JPH1039077A - Method for carrying in and carrying out reactor pressure vessel - Google Patents

Abstract

PROBLEM TO BE SOLVED: To replace a reactor pressure vessel in a short time without having any adverse effect on the facility by carrying out a reactor pressure vessel having expired serve life integrally with the upper part of reactor shield wall from the inside of a reactor container. SOLUTION: Upper and lower nozzles 11, 12 and a CRD housing 10 fixed to a reactor pressure vessel 4 are separated from external machines while closing the openings with closing plates 21, 22,... and a reactor shield wall 6 is cut off at the lower side of a lower nozzle opening 8. A lower air tank 26 is then inserted into the core area 20 of a pressure vessel body 13 and secured to a shroud 17. Subsequently, an upper air tank 24 is inserted into an upper space 25 and secured to the pressure vessel body 13. A shielding space is kept by the water in all direction for each air tank 26, 24. A cover body 15 is then fixed to the pressure vessel body 13 and shielding water 28 is injected through a nozzle 14. After filled with the shielding water, the pressure vessel body 13 is carried out integrally with the upper part of the reactor shield wall 6 through a suspension member using a crane or the like.

Description

DETAILED DESCRIPTION OF THE INVENTION

[0001]

BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a method for carrying out and carrying out a reactor pressure vessel. More specifically, the present invention relates to a method of unloading and loading a reactor pressure vessel that can replace a reactor pressure vessel without affecting a facility in a short time.

[0002]

2. Description of the Related Art Nuclear power generation facilities are designed with their service lives determined in advance, and after a predetermined service life, the facilities are destroyed.

However, since a nuclear power generation facility actually has a sufficient margin for a determined service life, the life of the nuclear power generation facility is extended by replacing only parts whose life has expired. It is possible.

For this reason, it is necessary to establish a technology for replacing a component whose life has expired. In this case, a typical example of the component to be replaced is a reactor pressure vessel.

[0005] However, at present, there is no actual example of replacing the reactor pressure vessel, and no replacement technology has been established.

[0006]

When an expired reactor pressure vessel is carried out of a nuclear power generation facility, how to shield the activated reactor pressure vessel and how quickly the reactor pressure vessel is not affected. It is important to carry it out.

[0007] When a new reactor pressure vessel is carried in, it is important how to carry it into the facility in a short time without affecting the existing part of the facility.

The present invention has been made in view of the above circumstances, and has as its object to provide a method for unloading and loading a reactor pressure vessel which can replace a reactor pressure vessel in a short time without affecting a facility. It is assumed that.

[0009]

The present invention is characterized in that the reactor pressure vessel 4 whose life has expired and the upper part of the reactor shield wall 6 are integrally carried out of the reactor containment vessel 1. The method according to the present invention relates to a method for unloading a reactor pressure vessel.

In this case, the inside of the reactor pressure vessel 4 to be carried out may be filled with shielding water 28.

Further, inside the reactor pressure vessel 4 to be carried out,
After inserting the water injection amount reducing member, the shielding water 28 may be filled.

The member for reducing the amount of injected water is the air tank 2
4, 26 may be used.

Further, the member for reducing the amount of injected water is made of the foamed resin 30,3.
It may be 1.

Further, according to the present invention, a new reactor pressure vessel 34 and a new reactor pressure shield 34 are provided for the reactor containment vessel 1 from which the reactor pressure vessel 4 and the upper part of the reactor shield wall 6 whose life has expired have been removed. The present invention relates to a method for carrying in a reactor pressure vessel, wherein the upper part of the wall is integrally carried in.

In this case, the lower part 36 of the reactor shield wall remaining in the reactor containment vessel 1 is cut at the lower side position a of the lower nozzle opening 8 and the upper part 35 of the reactor shield wall 35 to be carried in.
Is formed up to the upper side position B of the lower nozzle opening 8, and the upper part 35 of the reactor shield wall is temporarily received on the lower part 36 of the reactor shield wall via the temporary receiving material 37, and both are aligned. The connection wall 38 may be attached between the upper part 35 of the reactor shield wall and the lower part 36 of the reactor shield wall to form the lower nozzle opening 8.

