JPS62233790A - Nuclear-reactor pressure vessel pedestal - Google Patents

Abstract

(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.

Description

[Detailed description of the invention] [Industrial application field] The present invention relates to a nuclear reactor pressure vessel pedestal.

In particular, it concerns the reactor pressure vessel pedestal, which aims to shorten the manufacturing and installation process and improve construction safety.

[Conventional technology]

The conventional device has a steel frame structure as shown in Japanese Patent Publication No. 56-51598, but no consideration was given to the method of joining the members and the seismic design.

Furthermore, in JP-A No. 58-155386, the members are joined by bolts, but no consideration was given to earthquake-resistant design or improvement in structural strength.

[Problem that the invention seeks to solve]

FIG. 5 shows a conventional boiling water nuclear reactor, and in the figure, reference numeral 1 indicates a reactor containment vessel housed within the reactor building 2. In FIG. This reactor containment vessel 1 is divided into two parts, a wet well 4 and a dry well 5, and a reactor pressure vessel pedestal 7 whose upper portion is disposed within the dry well 5 is installed in the basic concrete maturo. A reactor pressure vessel 8 installed and supported on the reactor pressure vessel pedestal 7 is accommodated in the dry well, and this reactor pressure vessel 8 is equipped with a reactor shield installed on the reactor pressure vessel pedestal 7. It is surrounded by wall 9.

In a boiling water reactor configured in this way.

Since the reactor pressure vessel pedestal 7 supports important heavy objects such as the reactor pressure vessel 8, it has conventionally been made of reinforced concrete with a very large amount of steel movement, and has been installed entirely by on-site work.

Also, after the completion of reactor pressure vessel pedestal 7.

Since the installation of the reactor shield Ji9, the installation of the reactor pressure vessel 8, and the installation of structures, piping, etc. inside the reactor containment vessel 1 are performed, installation of the reactor pressure vessel pedestal 7 can shorten the process. This is an important point for shortening the power plant construction process. Therefore, in order to shorten the installation process of this reactor pressure vessel pedestal 7,
For example, the main structure of the reactor pressure vessel pedestal 7 is made of steel, eliminating the reinforcing steel assembly work that was conventionally done on-site, and the steel parts are produced separately at a factory and then assembled on-site by welding. things are being done.

However, this welding work is mainly performed in the closed air conditioner configured by the reactor pressure vessel pedestal 7, and therefore a considerable amount of time is spent on this welding work.

Additionally, this method has the problem of being undesirable in terms of safety management for workers.

The present invention has been made in response to such conventional circumstances, and aims to provide a reactor pressure vessel pedestal that can shorten the construction period and increase the safety of one worker. ·be.

[Means for solving problems]

The above objective is achieved by the following.

(1) By adopting a seismic isolation structure, horizontal seismic force is reduced and reinforcement becomes easier. As a result, the reinforcing plates can be joined using simple bolts. Therefore, the construction period can be shortened.

(2) Same as above, since bolt connection is possible and block formation is easy, worker safety is also improved.

[Effect]

In the reactor pressure vessel pedestal configured as described above, when the pedestal is in a geological formation, the horizontal load is converted into frictional energy by the upper and lower friction plates, and the seismic load on the pedestal body is reduced.

In addition, each cylindrical steel plate is brought in separately and easily assembled using joining materials (bolt joints), so the construction process can be shortened.

[Embodiments of the invention]

DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS The details of the present invention will be described below with reference to an embodiment shown in the drawings.

1 to 4 show a reactor pressure vessel pedestal according to an embodiment of the present invention. In FIG. 1, reference numeral 7 indicates the reactor pressure vessel pedestal. This reactor pressure vessel pedestal 7 is made of a cylindrical steel plate, is installed on a concrete foundation, and is made up of an inner cylinder 12 forming an inner wall and an outer cylinder 13 forming an outer wall. A reinforcing member 14 made of a flat plate is installed between the inner cylinder 12 and the outer cylinder 13 in order to reinforce the reactor pressure vessel pedestal 7. Upper and lower friction plates are installed at the contact point between the drywell bottom concrete and the pedestal.

That is, each cylindrical steel plate has an annular shape obtained by cutting vertically around the reactor pressure vessel pedestal 7 as an axis, and is composed of structural members divided in the upper direction and the radial direction. , it can be transported in parts as shown in Figure 4.

Moreover, each structural member is joined as shown in FIG.

The reinforcing plates 14 are located on the same vertical plane. As shown in Figure 3, the pedestal has a reinforcing plate 14. Through-holes are provided in the inner cylinder steel plate 12 and the outer cylinder steel plate 13, and each is joined by a joining member (joining bolt) 10.

In the reactor pressure vessel pedestal configured as described above, the reinforcing plate 14 is joined in a closed space surrounded by the inner cylinder 12 and the outer cylinder 13.

Since this work only requires inserting the bolt 10 into the through hole and tightening it with a nut from the opposite side, workability and safety are greatly improved compared to conventional joining by welding.

〔Effect of the invention〕

As described above, according to the reactor pressure vessel pedestal of the present invention, it is possible to significantly shorten the construction period of the reactor pressure vessel pedestal, improve worker safety, and provide a seismic isolation structure. This makes it possible to improve the structural strength.

[Brief explanation of drawings]

FIG. 1 is a vertical sectional view showing a reactor pressure vessel pedestal according to an embodiment of the present invention, FIG. 2 is a horizontal sectional view of the pedestal, FIG. 3 is a sectional view showing details of the joint in FIG. FIG. 4 is a perspective view showing the division of constituent materials, and FIG. 5 is a longitudinal sectional view showing a conventional boiling water reactor. 1... Reactor containment vessel, 2... Reactor building, 3...
・Upper friction plate, 4...Wet well, 5...Dry well, 6...Concrete mat, 8...Reactor pressure vessel, 9...Reactor shielding wall, 10...Joint bolt , 11... Lower friction plate, 12... Inner cylinder steel plate, 1
3... Outer cylinder steel plate. 1st mouth 2nd mouth l〃 father-in-law 3 mouth ivy 4 eyes/l ■5 flashes

Claims (1)

[Claims] 1. In the reactor pressure vessel pedestal, which is composed of a plurality of concentric cylindrical steel plates and a long reinforcing plate extending between the steel plates, upper and lower friction plates are installed at the joint with the concrete at the bottom of the dry well. A nuclear reactor pressure vessel pedestal, wherein the cylindrical steel plate is composed of structural members divided in the vertical direction and the radial direction, and a plurality of structural members are combined to form an integral structure.