JP3445907B2 - Construction method of reactor pressure vessel foundation and module used in the method - Google Patents

Description

Detailed Description of the Invention

[0001]

BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a technical field relating to the foundation of a reactor pressure vessel and its surroundings.

[0002]

2. Description of the Related Art An improved boiling water reactor (hereinafter referred to as A
In the construction of a BWR) plant, a cylindrical pedestal 1 on which a reactor pressure vessel (hereinafter referred to as RPV) is installed is divided into blocks of about 5 stages in the vertical direction and each block is loaded and set. In addition, the equipment, pipes, support structures, etc. arranged in the pedestal 1 were loaded and set individually for each item before the RPV 4 was suspended after the pedestal construction was completed.

After that, the RPV 4 is mounted on the pedestal that is completed by stacking all the stages at the installation position and is fixed by the anchor bolts.

In the pedestal 1 having a plurality of stages, since the joining portions of the upper stage and the lower stage are welded at the construction site, the deformation of each stage is accumulated and the means for absorbing it is taken.

[0005]

Since the pedestal is welded and installed at the site where the upper and lower tiers are joined together, the pedestal undergoes dimensional changes in the vertical direction due to welding distortion and the like. For this reason, when mounting the RPV on the pedestal and fixing it with the anchor bolts, a sole plate and a shim are called on the support skirt of the RPV and the mounting surface (RPV receiving surface) so as to compensate for the dimensional change. The installation height level of the RPV was adjusted by interposing a plate.

Such adjustment work is performed at the installation site, complicating the work at the site.

In the construction of RPV pedestal, RP
Since the V pedestal is carried in divided into several stages of blocks, it took a lot of days and labor to weld each block and to fill the inside of the cylinder with concrete.

A large number of equipment, pipes, support structures, etc. are provided inside the pedestal cylinder, but these are carried in individually after completion of the pedestal construction, so many days and labor are required for setting them. Was needed.

Further, the construction of the equipment, pipes, support structures, etc. arranged inside the pedestal 1 and the diaphragm floor 5 of the RPV 4 and the pedestal cylindrical portion of the RPV 4 of FIG.
It had to be completed before the RPV4 was suspended and was a critical path in the construction process. Furthermore, since it was forced to work in high places in a narrow space within the reactor building 2, it was not the optimum construction method in terms of work safety and work efficiency.

Therefore, it is desired to improve the construction method such as making each product and member into a large block in order to shorten the process of the construction work of the main body and the inside of the RPV pedestal of the nuclear power plant and to improve the work efficiency and safety. It had been.

It is an object of the present invention to shorten the nuclear plant construction process involving the installation of a reactor pressure vessel foundation.

[0012]

[0013]

[0014]

[0015]

[0016]

[0017]

[Means for Solving the Problems] To achieve the above object
In the module to be loaded into the installation position when constructing the reactor containment vessel , the first means is to install at least each stage of the reactor pressure vessel foundation in a plurality of vertical directions from the lower stage of each stage to the reactor pressure vessel. It is assembled in the upward direction up to the stage of the reactor pressure vessel foundation equipped with a stand for receiving
A receiving surface on a cradle for receiving the reactor pressure vessel is a module used in a method for constructing a reactor pressure vessel foundation characterized by being machined to a height for receiving the reactor pressure vessel. When used in construction work, at the module assembly manufacturing stage, even if the vertical dimensional distortion caused at the assembly manufacturing stage affects the height of the receiving surface of the reactor pressure vessel, the effect is machined. The height adjustment work at the construction site can be omitted, and the process of the nuclear power plant can be shortened.

A second means is the same as the first means , wherein a cylindrical reactor pressure vessel base provided with an inner cylinder steel plate and an outer cylinder steel plate and an atomic space arranged in an inner space inside the inner cylinder steel plate. A module for use in a method of constructing a reactor pressure vessel foundation, which comprises equipment, piping, and support structures attached to the reactor pressure vessel foundation, and in addition to the function and effect of the first means , the installation position of the reactor pressure vessel foundation. By loading the module into the reactor pressure vessel foundation as well as equipment installed in the tubular inner space of the reactor pressure vessel foundation,
Even compared to installing the reactor pressure vessel on the foundation of the reactor pressure vessel after waiting for the equipment, the piping, and the support structure to be brought in separately, the piping and the support structure can be brought in at the same time all at once. The work of installing the pressure vessel on the reactor pressure vessel foundation can be performed ahead of time, and the process of the nuclear power plant can be further shortened.