According to the above means, the following effects can be obtained.

When the reactor pressure vessel 4 is taken out of the reactor containment vessel 1, the reactor shield wall 6 is cut at the lower side position A of the lower nozzle opening 8.

Then, a water injection amount reducing member such as the air tanks 24 and 26 and the foamed resins 30 and 31 is inserted and arranged inside the pressure vessel body 13.

When the air tanks 24, 26 and the like are set in this way, the shielding water 28 is injected into the pressure vessel main body 13 to fill the pressure vessel main body 13 with water.

When the preparation is completed, the pressure vessel body 13 is pulled up using a crane or the like, and the reactor shield wall 6 is lifted.
Out of the pressure vessel body 13 together with the upper part of the pressure vessel.

As described above, according to the present embodiment, since the shielding water 28 is injected into the pressure vessel main body 13 and is shielded by the shielding water 28, the shielding can be performed simply and reliably. Can be.

The air tank 2 is provided inside the pressure vessel body 13.
Since the shielding water 28 is injected in a state in which 4, 26 and the like are inserted, the shielding water 28 can be shielded with the minimum shielding water 28, and the lifting weight can be reduced.

Further, since the pressure vessel main body 13 is taken out to the outside together with the upper part of the reactor shield wall 6, the steps can be omitted.

As described above, it is possible to replace the reactor pressure vessel 4 within a short time without affecting the facility.

In particular, the foamed resin 3
The use of the air tanks 24, 26
As a result, the lifting weight at the time of unloading can be greatly reduced, and the labor of installing the water injection amount reducing member and the labor of the unloading operation can be reduced.

When exhausting the expired reactor pressure vessel 4 along with the upper part of the reactor shield wall 6, the upper part 35 of the reactor shield wall is integrally attached to a new reactor pressure vessel 34 in advance. After the reactor pressure vessel 4 and the like whose life has expired are transported out by a crane or the like, a new reactor pressure vessel 34 prepared is transferred to the upper part of the reactor shield wall 35.
The lower part 36 of the reactor shield wall that is carried in integrally with the crane (not shown) and the upper part 35 of the reactor shield wall that are carried in are joined together to form the reactor shield wall 6.

At this time, a problem arises between the upper part 35 of the reactor shield wall to be carried in integrally with the new reactor pressure vessel 34 and the lower part 36 of the remaining reactor shield wall. The upper shielding wall 35 is located above the upper side position of the lower nozzle opening 8 shown by the broken line B, and a temporary receiving material 37 is installed between the lower shielding wall 36 and the remaining reactor shielding wall lower part 36. After the shielding wall lower part 36 and the reactor shielding wall upper part 35 are aligned, a connecting wall part 38 between the lower nozzles 12 is formed on site and connected.

The temporary receiving member 37 is set on both sides of the lower nozzle 12 at a position corresponding to the lower nozzle opening 8.

As described above, by carrying in a new reactor pressure vessel 34 and the upper part of the reactor shield wall 35 integrally, it becomes possible to carry out the work in a short time by omitting the steps. .

Further, the lower part 36 of the reactor shield wall remaining in the reactor containment vessel 1 is cut at the lower side position a of the lower nozzle opening 8, and the upper part 35 of the reactor shield wall to be carried in is cut off by the lower nozzle opening 8. It is formed up to the upper side position b, and the lower part of the reactor shield wall 36
The upper portion of the reactor shield wall 35 is temporarily received via the temporary receiving material 37 and the two are aligned, and then the connection wall between the upper portion 35 of the reactor shield wall and the lower portion 36 of the reactor shield wall at the site. Part 3
By attaching 8, it is possible to solve the problem of the connection when the upper part of the reactor shield wall 35 and the lower part 36 of the remaining reactor shield wall are joined on site.

[0031]

Embodiments of the present invention will be described below with reference to the drawings.

FIGS. 1 to 4 show a first embodiment of the present invention.

