnected for parts that do not directly affect the safety of the reactor building. The distance H between the lower surface of the ceiling 60A of the clean room 60 and the upper surface of the reactor building 31 is set to a value larger than the height of the reactor pressure vessel, and the side wall 60B and the reactor building 3
The distance B from the side wall of 1 is set to a value larger than the outer diameter of the γ shield 17. It is desirable to plan the opening 57 in advance so that the members can be easily removed during the plant construction stage. Simultaneously with the installation of the clean room 60, the large lifting machine 58 is installed at a predetermined position (procedure 48). Also,
As shown in FIG. 22, the raising / lowering member 58A of the large-sized lifting machine 58.
The part of the upper part of the side wall 60B of the clean room 60 and a part of the ceiling part 60A continuous with the part of the side wall are partially formed by the width of the raising and lowering member 58A so that the part can enter the clean room 60 when tilted to the hanging position. It is configured to move laterally to form the opening. The side wall 60B and the ceiling portion 60A are partially opened at the portion where the raising and lowering member 58A penetrates the side wall 60B and the ceiling portion 60A, and the other portions are closed. The position can be changed. The ceiling is designed to move in half on both sides (perpendicular to the plane of the paper), and when the hoist of the lifting machine passes, it is opened and closed again by the width of the hoist.

In order to make the opening formed in the clean room 60 as small as possible when the raising / lowering member 58A of the large-sized hoisting machine 58 is inclined to the hoisting position, the side wall and the ceiling portion of the relevant portion are continuously bendable strip-shaped. Alternatively, the connection portion with the wall surface parallel to the paper surface of the clean room 60 may be slidable. FIG. 37 shows
An example using such a strip-shaped wall surface is shown. A wall surface 60C indicated by a broken line shows a state in which the strip-shaped wall surface is moved to the inside of the clean room 60 to the maximum, and a wall surface 60D has the tilting member 58 slightly. The position of the strip-shaped wall when getting up is shown. In any case, the clean room 60 portion on the lifting machine side of the strip-shaped wall surface indicated by the broken line is open to the outside, and the reactor building side portion is closed to the outside.

The clean room 60 may be configured to be movable toward the inside, and the wall surface may be moved to the position shown by the dotted line in FIG. As described above with respect to the movement of the hanging device, at the center of the strip-shaped wall surface, there is provided an opening / closing means for opening the lifting device width to form a hanging device passage when the lifting device of the lifting machine passes. Has been.

Procedures 44, 45, 46, 47 and Procedure 48
When is finished, the procedure proceeds to step 49 to carry out the RPV. In step 49, drainage (49a) of the reactor water (reactor coolant) contained in the RPV 1, removal of the RPV installation bolt (49b), RPV 1, internal reactor structure 2, γ shield 17, and CRD housing 23 are performed. Lifting with a large integrated block (49c), carrying out outside the reactor building (49c)
d) is performed. When cutting the RPV nozzle and piping,
Use a plug to stop the water in advance from the inside of the RPV or RP
Either the V-draining or the cutting of the nozzle portion is performed, but the former is preferable in terms of radiation shielding.

The RPV may be carried out with the reactor water contained in the RPV 1 without performing the above-mentioned draining operation of the reactor water. In that case, the reactor water in the RPV also has an effect of shielding radiation when the RPV 1, the internal structure 2, the γ shield 17, the CRD housing and the like are carried out to the outside of the reactor building. However, when carrying out with the reactor water in
In order to prevent water leakage from the nozzles 9 to 15 provided on the PV 1, after plugging each nozzle portion and cutting the pipe as described above, each nozzle 9 to 15 is covered with a lid from the outside. Must be installed.

If the RPV 1, the reactor internal structure 2, the gamma shield 17, the CRD housing 23, and the like are integrated into a large block, the gamma shield is essentially a shield, so that it can be carried out outside the reactor building. The shielding effect against the radiation emitted from the RPV 1 and the reactor internal structure 2 is also improved.