According to the third means, in the first means or the second means , the reactor pressure vessel foundation comprises an inner cylinder steel plate and an outer cylinder steel plate, and a space between the inner cylinder steel plate and the outer cylinder steel plate. a module incorporated in the construction method of the reactor pressure vessel foundation characterized in that the are the vent pipe is incorporated in the space, first means or the second
In addition to the effect of the two means , the vent pipe is included in the module members, so that the vent pipe can be installed at the same time as the reactor pressure vessel foundation is installed, and the process of the nuclear power plant can be further shortened. You can

The fourth means is the first means, the second means or the
In the three means , the reactor pressure vessel base includes an inner cylinder steel plate and an outer cylinder steel plate, and a mount for receiving the reactor pressure container is provided in an inner space inside the inner cylinder steel plate. A module for use in a method for constructing a foundation for a reactor pressure vessel, characterized by being equipped with anchor bolts for fixing the reactor pressure vessel, the first means or the second means.
In addition to the function and effect of the means or the third means , since the module member includes a mount for receiving the reactor pressure vessel and an anchor bolt for fixing the reactor pressure vessel, at the same time as installing the reactor pressure vessel foundation. The gantry and the anchor bolt can be installed, and the process of the nuclear power plant can be further shortened.

The fifth means is any one unit from the first means to the fourth means, the reactor pressure vessel foundation and a inner cylinder steel plate and the outer cylinder steel plate, and the outer tube steel the inner tube steel A module used in a method of constructing a reactor pressure vessel foundation, characterized in that concrete is placed in a space between the two, in addition to the effect of any one of the first to fourth means , Since it is possible to significantly reduce the work of placing concrete on the foundation of the reactor pressure vessel at the construction site, it is possible to suppress an increase in the work process at the site and further shorten the process of the nuclear power plant.

A sixth means is any one of the first to fifth means , characterized in that the reactor pressure vessel foundation is integrated over all stages from the lower stage to the upper stage. A module used in a method for constructing a container foundation, and in addition to the effect of any one of the first means to the fifth means, when the module is carried into the installation position, the entire reactor pressure vessel foundation can be installed at a stretch. The work of aligning each stage of the pedestal can be omitted at the installation site, and due to the synergistic effect of these, the work of installing the reactor pressure vessel on the reactor pressure vessel foundation can be advanced, and the process of the nuclear power plant can be shortened.

[0023]

The seventh means assembles the module by any one of the first means to the sixth means at a factory or a construction site, and thereafter, the assembled module is lifted to the installation position of the module. It is a method of constructing a reactor pressure vessel foundation that is set by suspending by using a hoist to hang the module assembled at the factory or construction site at the reactor pressure vessel foundation installation position with a lifting machine. Since the height of the surface that receives the reactor pressure vessel was correctly adjusted at the module creation stage, adjustment work at the construction site was omitted, and each stage of the reactor pressure vessel foundation was assembled at the installation position. Compared to installing the reactor pressure vessel on the reactor pressure vessel foundation, the construction work to install the reactor pressure vessel on the reactor pressure vessel foundation is advanced. To be performed, it is possible to reduce the nuclear plant process.

In the eighth means, in the seventh means , the receiving surface on the cradle for receiving the reactor pressure vessel is assembled so as to be higher than the regular height for receiving the reactor pressure vessel, and thereafter, the regular height is set. a construction method of a nuclear reactor pressure vessel foundation characterized by assembling the modules by cutting the receiving surface so as to is, in addition to the effects according to the seventh means, in the assembly stage of the module, resulting Even if the strain acts to lower the receiving surface of the reactor pressure vessel, the receiving surface is set to be higher in advance, so the receiving surface does not fall below the normal height and the cutting allowance is After obtaining the effect of distortion during production, the receiving surface can be cut and adjusted to a regular height.

[0026]

1 is a sectional view of a reactor building of an ABWR plant constructed by applying the present invention.

That is, a reactor containment vessel (RCCV) 3 made of reinforced concrete is provided at the center of the reactor building 2.

The structure is a cylindrical structure, and the pedestal 1 of the RPV 4 on which the RPV 4 is mounted is provided in the central portion.

The pedestal 1 of the RPV 4 of this embodiment is R
In order to support the load of PV4 and withstand vibration sufficiently, the inner and outer sides are made of cylindrical steel plates that also serve as the formwork for concrete pouring, and both spaces have a structure filled with high-strength concrete. And the RPV4 of this embodiment.
The equipment, piping, and support structure modules that are integrated with the pedestal 1 are installed in the middle of the pedestal 1.