In the drawing, 1 is a reactor containment vessel, 2 is a building part on the upper part of the reactor containment vessel 1, 3 is a dry well part on a lower part of the reactor containment vessel 1, and 4 is a part contained in the reactor containment vessel 1. The reactor pressure vessel 5 was provided in the dry well section 3,
A pedestal for supporting the lower part of the reactor pressure vessel 4,
Reference numeral 6 denotes a reactor shield wall supported at its lower part by the pedestal 5 and provided to surround the outer periphery of the reactor pressure vessel 4. Reference numeral 8 denotes a lower nozzle opening formed at a plurality of locations in the circumferential direction below the reactor shielding wall 6, and 9 denotes a port for connecting the upper part of the reactor pressure vessel 4 to the reactor containment vessel 1 via bellows (not shown). This is the bulkhead section.

The reactor pressure vessel 4 has a CRD housing 10 at a lower portion for inserting and removing fuel rods, and an upper nozzle at a side corresponding to the upper nozzle opening 7 and the lower nozzle opening 8, respectively. 11 and lower nozzle 12
, A lid 15 having a plurality of nozzles 14, and a stat bolt 16 for fastening the pressure vessel main body 13 and the lid 15.

A cylindrical body called a shroud 17 is attached to a lower part in the pressure vessel body 13, and an upper lattice plate 18 attached to an upper part of the shroud 17 and a core support plate attached to an intermediate part. A core region 20 is formed between the core region 19 and the core region 20.

In the drawings, reference numerals 21 and 22 denote opening closing plates for closing the upper nozzle opening 7 and the lower nozzle opening 8, respectively. Reference numeral 23 fixes the pressure vessel main body 13 and the upper part of the reactor shielding wall 6. 2, 24 is an upper air tank (water injection amount reducing member) inserted into an upper space 25 of the pressure vessel body 13, and 26 is a lower air tank (note) inserted into a core region 20 of the pressure vessel body 13. (A water amount reducing member), 27 is the pressure vessel body 13, the shroud 17, and the upper air tank 2
And a position adjustment support member such as a turnbuckle type interposed between the pressure vessel main body 4 and the lower air tank 26;
3. Shielding water injected into the inside of 3; 29 in FIG.
Pressure vessel body 1 with a crane (not shown)
3 is a suspending member for lifting.

Next, the operation will be described.

When the reactor pressure vessel 4 is taken out of the reactor containment vessel 1, the upper nozzle 11, the lower nozzle 12 and the CRD housing 10 attached to the reactor pressure vessel 4 are removed.
And cut off the edge with the external equipment, and close the upper nozzle 11, the lower nozzle 12, and the opening of the CRD housing 10,
The upper nozzle opening 7 and the lower nozzle opening 8 are closed by opening closing plates 21 and 22, respectively, and the reactor shield wall 6 is cut at the lower side of the lower nozzle opening 8 as shown by a broken line a in FIG. I do.

In parallel with the above operation, the reactor pressure vessel 4
Then, the cap body 15 is opened by removing the stat bolt 16, the inside of the pressure vessel body 13 is disassembled, and parts other than the parts to be removed simultaneously with the reactor pressure vessel 4 are removed.

When the above operation is completed, the pressure vessel body 13
The lower air tank 26 is inserted and arranged in the core region 20 of the first embodiment, and a position adjusting support member 27 is interposed between the lower air tank 26 and the shroud 17 so that the lower air tank 26 is
7 and the position adjustment support member 27 is adjusted so that the distance between them is equal to or greater than the minimum distance required for shielding by water in all directions.

Similarly, the upper space 25 of the pressure vessel body 13
The upper air tank 24 is inserted and arranged in the upper air tank 2.
A position adjusting support member 27 is interposed between the pressure vessel main body 4 and the pressure vessel main body 13 to fix the upper air tank 24 to the pressure vessel main body 13, and the position adjusting support member 27 is adjusted so that the distance between the two is completely reduced. The direction is maintained such that the distance is equal to or longer than the minimum distance required for shielding by water.

When the lower air tank 26 and the upper air tank 24 are set in this manner, the pressure vessel main body 1 is again set.
3, the cover 15 is further attached, a suspension member 29 is attached to the cover 15, and the shielding water 28 is injected into the pressure vessel body 13 from the nozzle 14 formed on the cover 15.
The inside of the pressure vessel body 13 is filled with water.