Dismantling work 44 of RPV 1 and γ shield 17
Is performed including the following steps. It should be noted that the described order does not define the order of work, and the order may be interchanged and there may be parallel work. Each work will be described with reference to FIGS.

A. The cutting work 44a of the radial beam 27 and the support 28 is performed (see FIGS. 7 and 8 showing A and B parts and A and B parts in detail in FIG. 6). When removing the support 28, the nut is removed from the bolt embedded in the γ shield 17 and the support 28 is removed. When removing the radial beam 27, the illustrated bolt 27 'is removed to separate the radial beam 27.

B. A cutting operation 44b of the RPV nozzles 9 to 15 and the pipes attached to the nozzles is performed (C, D, E, F, G portions in FIG. 6 and FIGS. 9 to 13 showing the details thereof).
And FIGS. 14 and 15). An example of cutting the RPV nozzles 9 to 15 and the pipe will be described with reference to FIGS. 14 and 15.
FIG. 14 shows the positional relationship between the RPV nozzle portions 9 to 15 and the γ shield 17. The γ shield 17 has an RPV nozzle portion 9
An opening is formed at a position of ~ 15, and each nozzle is connected to a pipe 67 that is inserted into the opening. RPV1
A metal heat insulating material 66 is attached to the outer periphery of the pipe at a position between the gamma shield 17 and a metal heat insulating material 66 'on the outer surface of the pipe. The outside of the metal heat insulating material 66 ′ in the opening of the γ shield 17 is closed by a shield plug 64. In the case of cutting the pipe, first, the metal heat insulating material 66 'mounted on the outer periphery of the pipe is cut and removed, and then the shield plug 64 is cut and removed. Then piping 67
Is cut at a predetermined position, for example, a joining position between the nozzle and the pipe and an appropriate position outside the γ shield 17, and then removed. After removing the pipe 67, a temporary shielding plate 68 is attached to the outer surface of the opening of the γ shield 17 so as to cover it. FIG. 15 shows a state in which the temporary shielding plate 68 is provided. Since the radiation inside the RPV 1 comes out from the nozzle after cutting the pipe 68, the temporary shielding plate 68 is effective as a radiation shielding, and it is effective to use a lead plate or the like.

C. The weight of the γ shield 17 is supported by the RPV.

Various methods can be applied as a method for supporting the weight of the γ shield 17 on the RPV. As shown in FIG. 16, a metal round bar, for example, a steel rod 71 is inserted into the hole of the nozzle after the pipe 67 is removed and welded and fixed to the nozzle, and the steel rod 71 is fixed to the opening 69 with a supporting material 70. hand,
The weight of the γ shield 17 may be supported by the RPV via the steel rod 71 and the support member 70. Also, steel rod 7
1, the support member 70 is directly welded and fixed to the end portion of the nozzle, and the support member 70 is fixed to the opening 69 so that the γ shield 1
The weight of 7 may be supported by the RPV via the support material 70. Alternatively, concrete may be poured between the RPV 1 and the γ shield 17 to be solidified, and the two may be bonded to each other so that the weight of the γ shield 17 is supported by the RPV. Further, the weight of the γ shield 17 may be supported by the RPV by passing a wire rope through the opening 69 of the γ shield 17.

D. The chipping work 44d of the foundation bolt 29 for positioning the γ shield 17 on the RPV pedestal is performed (see FIG. 7 showing the details of the A portion and the A portion of FIG. 6). The concrete around the foundation bolt embedded in the RPV pedestal 18 is removed to separate the γ shield 17 and the RPV pedestal.

E. Carrying out work 4 such as duct 63 and operation floor
4e (see FIG. 7 showing the details of the H portion and the H portion in FIG. 6).

F. The cutting operation 44f of the bulkhead plate 19 is performed (see FIG. 18 showing the I portion and the I portion in FIG. 6). The bulkhead plate 19 is composed of an annular portion forming a floor plate and a reinforcing material on the bottom surface of the floor plate that reinforces the floor plate. Cutting is performed at a position close to the PCV body, and both the floor plate and the reinforcing material are separated from the PCV body. To do.

