JPS6316294A - Nuclear reactor container - 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] [Objective of the Invention] (Industrial Application Field) The present invention relates to a concrete reactor containment vessel, and particularly to a method for reducing seismic loads on heat shielding walls inside the reactor containment vessel. Regarding the reactor containment vessel that can be used.

[Conventional technology]

A conventional concrete reactor containment vessel is constructed as shown in FIGS. 6 and 7. That is, reference numeral 1 denotes a reactor containment vessel, which is made of, for example, reinforced concrete, and has pressure resistance and radiation shielding ability. A liner 2 is stretched over the inner surface of the reactor containment vessel 1 to provide airtightness. In addition, this reactor containment vessel 1
The inside is divided into upper and lower parts by a diaphragm floor 3, with a dry well 4 in the upper part and a suppression chamber 5 in the lower part. A pedestal 6 is erected within the reactor containment vessel 1, and a reactor pressure vessel 7 is installed on the pedestal 6. Further, a cylindrical heat shielding wall 8 is provided surrounding the pressure vessel 7.

The upper end of this heat shield wall 8 is supported by the inner circumferential surface of the reactor containment vessel 1 via a support member 30, and the horizontal load applied to this heat shield wall 8 and pressure vessel 7 in the event of an earthquake etc. is transferred to the reactor reactor. It is designed to be supported by the containment vessel 1.

By the way, these supporting members 30 have conventionally been provided horizontally between the outer circumference of the upper end of the heat shield wall 8 and the inner circumferential surface of the reactor containment vessel main body 1, so that the isolation valve of the main steam pipe 10 A rail 11 on which a hoist crane such as 108 is mounted and removed is provided below the support member 30.

Furthermore, the attachment portion between the support member 30 and the containment vessel 1 is compared to the containment vessel 1 as shown in FIG.

A large-sized support fitting 31 is embedded, and the large horizontal load acting through the support member 30 is dispersed and supported by the containment vessel 1.

Further, the heat shielding wall 8 and the pressure vessel 7 are connected by a connecting member 9. -Furthermore, a flange member 14 for attaching the upper lid 13 is separately formed, and this flange member 14 is attached to a large-sized fitting 32 embedded in the upper part of the containment vessel body 1.

In addition to the above-mentioned conventional example, the support WJ structure between the reactor containment vessel and the heat shield wall is constructed from a plurality of support members consisting of a vibrator projecting upward from the heat shield wall, and a shag structure is used. A system in which a heat shielding wall and a reactor containment vessel are connected is known (Japanese Patent Laid-Open No. 58-2781).

(Problem to be solved by the invention) When a nuclear reactor building is installed in a high earthquake zone, the entire reactor containment vessel may become thick (shake) due to an earthquake. The shaking of the container 7 and the heat shielding wall 8 is controlled by the support member 30.
It is transmitted to In order to improve the earthquake resistance of the pressure vessel 7 and the heat shield wall 8, it is effective to increase the rigidity of the support member 30 between the heat shield wall 8 and the containment vessel 1. However, the support member 30 generally consists of a vibrator or the like;
Increasing the cross-sectional area of this vibrator to increase its rigidity is limited by the space within the containment vessel. Furthermore, since the support member 30 of the conventional reactor containment vessel is provided in the horizontal direction, the traveling rail 11 must be provided below the support member 30, making it possible to effectively utilize the upper space within the containment vessel 1. I can't.

Moreover, since the support II 4 structure of JP-A-58-2781 is also composed of a plurality of pipe materials, there is a limit to increasing the cross-sectional area of the pipe materials to increase the rigidity.

The present invention has been made in consideration of the above points, and particularly aims to provide a nuclear reactor containment vessel that can reduce seismic loads on heat shielding walls and improve seismic resistance.

[Structure of the invention]

(Means for Solving the Problems) The present invention provides a reactor containment vessel in which a cylindrical heat shielding wall is erected inside the reactor containment vessel. A plurality of shear blocks are fixed to each other, and a ring loosely fitted at a predetermined interval on the upper outer periphery of the heat shielding wall is supported by the shear block, and the seismic load applied to the heat shield wall is transferred to atoms through the rings and shear blocks. It is characterized by being configured to transmit information to the reactor containment vessel.

(Function) When an earthquake occurs and the heat shield wall shakes horizontally due to the seismic load and comes into contact with the ring, this seismic load is transmitted to the reactor containment vessel through the ring and mainly through the shear blocks whose load direction is in the radial direction. be done.

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

1 to 5 are diagrams showing an embodiment of the reactor containment vessel according to the present invention.

Note that the same members as those in the conventional example are given the same reference numerals and detailed explanations will be omitted. In FIG. 1, a reactor containment vessel 1 is made of reinforced concrete and is strongly formed, and has earthquake resistance and radiation shielding ability.

A liner 2 made of a steel plate or the like is tightly attached to the inner surface of the reactor containment vessel 1.
Airtightness is provided by

The inside of this reactor containment vessel 1 is divided into upper and lower parts by a diaphragm floor 3, and the upper part is a dry well 4.
A suppression chamber 5 is formed in the lower part. In addition, a pedestal 6 is installed in the center of the reactor containment vessel 1.
is erected, and a pressure vessel 7 is mounted on this pedestal 6.
is installed. Further, a cylindrical heat shielding wall 8 is erected on the pedestal 6 to surround the pressure vessel 7 and shield heat from the pressure vessel 7. The pressure vessel 7 and the heat shielding wall 8 are connected via a connecting member 9. Further, reference numeral 10 is a main steam pipe, and a main steam isolation valve 10a is provided in the middle thereof. Further, a flange member 14 made of T14 is provided at the upper opening of the reactor containment vessel 1, and an upper M13 is detachably attached to this flange member 14.