When the preparation is completed, as shown in FIG. 4, the pressure vessel main body 13 is pulled up via the hanging member 29 using a crane or the like (not shown), and the pressure vessel main body 13 together with the upper part of the reactor shield wall 6 is removed. Take it out.

As described above, according to the present embodiment, the shielding water 28 is injected into the pressure vessel main body 13 and is shielded by the shielding water 28, so that the shielding can be performed simply and reliably. Can be.

Further, since the shielding water 28 is injected in a state where the lower air tank 26 and the upper air tank 24 are inserted into the pressure vessel main body 13, the shielding water 28 can be shielded with the minimum shielding water 28. Thus, the lifting weight can be reduced.

Further, since the pressure vessel main body 13 is carried out to the outside together with the upper part of the reactor shield wall 6, the steps can be omitted.

As described above, it is possible to replace the reactor pressure vessel 4 within a short time without affecting the facility.

FIG. 5 shows a second embodiment of the present invention, in which foaming resins 30 and 31 such as urethane foam are used as the water injection amount reducing members instead of the upper air tank 24 and the lower air tank 26. The method according to the present invention relates to a method of unloading the reactor pressure vessel 4.

More specifically, the lid 15 is opened from the reactor pressure vessel 4, the inside of the pressure vessel body 13 is disassembled, and components other than the components to be removed simultaneously with the reactor pressure vessel 4 are removed. A plastic bag 32 swelled into a required shape is inserted and arranged in the core region 20 of the container body 13, and the undiluted solution of the foamed resin 31 and the foam material are injected into the plastic bag 32 to foam.

Similarly, the upper space 25 of the pressure vessel body 13
Plastic bag 3 that can be inflated to the required shape
3 is inserted and arranged, and the undiluted solution of the foamed resin 30 and the foamed material are injected into the plastic bag 33 to foam.

The foamed resins 30, 31 thus formed
The plastic bags 32 and 33 are attached to the shroud 17 and the pressure vessel body 13 by using the position adjustment support member 27 so that the distance between the shroud 17 and the pressure vessel main body 13 is equal to or longer than the minimum distance required for shielding with water in all directions. Hold the part.

As described above, by using the foamed resin 30 or 31 such as urethane foam as the water injection amount reducing member, the upper air tank 24 and the lower air tank 26 can be formed.
As a result, the lifting weight at the time of unloading can be greatly reduced, and the labor of installing the water injection amount reducing member and the labor of the unloading operation can be reduced.

The injection of the undiluted solution and the foam material into the plastic bags 32 and 33 may be performed with the lid 15 opened or through the nozzle 14 with the lid 15 closed.

Except for the above, the configuration is the same as that of the above embodiment, and the same operation and effect can be obtained.

FIG. 6 shows a third embodiment of the present invention, which relates to a method for loading a new reactor pressure vessel.

In the present embodiment, when discharging the expired reactor pressure vessel 4 together with the upper part of the reactor shield wall 6 to the outside, a new reactor pressure vessel 34 is first placed in the reactor shield wall upper part 35. The reactor pressure vessel 4 whose service life has expired is transported out by a crane or the like (not shown), and then a new reactor pressure vessel 3 is prepared.
4 is carried in integrally with the upper part of the reactor shield wall 35 by a crane or the like (not shown), and the lower part 36 of the reactor shield wall is left.
The upper part of the reactor shield wall 35 carried in is joined to form the reactor shield wall 6.

At this time, a problem arises between the upper part 35 of the reactor shield wall to be carried in integrally with the new reactor pressure vessel 34 and the lower part 36 of the remaining reactor shield wall. The shielding wall upper part 35 is higher than the upper side position of the lower nozzle opening 8 shown by a broken line B in FIG. 3, and a temporary receiving material 37 is installed between the upper part and the remaining reactor shielding wall lower part 36. After the reactor shield wall lower part 36 and the reactor shield wall upper part 35 are aligned, a connecting wall part 38 between the lower nozzles 12 is formed on site and connected.

The temporary receiving member 37 is set at the position corresponding to the lower nozzle opening 8 on both sides of the lower nozzle 12.