G. Cutting work of PCV stabilizer 30 4
Do 4 g. By cutting the PCV stabilizer 30, P
The CV body and the γ shield 17 are separated.

On the other hand, RPV and γ shield disassembly work 44
At the same time, the dismantling operation 45 in the RPV pedestal 18 is performed in the following procedure (see FIG. 3).

A. The removal work 45a of the CRD housing support 25 is performed.

B. Cable removal work 45b of CRD20 and ICM21 is performed.

C. The removal work 45c of the CRD housing 23 and the ICM housing 24 is performed. d. The work 45d for removing the housing beam 22 is performed.

After the dismantling work 44 of the RPV and the γ shield and the dismantling work 45 in the RPV pedestal described above are completed, next, the RPV, the internal structure of the reactor, the γ shield, and the CR.
Integrated carry-out work 49 by making the D housing a large block
Is done. RPV, reactor internals, γ shield, CRD
In carrying out the integrated unloading work 49 by making the housing into a large block, the opening 57 is installed in the ceiling of the reactor building 31 (procedure 47) (see FIG. 19), the reactor building 3
Installation of the large-sized lifting machine 58 in the vicinity of 1 (procedure 48) (see FIG. 20) is an essential condition.

In step 49, the RPV, the reactor internal structure, the γ shield, and the CRD housing are integrated into a large block, so that the RPV, the reactor internal structure, the γ shield, and the CRD housing structure are located near the reactor building 31. It is hoisted by a large-sized hoist 58 installed at the section, and then carried out to the outside of the reactor building (see FIGS. 22 to 26).

Here, when the opening 57 is provided in the ceiling of the reactor building shown in FIG. 19, it is desirable to provide a lid or an open / close shutter or the like above the opening so that the radioactivity does not leak outside.

When installing the large-sized hoist 58, gravel is laid on the ground so as to withstand its own weight and RPV, in-core structure, γ shield, and weight when hoisting the CRD housing, and iron plate is laid on it. Take measures to strengthen the ground.

As shown in FIG. 20, the reactor building 31
When carrying out the RPV to the outside, a clean room 60 having a radioactivity shielding effect (effect of suppressing release of radioactive substances to the external environment) is provided adjacent to the reactor building 31, and RP is provided therein.
Move a large block consisting of V, reactor internal structure, γ shield, and CRD housing. Also, clean room 6
A wire passage is provided in the ceiling portion of No. 0 so that a lifting tool (lifting wire) of the large lifting machine can be moved, and as described above, the hoisting member 58 of the lifting machine 58 is provided.
An opening, which is slightly wider than the width of the jib, is provided in the ceiling portion and the upper portion of the side wall so that the jib which is A can enter, and a means for closing this opening is also provided.

Regarding the phenomenon that the radiation of the RPV is emitted from the opening, it is possible to consider skyshine to the sky, but to reach the ground, the RPV surface dose (10 to 100 mS
It is about 10 to the fourth power of v), and it is estimated that the impact on the environment can be ignored.

The RP carried out from the reactor building 31
As shown in FIG. 21, the large block in which the V, the reactor internal structure, the gamma shield, and the CRD housing are integrated is stored and stored in the waste storage pit 59 provided at the bottom of the clean room 60, and the clean room 60. A large-scale decontamination device 61 installed inside decontaminates the RPV surface and γ-shield etc. to reduce the dose to the extent that it does not affect the environment, and then carries it out of the clean room 60. Waste treatment facility installed on the premises of the nuclear power plant. Any method of bringing in and storing may be used.

However, when carrying out to the outside of the clean room 60, it is necessary to provide a carry-out opening at the bottom of the clean room.

With the above, the carrying-out work by the large block in which the RPV, the internal structure of the furnace, the γ shield, and the CRD housing are integrated is completed.

