JPH01265197A - Reactor storage container - Google Patents

Abstract

PURPOSE:To improve the seismic resistance of a reactor vessel by changing the vessel to a concrete structure to support said vessel and providing means of suppressing the horizontal swiveling of said vessel to a reactor pedestal. CONSTITUTION:A hanging means 17 is provided between a side wall 13 which is the concrete structure and the upper position in the cylindrical part of the reactor pressure vessel 3 and the pressure vessel 3 is supported in a hanging state over the entire part by this hanging means 17. The circumferential restraining means 18 is disposed to the inside circumferential part of the reactor pedestal 4 to prevent the horizontal swiveling in the lower part of the vessel 3. The restraining means 18 is a kind of the shear lag mechanism interposed between the cylindrical part of the pressure vessel 3 and the side wall 13 and is constituted of an engaging member 23 formed to project radially and outward from the lower part of the cylindrical part of the vessel 3 and a pair of restraining members 24 which allows the vertical movement of the member 23 and limits the circumferential movement thereof.

Description

Detailed Description of the Invention "Industrial Application Field" The present invention relates to a nuclear reactor containment vessel, and in particular, the reactor pressure vessel is supported in a suspended state on a concrete side wall, and the reactor pressure vessel is This relates to technology for suppressing horizontal rotation.

``Prior Art'' Figure 5 shows a conventional example of a reactor containment vessel for a boiling water reactor. The reactor pressure vessel 3, reactor pedestal 4, and reactor shielding wall 5 are housed in the diaphragm floor 6.
A dry well 7 and a suppression chamber 8 are partitioned.

The weight of the reactor pressure vessel 3 is supported by placing and fixing the skirt part 9 on the step part 4a of the reactor pedestal 4, and the weight of the reactor pressure vessel 3 is
A sealing device 10 is installed between the upper part of the dry well 7 and the concrete bioshielding wall l, which is used when filling the upper part of the dry well 7 (reactor well) with water when exchanging nuclear fuel.

In addition, a large number of vent pipes 11 are suspended from the diaphragm floor 6, and when the pressure in the dry well 7 suddenly increases due to, for example, reactor cooling water gushing out,
Pressure steam is ejected from the lower opening of the vent pipe 11 into the pool water W to reduce the volume due to condensation, thereby suppressing an increase in the internal pressure of the reactor containment vessel.

On the other hand, we are working to improve the specifications of boiling water reactors (BWR') and improve work efficiency in constructing reactor containment vessels, securing internal safety equipment installation locations, maintenance inspections, and repair work. For the purpose of achieving
) are being planned.

, ``Problem to be Solved by the Invention'' However, in all of these reactor containment vessels, the skirt portion 9 at the lower position of the reactor pressure vessel 3 is connected to the vertical cylindrical reactor pedestal 4. Since the device is supported in a mounted state, the distance from the support point (mounting point) to the upper part of the reactor pressure vessel 3 becomes large, and the horizontal shaking of the reactor pressure vessel 3 in the vicinity of the sealing device 10 is caused. , the amount of vertical expansion and contraction of the reactor pressure vessel 3 increases,
Since it is necessary to set the dimensional absorption amount of the bellows 10a that constitutes the sealing device 10 to be large, and because it is intended to limit the occurrence of large lateral vibrations, this is disadvantageous in terms of earthquake-resistant structure. Further, since the ABWR is planned to have a structure in which a lower dry well is formed below the reactor pressure vessel 3, the installation space near the skirt portion also becomes a problem.

The present invention solves the problems of the prior art. In other words, the objectives are to omit the bellows of the reactor well seal device, to improve earthquake resistance, and to expand the volume of the lower dry well in ABWR.

"Means for Solving the Problems" In the reactor containment vessel according to the present invention, a suspension means is provided on the inner surface of the concrete side wall and is integrated with the upper part of the reactor pressure vessel, and a suspension means is provided on the inner surface of the reactor pedestal. The reactor pressure vessel has a configuration in which circumferential restraint means for suppressing horizontal rotation of the lower part of the reactor pressure vessel is provided, and in addition to this configuration, the suspension means also serves as a reactor well sealing device.

"Function" For this reason, the reactor pressure vessel as a whole is supported in a suspended state, with the support point located above and directly supported by the concrete structure, and the lower part of the reactor pressure vessel In this case, the earthquake-resistant structure is simple because support is mainly focused on preventing shaking and allowing thermal expansion and contraction.

Furthermore, the support structure in the vicinity of the support point is simplified by serving both the suspension means and the reactor well sealing device in the vicinity of the support point.

"Embodiment" Hereinafter, an embodiment of a nuclear reactor containment vessel according to the present invention will be described based on FIGS. 1 to 4.

In this embodiment, as shown in FIG.
It is used for WR, and its side wall (concrete side wall) 13 has a vertical cylindrical shape, and has a sealed structure with a liner 14 attached to the inner surface, and an upper dry well 15 is placed on the diaphragm floor 6. , a lower dry well 16 is formed inside the reactor pedestal 4.

And, as shown in Figure 2, the side walls are concrete structures! 3 and a position above the body of the reactor pressure vessel 3, there is provided a suspension means 17 for integrally connecting these and suspending the reactor pressure vessel 3 as a whole. And as shown in Figure 4, the reactor pedestal 4
A circumferential restraining means 18 for suppressing the horizontal rotation of the lower part of the reactor pressure vessel 3 is disposed on the inner circumferential portion of the reactor pressure vessel 3 .