As described above, by carrying in the new reactor pressure vessel 34 and the upper part of the reactor shield wall 35 integrally, it is possible to carry out the work in a short time by omitting the steps. .

The lower part 36 of the reactor shield wall remaining in the reactor containment vessel 1 is cut at the lower side position a of the lower nozzle opening 8, and the upper part 35 of the reactor shield wall to be carried in is cut off by the lower nozzle opening 8. It is formed up to the upper side position b, and the lower part of the reactor shield wall 36
The upper portion of the reactor shield wall 35 is temporarily received via the temporary receiving material 37 and the two are aligned, and then the connection wall between the upper portion 35 of the reactor shield wall and the lower portion 36 of the reactor shield wall at the site. Part 3
By attaching 8, it is possible to solve the problem of the connection when the upper part of the reactor shield wall 35 and the lower part 36 of the remaining reactor shield wall are joined on site.

Except for the above, the configuration is the same as that of the above embodiment, and the same operation and effect can be obtained.

It should be noted that the present invention is not limited only to the above-described embodiment, and it goes without saying that various modifications can be made without departing from the spirit of the present invention.

[0063]

As described above, according to the method for unloading and loading a reactor pressure vessel of the present invention, the reactor pressure vessel can be replaced in a short time without affecting the facility. The effect can be obtained.

[Brief description of the drawings]

FIG. 1 is an overall schematic side sectional view of a first embodiment of the present invention.

FIG. 2 is an overall schematic side sectional view showing a state where an air tank is inserted and arranged inside a reactor pressure vessel.

FIG. 3 is a partial development view of a reactor shield wall.

FIG. 4 is an overall schematic side sectional view showing a state in which the reactor pressure vessel is carried out integrally with an upper portion of a reactor shielding wall.

FIG. 5 is an overall schematic side sectional view of a second embodiment of the present invention.

FIG. 6 is an overall schematic side sectional view of a third embodiment of the present invention.

[Explanation of symbols]

DESCRIPTION OF SYMBOLS 1 Reactor containment vessel 4 Reactor pressure vessel 6 Reactor shield wall 8 Lower nozzle opening 24, 26 Air tank (upper air tank, lower air tank, water injection amount reducing member) 28 Shielding water 30, 31 Foam resin (water injection amount) (Reducing member) 34 New reactor pressure vessel 35 Upper part of reactor shield wall 36 Lower part of reactor shield wall 37 Temporary receiving material 38 Connection wall part B Lower position B Upper position

Claims (7)

[Claims] An atomic reactor characterized in that an expired reactor pressure vessel (4) and an upper part of a reactor shield wall (6) are integrally carried out of a reactor containment vessel (1). Furnace pressure vessel unloading method. 2. The method for unloading a reactor pressure vessel according to claim 1, wherein the inside of the reactor pressure vessel to be unloaded is filled with shielding water. 3. A shielding water (2) having a water injection amount reducing member inserted and disposed inside a reactor pressure vessel (4) to be carried out.
The method according to claim 2, wherein the method (8) is filled. 4. An air tank (24), wherein the water injection amount reducing member is an air tank (24).
The method according to claim 3, wherein (26). 5. The foaming resin (30), wherein the water injection amount reducing member is
The method according to claim 3, wherein (31). 6. A new reactor pressure vessel (34) for the reactor containment vessel (1) from which the expired reactor pressure vessel (4) and the upper part of the reactor shield wall (6) have been removed. And a reactor shield upper part (35). 7. A reactor shield wall lower part (36) remaining in the reactor containment vessel (1) is cut at a lower side position (a) of the lower nozzle opening (8), and the reactor shield wall upper part to be carried in is cut. (3
5) is formed to the upper side position (b) of the lower nozzle opening (8), and the temporary receiving material (37) is placed on the lower part (36) of the reactor shield wall
The upper part of the reactor shield wall (35) is temporarily received via the, and both are aligned.
5) and the connecting wall (3) between the reactor shield wall lower part (36).
7. The method as claimed in claim 6, wherein the lower nozzle opening is formed by attaching the lower nozzle opening.