The above shows the RPV, the internal structure of the furnace, and γ.
This is an example showing that the shield and the CRD housing are carried out as a large block, but the RPV, the reactor internal structure, and the CRD housing are integrated and integrated.
Needless to say, the above method can be applied to the case where the γ shields are integrally carried out. For example, FIGS. 27 to 31 show RPVs, reactor internals, and CRs.
This is an example in which the D housing is integrally carried out to the outside of the reactor building, and FIGS. 32 to 36 are examples in which the γ shield is integrally carried out to the outside of the reactor building. However, the γ shield is RPV
In the case of separately carrying out and as a unit, the pipes of the nozzle parts 9 to 15 of the RPV need to be cut off shortly before carrying out the γ shield or the RPV so as not to hit the γ shield.

By adopting the above method, RP
V, reactor internal structure, γ shield, CRD housing can be carried out as a unit with it installed, RP
It is possible to significantly reduce the carry-out time of V, in-furnace structure, γ shield, CRD housing, etc. In addition, inside the reactor containment vessel and reactor building, RPV, internal structure,
Since radioactive materials such as the γ shield and CRD housing are not dismantled, there is little scattering of radioactive dust inside the reactor containment vessel and the reactor building, and various construction work for extending the life of Fewer obstacles to implementation.

[0062]

According to the present invention as set forth in claim 1, the RP
V, in-reactor structure, γ shield, CRD housing, etc. can be unloaded while they are installed, and the effect of shortening the unloading time and shortening the plant shutdown period during life extension work is there.

According to the present invention as set forth in claim 2, since the RPV including the reactor internals, the CRD housing, etc. is carried out as a unit, and the γ shield is mounted in a cylindrical shape, it is carried out as a unit. The overall carry-out time is reduced, which has the effect of shortening the plant suspension period during the life extension work.

According to the present invention as set forth in claim 3, since an opening that can be opened and closed is provided in the ceiling above the reactor containment vessel of the reactor building, it is possible to carry out the reactor pressure vessel as a unit. Preparatory work will be easier and the work period will be shortened.

According to the present invention as set forth in claim 4, since a shield building is provided adjacent to the reactor building and extending so as to cover the opening of the ceiling portion of the reactor building, it is suspended from the reactor building. The discharged reactor pressure vessel can be moved inside the shield building, and the release of radioactive substances to the external environment can be reduced.

According to the present invention as set forth in claims 5 and 6, when a hoist equipped with a tilting jib is used, the hoist can be arranged close to the reactor building, so that the radioactive material to the external environment can be prevented. The lifting radius can be reduced and the lifting machine can be downsized without increasing discharge.

[Brief description of drawings]

FIG. 1 is a vertical cross-sectional view showing an example of a reactor pressure vessel and reactor internals of a boiling water type light water reactor.

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

FIG. 3 is a vertical cross-sectional view showing an example of an internal structure of a reactor containment vessel of a boiling water type light water reactor.

FIG. 4 is a cross-sectional view showing an example of a nuclear reactor building of a nuclear power plant using a boiling water type light water reactor.

FIG. 5 is a flowchart showing an example of the present invention.

FIG. 6 is a cross-sectional view showing the positions of major operations in the reactor containment vessel.

FIG. 7 is a cross-sectional view showing related details of a γ shield, a radial beam, and an RPV pedestal shown in part A of FIG.

FIG. 8 is a cross-sectional view showing details of the support shown in part B of FIG.

FIG. 9 is a cross-sectional view showing details related to a nozzle, a pipe, a metal heat insulating material and a γ shield shown in a C portion of FIG.

FIG. 10 is a cross-sectional view showing details relating to a nozzle, a pipe, and metal heat retention shown in a D part of FIG.

FIG. 11 is a cross-sectional view showing details related to the nozzle, the pipe, the metal heat insulating material, and the γ shield shown in the E portion of FIG.

FIG. 12 is a cross-sectional view showing details related to a nozzle, a pipe, a metal heat insulating material, and a γ shield shown in an F portion of FIG.

FIG. 13 is a cross-sectional view showing details related to a nozzle, a pipe, a metal heat insulating material and a γ shield shown in a G portion of FIG.

FIG. 14 is a cross-sectional view showing an example of the relationship between a nozzle, a pipe, a metal heat insulating material, and a γ shield.