Next, a large module used for constructing the pedestal 1 of the RPV 4 in the reactor building 2 will be described.

FIG. 2 shows a bird's-eye view of a pedestal 1 of the RPV 4 which is conventionally divided into five stages and assembled in the vertical direction, and the pedestal in which the five stages are integrated in a yard at the construction site.

That is, the pedestal 1 of the RPV 4 has a concentric double cylindrical structure of an outer cylinder steel plate 11 and an inner cylinder steel plate 12, and a pedestal 1 on which the RPV 4 is mounted in the middle upper part of the cylinder.
3 is integrated, and an anchor bolt 14 for fixing the RPV 4 to the frame 13 is set on the frame 13.

Further, between the outer cylinder steel plate 11 and the inner cylinder steel plate 12, a reinforcing rib 15 and a vent pipe 17 for connecting the both are assembled and attached, and a concrete 32 having high strength is filled. ing.

The vent pipe 17 communicates with a communication hole 33 that opens at the upper end of the pedestal 1. Fig. 3 shows the equipment, pipes, installed in the middle of the inside of the pedestal 1 of the RPV4.
It is a bird's-eye view of the module of the support structure,
In reality, they are the control rod drive housing at the bottom of the RPV4 and the internal pump interface. That is, the equipment, piping, and support structure of the pedestal cylindrical inner space of the RPV 4 are the main beam 21 for the upper floor, the main beam 22 for the lower floor, the vertical beam 23, the steel beam structural support member of the beam 24,
It is composed of a heat exchanger 28 of an internal pump, a control rod drive pipe 29, and an instrumentation pipe 30, and these are integrated into a module in a factory or on-site ground yard.

FIG. 4 is a bird's-eye view of a large module in which the integrated equipment, piping, support structure and service platform 31 inside the pedestal are integrated with the integrated RPV pedestal body.

The module in the pedestal has the reinforcement beams 25 attached to the inner wall of the pedestal and the main beams 21, 2.
2 is directly welded and integrated with the pedestal body.

FIG. 5 shows a state in which the large module of this embodiment is carried into the reactor building 2 by using the large hoist 18.

FIG. 6 shows a construction process sequence of the construction method of the present embodiment and the conventional construction method in the construction of the reactor building.

As can be seen from this process sequence,
By assembling all stages of the pedestal 1 of RPV4 into one module, and then setting the module by suspending it at the installation position of the module with a lifting machine, the diaphragm construction and the reactor containment vessel (RCCV) construction are advanced. The construction process of the pedestal 1 of RPV4 which has advanced the installation time of RPV4 is adopted, and if the module is suspended and set at the installation position, the RPV4 will be installed at once.
Pedestal 1 is installed, the construction of the diaphragm and the reactor containment that follows can be done ahead of schedule, and the pedestal 1 of RPV4 is piled up according to each stage at the time of installation. Since the mounting surface of the RPV 4 is adjusted to a regular height by cutting the upper surface of the gantry 13 so that the deformation dimension due to the distortion when the module is manufactured by welding is cut,
Attach RPV4 to pedestal 1 of RPV4 (RPVO
N) The height adjustment at the time can be significantly reduced, and the synergistic effect of them can shorten the construction process of the nuclear power plant.

R on pedestal 1 of RPV4 at construction site
In order to eliminate or reduce the height adjustment when assembling the PV4 (RPVON), when the pedestal part of each stage is assembled from the lower stage to the upper stage in the factory or the local yard, the pedestal 13 is previously prepared. The upper surface of the device is arranged or thickened in the vertical direction so that the height of the upper surface of the device becomes higher than the normal height for receiving the RPV. The pedestal 13 lowers due to the distortion when welding the joints of each pedestal at the time of assembling each pedestal. It is left. After the steps of the pedestal equipped with the pedestal 13 are assembled, the adjustment allowance is cut and machined to adjust the height to a regular level. In this way, the modularized pedestal is
The surface that receives the PV is adjusted to a regular height, and the height adjustment work at the installation site is omitted or reduced.

[0041]

[0042]

[0043]

[0044]

[0045]

[0046]

[0047]

Effect of the Invention According to the invention of claim 1, the use of the module according to the invention in construction work, module assembling at the manufacturing stage, receiving the vertical dimension distortion reactor pressure vessel resulted from that assembly manufacturing stage Even if it affects the height of the surface,
Since the height is adjusted by processing the receiving surface of the influence, the height adjustment work at the construction site can be omitted, and the process of the nuclear power plant can be shortened.

