JPS62263497A - 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 nuclear reactor containment vessel, and particularly to a reactor containment vessel with improved seismic resistance.

(Prior art) The reactor containment vessel houses the reactor subsystem equipment such as the pressure vessel and recirculation equipment, and even if radioactive material leaks from the reactor subsystem due to an accident, it will be able to release it to the outside. This is a device to confine the substance so that it does not come out.

Figure 9 shows the conventional MARK-I type reactor containment vessel,
The reactor containment vessel 2111 is made of steel and is under pressure*! 2, etc., and a cylindrical suppression chamber 4 that stores subrepression chamber water (not shown). (not shown) are connected in one series. In addition, between the dry well 3 and the suppression chamber 4, there is a space 4 which divides the inside of the reactor containment capacity 1,110 into upper and lower parts.
A diaphragm floor 5 is provided. However,
The reactor containment vessel 1 is anchored on the reactor building matte door, and is formed so that the bottom surface of the suppression chamber 4 is located on the same plane as the matte surface of the reactor building matte door, and the outer peripheral surface of the reactor containment vessel 1 is It is surrounded by a building shell wall 9 of the furnace building 8.

By the way, in the atomic containment vessel 1 constructed as described above, the thickness of the steel plates forming the containment vessel is thin compared to its diameter, so when the entire reactor 1118 shakes during the earth m The deformation of the building is transmitted to the containment vessel.
In particular, in the case of a design that absorbs seismic force by increasing the deformation of the building, this forced displacement may cause buckling and cracking in the suppression chamber 4 of the containment vessel.
There was a risk that the water from the suppression chamber would leak to the outside and the water source for the emergency core cooling system would be isolated. For this reason, it has been proposed to reinforce the portion of the reactor containment vessel 1 where buckling may occur, that is, the periphery 14a of the suppression chamber 4, to increase its rigidity so that it can withstand larger loads.

(Problem to be solved by the invention) However, the load applied to the reactor containment vessel 1 during an actual earthquake is a displacement control type load determined according to the amount of deformation of the reactor building 8, and as described above, buckling occurs. If the rigidity of the reactor containment vessel 1 is reduced by considering only the load Φ, the deformation of the containment vessel will be conversely restricted.

As a result, it has been found that a large force acts on the reactor containment vessel 1 to deform the containment vessel, which is counterproductive in terms of preventing buckling of the containment vessel.

Therefore, the present invention solves the problems of the above-mentioned conventional technology, improves the earthquake resistance of the containment vessel so that buckling does not occur in the reactor containment vessel during an earthquake, and provides a highly safe reactor containment vessel. The purpose is to

[Structure of the invention]

(Means for Solving the Problems) In order to achieve the above object, the present invention provides a method for deforming a reactor containment vessel to absorb the amount of deformation that the containment vessel receives from the reactor building into a suppression chamber that constitutes the reactor containment vessel. A cup-absorbing device is installed.

(Function) When a nuclear reactor power generation facility is hit by an earthquake, the entire reactor building shakes, and the deformation of the reactor building is transmitted to the reactor containment vessel through the layered shell wall. Since the deformation force is absorbed by the deformation absorbing device, the rigidity of the reactor containment vessel against bending is reduced and the permissible displacement against buckling is increased, making it possible to prevent buckling.

(Embodiment) Hereinafter, a first embodiment of a nuclear reactor containment vessel according to the present invention will be described with reference to FIGS. 1 to 5. Note that the same reference numerals are used for the same parts as in FIG. 9.

In FIG. 1, reference numeral 1 indicates a reactor containment vessel, which is formed of a thin steel plate and is a conical dry well that stores a pressure vessel 2 and the like inside and forms the upper part of the containment vessel. 3 and a cylindrical suppression chamber 4 that stores suppression chamber water (not shown), which is a water source for the emergency core cooling system, and forms the r section of the containment vessel. They are connected together by a steel vent pipe (not shown). Further, the reactor containment vessel 211 is anchored on the reactor building pine door via a steel plate liner 6, and the outer peripheral surface of the containment vessel is surrounded by the building shell wall 9 of the reactor building 8.

Incidentally, a bead portion 10 is formed at the base of the peripheral wall 4a of the suppression chamber 4, as shown in FIG. This bellows part 10 is integrally formed with a thin plate of the same w4\IJ as the suppression chamber 4, and the lower end of the bellows part 10 is joined to a steel plate live 6 installed on the reactor building mat door. ing.

Therefore, the nuclear power generation facility equipped with the reactor containment vessel 1 configured as described above is I! ! When an earthquake hits, the nuclear reactor
The entire reactor building 8 shakes, especially if the building is designed to absorb seismic force by increasing its deformation.
The oscillation becomes larger. For this reason, reactor building 8
Since the deformation is transmitted to the reactor containment vessel 1 via the building shell wall 9, the containment vessel is forced to receive a deforming force from the reactor building 8. However, since the bellows portion 10 is formed at the base of the reactor containment vessel 1, the bellows portion 10 is bent and deformed by the above deformation force, and the reactor containment vessel 1 is deformed with the bellows portion 10 becoming a knot. For this reason,
Due to the bending deformation of the bellows portion 10, the forced deformation of the reactor containment vessel N1 from the reactor limber 8 during an earthquake is absorbed, reducing the stress generated in the reactor containment vessel 1, especially the suppression chamber 4, and causing buckling. can be prevented. In this way, the bellows portion 10 moves to absorb deformation of the reactor containment vessel 1, reducing the rigidity of the containment vessel against bending and increasing the permissible displacement against buckling. Buckling can be prevented and earthquake resistance can be improved.

3 to 5 show modifications of the first embodiment, and FIG. 3 shows a case in which the bell oxide portion 10 is formed not only at the base of the suppression chamber 4 but also at the middle aS. .