FIG. 15 is a cross-sectional view showing a lid of a γ shield provided after cutting the pipe.

FIG. 16 is a cross-sectional view showing an example of a method for supporting the weight of the γ shield on the RPV.

17 is a cross-sectional view showing an example of the cutting position of the duct shown in the H portion of FIG.

FIG. 18 is an R of the bulkhead plate shown in part I of FIG.
It is sectional drawing which shows the relationship with PV and PCV.

19 is a cross-sectional view showing an example in which an opening is provided in the reactor building ceiling shown in FIG.

FIG. 20 is a cross-sectional view showing a state in which a large lifting machine is installed in the vicinity of the reactor building and a clean room is installed in contact with the reactor building.

21 is a cross-sectional view showing an example in which a waste storage pit and a large decontamination device are installed in the clean room shown in FIG.

FIG. 22 is a cross-sectional view showing a state in which the RPV, the reactor internal structure, the γ shield, and the CRD housing are applied to the outside of the reactor building to which the present invention is applied.

FIG. 23 is a cross-sectional view showing a state in which the RPV, the reactor internal structure, the γ shield, and the CRD housing are integrally carried out to the outside of the reactor building by applying the present invention.

FIG. 24 is a cross-sectional view showing a state in which the RPV, the reactor internal structure, the γ shield, and the CRD housing are integrally carried out to the outside of the reactor building by applying the present invention.

FIG. 25 is a cross-sectional view showing a state in which the RPV, the reactor internal structure, the γ shield, and the CRD housing are unloaded to the outside of the reactor building by applying the present invention.

FIG. 26 is a cross-sectional view showing a state in which the RPV, the reactor internal structure, the γ shield, and the CRD housing are integrally carried out to the outside of the reactor building by applying the present invention.

FIG. 27 is a diagram showing an RPV, an internal structure, and a CR to which the present invention is applied.
It is sectional drawing which shows the state which carries out the integrated body of D housing to the outdoor of a reactor building.

FIG. 28 is a diagram showing the application of the present invention to RPV, in-core structure, CR
It is sectional drawing which shows the state which carries out the integrated body of D housing to the outdoor of a reactor building.

FIG. 29 is a diagram showing the application of the present invention to RPV, in-core structure, and CR.
It is sectional drawing which shows the state which carries out the integrated body of D housing to the outdoor of a reactor building.

FIG. 30 is a diagram showing an RPV, a reactor internal structure, and a CR to which the present invention is applied.
It is sectional drawing which shows the state which carries out the integrated body of D housing to the outdoor of a reactor building.

FIG. 31 is a diagram showing an RPV, a reactor internal structure, and a CR to which the present invention is applied.
It is sectional drawing which shows the state which carries out the integrated body of D housing to the outdoor of a reactor building.

FIG. 32 is a cross-sectional view showing a state in which the present invention is applied and a γ shield is carried out to the outside of the reactor building.

FIG. 33 is a cross-sectional view showing a state in which the present invention is applied and a γ shield is carried out to the outside of the reactor building.

FIG. 34 is a cross-sectional view showing a state in which the present invention is applied and the γ shield is carried out to the outside of the reactor building.

FIG. 35 is a cross-sectional view showing a state in which the present invention is applied and the γ shield is carried out to the outside of the reactor building.

FIG. 36 is a cross-sectional view showing a state in which the present invention is applied and the γ shield is carried out to the outside of the reactor building.

FIG. 37 is a cross-sectional view showing an example of a part of a side wall of a shield building for unloading a reactor pressure vessel and a movement of a ceiling part continuous to a part of the side wall.