Further, on the upper outer periphery of the heat shield wall 8, this heat shield wall 8
A ring 18 is loosely fitted to surround the
This ring 18 is supported by a shear block 15 fixed to the lower surface of the earthen wall of the reactor containment vessel 1.

The ring 18 and shear block 15 will be explained in further detail with reference to FIGS. 2 to 4.

FIG. 2 is an enlarged view of part A in FIG. 1. In FIG. 2, a mounting bracket 16 is fixed to a stud bolt 17 embedded in the lower surface of the upper wall of the reactor containment vessel 1, and a shear block 15 is attached to the mounting bracket 16. A ring 18 is supported by the shear block 15, and a predetermined clearance 19 is formed between the ring 18 and the heat shield wall 8. It can be slid vertically.

As shown in FIG. 4, a plurality of ICC shear blocks 15a, 15b, and 15c are provided radially in the circumferential direction. It has a durable structure.

Next, the operation of this embodiment having such a configuration will be explained.

When an earthquake occurs, a horizontal earthquake load is generated on the pressure vessel 7 and the heat shield wall 8, which are connected by the connecting member 9. This seismic load causes the heat shield wall 8 to shake in the horizontal direction, and the heat shield wall 8 comes into contact with the ring 18 . In this case, pressure vessel 7
The earthquake load generated on the heat shielding wall 8 passes through the ring 18,
Shear block 15 whose load direction is mainly the radial direction
is transmitted to the reactor containment vessel 1 by. In other words, when an earthquake load occurs in the L1 direction as shown in Figure 4,
Shear block 15 whose radial direction is mainly in the L1 direction
b is transmitted to the reactor containment vessel 1.

Furthermore, as described above, the clearance 19 is formed between the heat shield wall 8 and the ring 18, and both can slide in the vertical direction, so even if the heat shield wall 8 is thermally deformed,
Due to the clearance 19 for radial thermal deformation,
Heat shielding wall 8 and ring 18 for vertical thermal deformation
Both can be released by sliding motion with.

As explained above, according to this embodiment, the horizontal seismic load generated on the pressure vessel 7 and the heat shield wall 8 is transmitted to the reactor containment vessel 1 by the shear block 15 via the ring 18. Unlike a conventional pipe-shaped support member, the shear block 15 can be enlarged in shape to increase its rigidity without particularly reducing the upper girth space within the reactor containment vessel 1. By increasing the rigidity in this way, it is possible to reduce the seismic load on the pressure vessel 7 and the heat shield wall 8 and the seismic load on the piping and the like in the reactor containment vessel 1.

FIG. 5 shows a comparison of the response (acceleration magnification) of the spectrum for piping design between the present invention and the conventional example. From Figure 5, in the vicinity of the period of 0.1 seconds of the main piping system in the reactor containment vessel,
It can be seen that the input to the piping system is approximately one hand smaller in the present invention. As is clear from this example, the use of the shear block 15 that can increase rigidity provides a great effect on earthquake resistance.

In addition, the seismic load on the heat shield wall 8 is transmitted to the reactor containment vessel 1 via a ring 18 fitted on the outer periphery of the upper part of the heat shield wall 8 and a shear block 15 fixed to the lower surface of the upper wall of the reactor containment vessel 1. Therefore, the upper space inside the reactor containment vessel 1 can be used more effectively than in the conventional device in which the support member is provided horizontally.

〔Effect of the invention〕

According to the present invention, the shear block can be enlarged and increased in rigidity without particularly reducing the upper space inside the reactor containment vessel, so it is possible to prevent seismic loads that are applied to heat shield walls and piping inside the reactor containment vessel. It is possible to reduce the amount of energy generated.

[Brief explanation of the drawing]

1 to 5 are diagrams showing one embodiment of the reactor containment vessel according to the present invention, in which FIG. 1 is a vertical sectional view thereof, FIG. 2 is an enlarged view of FIG. 1 Am, and FIG. Figure 2 ■-■ line sectional view,
Fig. 4 is a plan view showing the arrangement of shear blocks and rings, Fig. 5 is a drawing showing a comparison of response of spectra for piping design between the present invention and a conventional example, and Fig. 6 shows a conventional reactor containment vessel. The vertical cross-sectional view and FIG. 7 are an enlarged view of part B in FIG. 6. DESCRIPTION OF SYMBOLS 1... Reactor containment vessel, 2... Liner, 7... Pressure vessel, 8... Heat shield wall, 9... Connecting member, 10
...Main steam pipe, 13...Top lid, 14...Flange member, 15...Share block, 18...Ring. Applicant's agent @ wisteria - male vine l zucha 3 haisecha 4 tsutsune O zuimo 7 fig.

Claims (1)

[Claims] In a reactor containment vessel in which a cylindrical heat shielding wall is erected inside, a plurality of shear blocks are fixed along the circumferential direction to the lower surface of the upper wall of the reactor containment vessel, and a plurality of shear blocks are fixed to the upper outer periphery of the heat shielding wall. A reactor containment vessel characterized in that a ring loosely fitted at a predetermined interval is supported by the shear block, and an earthquake load applied to the heat shield wall is transmitted to the reactor containment vessel via the ring and the shear block. .