The suspension means 17 includes an upward skirt portion 19 integrally formed above the trunk of the reactor pressure vessel 3;
The dry well 7 is composed of a flange 20 attached to the upper end of the upward skirt portion 19 and a bulkhead 21 that supports the flange 20 and is formed to protrude inward from the side wall 13 which is a concrete structure. In addition to partitioning the actuator well 22 into an airtight state,
This structure also serves as the sealing device @10 shown in FIG.

The circumferential restraint means 18 is a type of shag lug mechanism that is interposed between the body of the reactor pressure vessel 3 and the side wall 13, and extends radially outward from the lower part of the body of the reactor pressure vessel 3. Engagement member 2 integrally formed in a protruding state
3, and a pair of restraining members 24 integrally attached to the inner surface of the side wall 13 in order to allow relative movement of the engaging member 23 in the vertical direction and restrict movement in the circumferential direction, A plurality of sets (for example, 8 locations) are installed at intervals in the circumferential direction.

In addition, in FIG. 1, the reference numeral 25 indicates the reactor pedestal 4.
This is a horizontal vent pipe that penetrates through and is connected to both dry wells 15 and 16.

In the reactor containment vessel configured in this way, the reactor pressure vessel 3 is supported in a suspended state above the side wall 13, and the support point by the suspension means 17 is centered on the reactor pressure vessel 3. The lower part of the reactor pressure vessel 3 is indicated by the arrow in Figure 1 (I).
) (b) will result in shaking as shown in (b). This shaking is prevented by the circumferential restraining means 18, which provides support that allows displacement when the trunk of the reactor pressure vessel 3 thermally expands and contracts in the radial direction and the vertical direction.

Therefore, assuming that the reactor pressure vessel 3 has a simple earthquake-resistant structure that prevents rolling at the upper and lower positions, the suspension means 17 near the upper support point is It also serves as the reactor well sealing device IO. Therefore, the support point and the position of the sealing device 10 almost coincide with each other, and in the vicinity of the support point, the setting of dimensional absorption due to thermal expansion and contraction of the reactor pressure vessel 3 is omitted, and the above-mentioned simple structure without bellows is used. It becomes a structure.

On the other hand, high-temperature reactor cooling water is leaking from the piping supported by the pipe structure in the upper dry well 15 and various equipment mounted on the diaphragm floor 6 due to leakage, breakage, etc. Upper dry well 15
Considering the case where an abnormal phenomenon occurs such as spouting, as the internal pressure of the upper dry well 15 increases, pressure steam passes between the plurality of circumferential restraining means 18 and enters the lower dry well 16. The pressure steam is ejected from the horizontal vent pipe 25 into the boule water W of the subreduction chamber 8, and the volume of the pressure steam is reduced by the condensation action, thereby suppressing the pressure rise.

In this case, both the dry wells 15 and 16 are connected to each other via a plurality of circumferential restraining means 18 arranged at intervals. A communication path can be omitted.

Furthermore, the skirt portion 9 shown in FIG. 5 is not present in the lower part of the reactor pressure vessel 3, and the volume of the lower dry well 16 in the example shown in FIG. 1, that is, in the ABWR, can be expanded.

Note that the number and specific structure of the circumferential restraining means 18 can be arbitrary as long as the functions thereof are satisfied.

"Effects of the Invention" As explained above, according to the reactor containment vessel according to the present invention, ■ a suspension means integrated with the upper part of the reactor pressure vessel is provided on the inner surface of the concrete side wall, and the reactor Since the entire pressure vessel is suspended, the support point is located above and directly supported by the concrete structure, and the lower part of the reactor pressure vessel is designed to prevent shaking and allow for thermal expansion and contraction. The earthquake-resistant structure is simple, with support centered on the

■Since the reactor pedestal is provided with a circumferential restraining means to suppress the horizontal rotation of the reactor pressure vessel, the seismic structure can be simplified.

(2) As described above, the lower structure of the reactor pressure vessel can be simplified and the volume of the lower dry well can be expanded.

(2) Since the suspension means also serves as a reactor well sealing device, and the support point and the sealing position almost coincide, the sealing structure in the vicinity can be simplified.

This results in excellent effects such as:

[Brief explanation of the drawing]

Fig. 1 is a partially omitted front cross-sectional view showing an embodiment of the reactor containment vessel of the present invention, Fig. 2 is an enlarged view of the part indicated by the chain line ■ in Fig. 1, and Fig. 3 is an enlarged view shown by the chain line in Fig. 1. FIG. 4 is an enlarged view of part (2), FIG. 4 is a view taken along the line IV--(2) in FIG. 3, and FIG. 5 is a partially omitted vertical cross-sectional view showing a conventional example of a nuclear reactor containment vessel. 3...Reactor pressure vessel, 4...Reactor pedestal, 6...Diaphragm floor, 7...Diaphragm floor, 8... Suppression chamber, 12...
... Concrete container, 13 ... Side wall, 14 ... Liner, 15 ... Upper dry well, 16 ... Lower dry well, 17 ... ...
- Hanging means, 18... Circumferential restraint means, 19... Upward skirt portion, 20... Flange, 21... Bulkhead, 22... ... Reactor well, 23 ... Engagement member, 24 ... Restraint member, 25 ... Horizontal vent pipe, W ... Pool water. Applicant Ishikawajima Harima Heavy Industries Co., Ltd. Figure 1 Figure 2 Figure 4 Figure 1

Claims (1)

[Claims] 1. A suspension means integrated with the upper part of the reactor pressure vessel is provided on the inner surface of the concrete side wall, and the horizontal rotation of the lower part of the reactor pressure vessel is suppressed on the inner circumference of the reactor pedestal. A nuclear reactor containment vessel equipped with circumferential restraint means. 2. The reactor containment vessel according to claim 1, wherein the suspension means also serves as a reactor well sealing device.