According to the invention of claim 2 , in addition to the effect of the invention of claim 1 , by loading the module into the installation position of the reactor pressure vessel foundation, not only the reactor pressure vessel foundation but also the reactor Equipment, pipes, and even supporting structures that are equipped in the inner space inside the inner cylinder steel plate of the pressure vessel foundation can be carried in at once and at the same time. Wait until the equipment, piping, and supporting structures are separated and carried in. Installation of the reactor pressure vessel on the base of the reactor pressure vessel can be carried out earlier than installation of the reactor pressure vessel on the foundation of the reactor pressure vessel, and the process of the nuclear power plant can be further shortened.

According to the invention of claim 3 , claim 1 or the contract
In addition to the effect of the invention of claim 2 , since the module configuration member includes the vent pipe, the effect of simultaneously installing the reactor pressure vessel foundation and simultaneously installing the vent pipe can be obtained, further shortening the nuclear plant process. can do.

According to the invention of claim 4 , claim 1 or the contract
In addition to the effects according to the invention of claim 2 or claim 3 , since the module members include a cradle for receiving the reactor pressure vessel and an anchor bolt for fixing the reactor pressure vessel, the reactor pressure vessel foundation is The effect that the pedestal and anchor bolts can be installed at the same time as installation is achieved, and the process of the nuclear power plant can be further shortened.

According to the invention of claim 5, the contract from claim 1 is applied.
In addition to the effect of the invention according to any one of claim 4
Since it is possible to significantly reduce the work of placing concrete on the foundation of the reactor pressure vessel at the construction site, it is possible to suppress an increase in the work process at the site and further shorten the process of the nuclear power plant.

According to the invention of claim 6, the contract from claim 1 is applied.
In addition to the effect of the invention according to any one of claim 5
When the module is loaded into the installation position, the entire reactor pressure vessel foundation can be installed at once, and the work of aligning each stage of the pedestal can be omitted at the installation site, and the synergistic effect of these will install the reactor pressure vessel to the reactor pressure vessel foundation. The construction can be advanced and the nuclear plant process can be shortened.

[0053]

According to the invention of claim 7 , when the module assembled at the factory or construction site is hung by a lifting machine at the installation position of the reactor pressure vessel base to install the reactor pressure vessel foundation, the module is produced. Since the height of the surface that receives the reactor pressure vessel is adjusted correctly at each stage, the adjustment work at the construction site is omitted, and each stage of the reactor pressure vessel foundation is assembled at the installation position and the reactor pressure vessel is assembled. Compared with the installation on the reactor pressure vessel base, the installation of the reactor pressure vessel on the reactor pressure vessel base can be performed earlier, and the process of the nuclear power plant can be shortened.

According to the invention of claim 8 , in addition to the effect of the invention of claim 7 , even if the strain generated at the stage of producing the module acts to lower the receiving surface of the reactor pressure vessel, Since the receiving surface is set to be higher, the receiving surface will not be lower than the normal height, the cutting allowance will be obtained, and the receiving surface will be affected after the influence of distortion at the time of production at the production stage. It can be cut and adjusted to a regular height.

[0056]

[Brief description of drawings]

FIG. 1 is a vertical sectional view of a pedestal of RCCV and RPV in a reactor building.

FIG. 2 is a bird's-eye view with a partial cross-sectional view of the module of the pedestal of the RPV of FIG.

3 is a bird's-eye view showing the second stage from the bottom of the pedestal of the RPV of the module of FIG. 2 in a section.

4 is a bird's-eye view showing a part of the lowermost stage of the pedestal of the RPV of the module of FIG. 2 to the uppermost stage in a sectional view.

5 is a cross-sectional view showing a state in which the module of FIG. 2 is loaded into a predetermined position of a reactor building by a lifting machine.

FIG. 6 is a diagram comparing and displaying a construction process sequence of an embodiment of the present invention involving the construction of an RPV pedestal and a conventional method.

[Explanation of symbols]

1 ... RPV pedestal, 2 ... reactor building, 3 ... reactor containment vessel (RCCV), 4 ... reactor pressure vessel (RPV),
5 ... Diaphragm floor, 11 ... RPV pedestal outer cylinder steel plate, 12 ... RPV pedestal inner cylinder steel plate, 13 ... Frame,
14 ... RPV anchor bolts, 15 ... RPV pedestal ribs, 17 ... vent pipes, 18 ... large hoist, 19 ... wires, 21 ... upper floor main beams, 22 ... lower floor main beams, 23 ... vertical beams, 24 ... beam, 26 ... upper floor support plate, 27 ... lower floor support plate, 28 ... heat exchanger, 29
... control rod drive pipe, 30 ... instrumentation pipe, 31 ... service platform, 32 ... concrete, 33 ... communication hole.