[Explanation of symbols]

1 Reactor Pressure Vessel (RPV) 2 Internal Structure 3 Dryer 4 Separator 5 Core Shroud 6 Core Support Plate 7 Upper Lattice Plate 8 Shroud Support 9 Main Steam Nozzle 10 Water Supply Nozzle 11 Core Spray Nozzle 12 Recirculation Inlet Nozzle 13 Recirculation Outlet nozzle 14 Various instrumentation nozzles 15 Drain / vent nozzle 16 Reactor containment vessel (PCV) 17 Radiation shield (γ shield) 18 RPV pedestal 19 Bulkhead plate 20 Control rod drive (CRD) 21 Neutron flux detector (ICM) ) 22 beam 23 CRD housing 24 ICM housing 25 CRD housing support 27 Radial beam 28 Support 29 γ shield foundation bolt 30 PCV stabilizer 31 Reactor building 32 Reactor well 33 Spent fuel pool 34 Dora Yer Separator Pool (D / S Pool) 37 RPV Head 56 Spent Fuel Rack 57 Opening 58 Large Lifting Machine 59 Waste Storage Pit 60 Clean Room with Shielding Effect 61 Large Decontamination Equipment 63 Duct 64 Shield Plug 65 Restraint 66 , 66 'Metal heat insulating material 67 Piping 68 Temporary shielding plate 69 Opening 70 Supporting material 71 Steel rod

 ─────────────────────────────────────────────────── ─── Continuation of the front page (72) Inventor Taishi Yoshida 3-1-1, Saiwaicho, Hitachi-shi, Ibaraki Hitachi Ltd. Hitachi factory

Claims (6)

[Claims] 1. A carry-out method for carrying out a reactor pressure vessel of a nuclear reactor building in a nuclear power plant, a reactor internal structure, a radiation shield of the reactor pressure vessel, a CRD housing, etc. to the outside of the reactor building after a service period, The reactor pressure vessel with the reactor internal structure and the CRD housing attached is integrated with the radiation shield of the reactor pressure vessel and simultaneously carried out to the outside of the reactor building using a large lifting machine. A method for carrying out the reactor pressure vessel and the internal structure of the reactor during replacement. 2. A carrying-out method for carrying out a reactor pressure vessel, a reactor internal structure, a radiation shield of the reactor pressure vessel, a CRD housing and the like of a nuclear reactor building in a nuclear power plant to the outside of the reactor building after a service period, With the reactor pressure vessel, the reactor internals, and the CRD housing integrated,
Moreover, when the radiation shield of the reactor pressure vessel is integrated, it is separately carried out to the outside of the reactor building by using a large-sized lifting machine, when the reactor pressure vessel and the reactor internal structure are replaced. Unloading method. 3. In a nuclear reactor building which is equipped with a nuclear reactor pressure vessel and a radiation shield for the nuclear reactor pressure vessel and forms a part of a nuclear power plant, it is removable on the ceiling of the nuclear reactor building above the nuclear reactor pressure vessel. A nuclear reactor building of a nuclear power plant, characterized in that an opening provided with various closing means is provided, and an inner diameter of the opening is made larger than an outer diameter of a radiation shield of the reactor pressure vessel. 4. The reactor building for a nuclear power plant according to claim 3, wherein a shield building for carrying out a reactor pressure vessel is provided which is adjacent to the reactor building and extends to an upper portion of the reactor building to cover the opening. The space between the ceiling lower surface of the reactor pressure vessel carry-out shield building above the reactor building and the upper surface of the reactor building is larger than the height of the reactor pressure vessel, and the reactor building side wall and the reactor The distance between the side walls of the shield building for unloading the pressure vessel is larger than the outer diameter of the radiation shield of the reactor pressure vessel,
Reactor building of a nuclear power plant characterized by. 5. The reactor building for a nuclear power plant according to claim 4, wherein a part of an upper portion of a side wall of the shield building for carrying out the reactor pressure vessel and a part of a ceiling portion continuous with a part of the side wall are provided,
A nuclear reactor building of a nuclear power plant, which can be opened and closed in stages. 6. The reactor building of the nuclear power plant according to claim 4, wherein a part of an upper part of a side wall of the shield building for carrying out the reactor pressure vessel and a part of a ceiling part continuous with a part of the side wall,
A reactor building of a nuclear power plant, which is capable of moving in stages toward the inside of the shield building for carrying out the reactor pressure vessel.