Further, FIG. 4 shows that the bellows part 10 is formed in the upper part of the suppression chamber 4 at the connecting part between the dry well 3 and the subledge gin chamber 4, and furthermore, FIG. Peripheral wall 4a rest area 0-1
1 is shown. In any of the modified examples, the base portion 1 is
Since the bellows 11 is curved and deformed, the forced deformation m that the reactor containment vessel 1 undergoes during an earthquake is absorbed, and buckling that occurs in the reactor containment vessel B1 can be prevented.

FIG. 6 shows a second embodiment of the night reactor containment vessel according to the present invention, in which the peripheral wall F end 4b of the suppression chamber 4 is formed to extend downward from the bottom surface of the suppression chamber. On the other hand, a recess 12 having a depth corresponding to the contour of the extended lower end 4b of the peripheral wall is formed in the reactor building pine door, and the containment vessel 1 is installed on the bottom of the recess 12 in a predetermined manner. It is anchored by .

By the way, it has been found that when a lateral load is applied to a cylindrical shell having the same radius R and the same plate thickness t, the larger the axial length, the larger the permissible displacement against buckling. According to this embodiment, the peripheral wall 4a of the pressure chamber 4 is formed long in the axial direction, and the extended lower peripheral wall E8B4b is discussed as the deformation amount absorption v4!2 of the reactor containment vessel 1, so the reactor The permissible displacement of the containment vessel 1 against buckling can be increased, and buckling can be prevented.

FIGS. 7 and 8 show a third embodiment of the nuclear containment vessel according to the present invention, and as shown in FIG.
! ! The pressure chamber 4 constituting the reactor building 1 is anchored on a concrete foundation 13 formed separately from the reactor building pine door. Further, the foundation 13 is extended by +51 m into a recess 14 formed in the matte door of the reactor building so that the upper surface 13a of the foundation 13 is located in the same plane as the mat surface 7a. Note that the foundation 13 is simply placed on the reactor building pine door and is not fixed.

According to this embodiment, when the reactor containment vessel 1 receives a forced deformation force, the base 13 that anchors the containment vessel
Since the restraining force on the Matsudoor of the containment vessel is relaxed due to the rigidity of the cap, the base 13 functions as a deformation @ accommodation device, increasing the permissible displacement of the atomic containment volume s1 against buckling and preventing the buckling. It can be prevented. Furthermore, since the nuclear power plant door and the foundation 13 can be constructed separately, it is possible to significantly shorten the construction period of the nuclear power generation facility.

FIG. 8 shows a modification of the third embodiment, in which a support member 15 made of rubber or the like is interposed between the base 13 and the reactor housing 7. According to this modification, the minute displacements, rotations, etc. of the foundation 13 on the reactor building pine door become larger, so that the reactor containment vessel 1 is more freely restrained by the pine door, and the containment vessel 1 itself is subjected to Deformation can be further reduced, and the safety of the containment vessel 1 against buckling can be improved.

In each of the above embodiments, the MARK-If type atom containment vessel has been described, but it goes without saying that the present invention is not limited to the MARK-■ type.

〔Effect of the invention〕

As is clear from the above description, according to the present invention, a deformation absorbing device is provided in the subledge chamber constituting the reactor containment vessel to absorb the deformation that the containment vessel receives from the reactor. Therefore, it is possible to reduce the rigidity of the reactor containment vessel against bending and increase the permissible displacement against buckling, thereby preventing buckling of the reactor containment vessel during an earthquake and improving the earthquake resistance of the reactor containment vessel. It is possible to obtain a reactor containment vessel with improved safety and high safety.

4. Brief description of the drawings Fig. 1 is a cross-sectional schematic diagram showing the first embodiment of the reactor containment vessel according to the present invention, Fig. 2 is a partially enlarged view of Fig. 1, and Figs. 3 and 4 are the same as those described above. A partially enlarged view showing a modification of the first embodiment; FIG. 5 is a schematic cross-sectional view showing a modification of the first embodiment;
FIG. 6 is a 1-meter schematic cross-sectional view showing a second embodiment of the reactor containment vessel according to the present invention, FIG. 7 is a cross-sectional schematic diagram showing a third embodiment of the reactor containment vessel according to the present invention, and FIG. 8 is the above-mentioned FIG. 9 is a partially enlarged view showing a modification of the embodiment, and is a schematic cross-sectional view showing a conventional reactor containment vessel.

1... Reactor containment vessel, 3... Dry well, 4...
... Suppression chamber, 7... Reactor building mat, 8... Reactor building, 9... Building shell wall, 10
...Bellows part, 11...Bellows, 12.14.
... recess, 13... foundation stand.

Applicant's agent: Mr. Sato ヱ Figure 1 Figure 2 Figure 3 Figure 4 ヱ Figure 5 Figure 6 Figure 8 s9 diagram

Claims (1)

[Claims] 1. In a reactor containment vessel in which a dry well and a suppression chamber provided below the dry well are installed in the shell wall of a reactor building, the suppression chamber is provided with a reactor containment vessel. 1. A reactor containment vessel, characterized in that it is provided with a deformation absorption device for absorbing variable measurements received from a reactor building. 2. The reactor containment vessel according to claim 1, wherein the deformation absorbing device is a bellows formed on the peripheral wall of the suppression chamber. 3. The reactor containment vessel according to claim 1, wherein the deformation absorbing device is a lower end portion of the peripheral wall of the suppression chamber extending downward from the bottom surface of the suppression chamber. 4. The reactor containment vessel according to claim 1, wherein the deformation absorbing device is a foundation that anchors the suppression chamber and is placed on a reactor building mat.