─────────────────────────────────────────────────── ─── Continuation of the front page (72) Inventor Tadaaki Oikawa 3-1-1, Saiwaicho, Hitachi, Ibaraki Hitachi Ltd. Hitachi factory (72) Inventor Koichi Gota 3-1-1, Saiwaicho, Hitachi, Ibaraki Hitachi Ltd. (72) Inventor Masamichi Chinen 3-2-2, 3-Sachimachi, Hitachi-shi, Ibaraki Hitachi Nuclear Engineering Co., Ltd. (72) Toshimi Komaru, Mizo-cho, Hitachi-shi, Ibaraki 1-chome 1-1 Hitachi Ltd. inside Hitachi factory (72) Inventor Yoichi Nemoto 3-2-2 3-chome, Saiwaicho, Hitachi-shi, Ibaraki Hitachi Nuclear Engineering Co., Ltd. (72) Inventor Tatsuo Makita Chiyoda-ku, Tokyo 1-114 Kanda Hitachi Plant Construction Co., Ltd. (72) Inventor Sumito Maezawa Uchigami, Chiyoda-ku, Tokyo 1-14 No. 1 in Hitachi Plant Construction Co., Ltd. (56) Reference JP-A-4-52595 (JP, A) JP-A-6-294888 (JP, A) JP-A-3-279895 (JP, A) JP-A-7-49395 (JP, A) JP-A-61-26890 (JP, A) JP-A-54-6308 (JP, A) JP-A-61-122596 (JP, A) (58) Fields investigated (Int.Cl. ⁷ , DB name) G21C 13/00

Claims (8)

(57) [Claims] 1. In a module to be loaded into an installation position when constructing a reactor containment vessel, at least each stage of the reactor pressure vessel foundation having a plurality of vertical stages is provided with a reactor pressure vessel from a lower stage of each stage. The reactor pressure vessel is equipped with a receiving base and is installed upward to the stage of the foundation, and the receiving surface on the receiving base for receiving the reactor pressure vessel is machined to a height for receiving the reactor pressure vessel. A module used in a method for constructing a foundation for a reactor pressure vessel, which is characterized in that 2. A according to claim 1, the inner cylinder steel plate and the outer cylinder and the cylindrical reactor pressure vessel foundation provided with a steel plate, the reactor pressure vessel is arranged inside the space on the inner side than the inner tube steel A module used in the method of constructing a reactor pressure vessel foundation consisting of equipment, piping, and support structures attached to the foundation. 3. The method of claim 1 or claim 2, wherein the reactor pressure vessel foundation and a inner cylinder steel plate and the outer tube steel, the vent tube is incorporated in a space between the inner cylinder steel plate and the outer cylinder steel A module used in a method for constructing a reactor pressure vessel foundation, which is characterized by 4. The method of claim 1 or claim 2 or claim 3, wherein the reactor pressure vessel foundation and a inner cylinder steel plate and the outer tube steel reactor the inner space in the inner side than the inner tube steel A module used in a method for constructing a foundation for a reactor pressure vessel, characterized in that it is equipped with a mount for receiving a pressure container, and the mount is equipped with anchor bolts for fixing the reactor pressure container. 5. A any one of claims 1 to 4, wherein the reactor pressure vessel foundation and a inner cylinder steel plate and the outer cylinder steel plate, between the inner cylinder steel plate and the outer cylinder steel A module used in the construction method of a reactor pressure vessel foundation, characterized in that the space is filled with concrete. 6. A any one of claims 1 to 5, reactor pressure vessel foundation characterized in that the reactor pressure vessel basis from the lower are integrated over all stages up to the uppermost Module used in the construction method of. 7. assembled module according to any one of claims 1 to 6 at the factory or construction site,
After that, a method for constructing a foundation for a reactor pressure vessel, in which the assembled module is suspended and set by a hoist at the installation position of the module. 8. The structure according to claim 7 , wherein the receiving surface on the cradle for receiving the reactor pressure vessel is assembled so as to be higher than a regular height for receiving the reactor pressure vessel, and then the regular height is obtained. A method of constructing a foundation for a reactor pressure vessel, which comprises assembling a module by cutting the receiving surface as described above.