JPH022989A - Pressure vessel supporter of reactor - Google Patents

Abstract

PURPOSE:To protect a pressure vessel from being vibrated and contrive the improvement of safety by selecting the required positions on the long-axis direction of a pressure vessel and arranging stabilizers dispersed at two points or more of the positions. CONSTITUTION:A plurality of support bodies 9, 9... are fixed along the upper circumferential face of a thermal shield 5, further a part of first stabilizers 7, 7... are attached to the respective support bodies 9 and their loose ends abut to a pressure vessel 1. The support body 2 of the pressure vessel 1 is fixed on the upper face of a pedestal 3, the pressure vessel 1 is attached by the supporter 2 and its middle part is supported so as to push by the stabilizers 7, 7... from sideward toward the axial center. Further a plurality of supporters 12, 12... are provided on the positions which face the side face of the head part of the vessel 1 while second stabilizers 13, 13... are attached to the supporters 12 respectively, abut to the side face of the head part of the vessel 1 and are worked with the stabilizer 7 to support and reinforce the vessel 1.

Description

Detailed Description of the Invention [Object of the Invention] (Field of Industrial Application) The present invention relates to an improvement of a support device for a reactor pressure vessel of a nuclear reactor.

(Prior art) Referring to Fig. 4, a conventional support means for a reactor pressure vessel will be explained. In the figure, 101 is a concrete shield for shielding radiation. 0 This concrete shield Inside 101, a reactor containment vessel body 102 made of a steel plate is attached to the inner wall with a predetermined gap therebetween.

This reactor containment vessel 201 has a substantially cylindrical bottom portion 102A.
and a conical portion 102B continuous thereto, and further a shoulder portion 102
Consisting of C and 7 rank part 102D・This 7 rank part 1
02D is in an open state, and a lid body 10 is attached to this end.
It is blocked by 3.

A pedestal 104 is constructed within the reactor containment main body 102, and a support 1 is mounted on this pedestal 104.
A reactor pressure vessel 105 is supported via 07.

A heat shielding wall 106 protrudes above the pedestal 4 so as to surround the reactor pressure vessel 105. A pressure control chamber 10 is located in the lower part of the reactor containment vessel main body 102.
9 is formed.

A first stabilizer 110 is provided between the upper part of the heat shielding wall 106 and the reactor containment vessel main body 102. A support plate 111 is fixed to the upper surface of the heat shielding wall 106 corresponding to the stabilizer 110. A second stabilizer 112 is fixed on the support plate 111, and this light leakage is prevented from occurring in the pressure vessel 105. The pressure vessel 1 is brought into contact with the intermediate outer wall I.
It has the effect of suppressing the vibration prevention of 05.

Note that a shag is interposed between the concrete shrouding wall 101 and the reactor containment vessel main body 102. Further, each of the stabilizers 110 and 112 is connected to the pressure vessel 105.
The structure is such that expansion and contraction due to thermal expansion of the heat shielding wall 106 is not restricted.

Since the pressure vessel 105 including the heat shielding wall 106 configured as described above is long, the supporting force in the direction perpendicular to its axis is not necessarily perfect (G).

In addition, since the pressure vessel is particularly exposed to high temperatures, it can be difficult to provide reliable support for the vessel. In other words, it is necessary to provide a support means that accommodates the expansion and contraction in the long axis direction due to thermal expansion of the pressure vessel, which tends to make the supporting force unstable, and it is difficult to obtain a satisfactory result with the conventional configuration.Therefore, various materials have been used. Although repeated attempts were made using this method, sufficient supporting force could not be obtained.

The inventor increased the number of stabilizers in the above support structure (concentrated in some areas), but this had a limit and was not as effective as expected, so he changed the location of the pressure vessel. ◎ This proposal would cause trouble during maintenance and inspection on the intermediate outer wall of the pressure vessel in the conventional structure. (Because there are various piping connections from the pressure vessel) Taking this into consideration, by distributing the stabilizers in the axial direction at the middle and tip of the pressure vessel, we achieved good results after repeated experiments. 0 (Problems to be Solved by the Invention) The present invention emphasizes the above results, and by providing the pressure vessel with vibration resistance, stable operation can be guaranteed◇ [Problem to be solved by the invention] Configuration] (Means for solving the problem) That is, a predetermined position 1c in the long axis direction of the pressure vessel is selected, and stabilizers are arranged dispersedly over at least 2 degrees FyT in this position f to protect the pressure vessel from perturbation. Constructed to protect and increase safety.

(Function) In supporting the reactor pressure vessel according to the present invention, by taking advantage of the long length of the pressure vessel and distributing it in the longitudinal direction and providing stabilizers at several locations, each stabilizer can be The supporting force is increased, and even if the number of supporting forces is reduced compared to the conventional system where the supporting force is concentrated in one place, the supporting force can be safely and reliably supported, so reliability is improved.

Furthermore, it has been discovered that the number of stabilizers does not have to be increased significantly, and it hardly interferes with maintenance and inspection.

(Embodiment) FIG. 1 shows a first embodiment of the support device for a pressure vessel of a nuclear reactor according to the present invention, which includes a concrete shield 10 for shielding radiation, and a concrete shield 10 for shielding radiation.
The reactor containment vessel main body 8 is attached along the inner wall of the reactor containment vessel main body 8 with a predetermined gap therebetween via a shag 11.

A pedestal 3 is constructed within this reactor containment vessel 8,
A heat shield (cylindrical) 5 is fixed thereon. A plurality of supports 9.9 are fixed along the upper peripheral surface of the heat shield 5, and each of the supports 9 has a first stabilizer 7.7.・A part of the pipe is fixed, and its free end is set so as to come into contact with a pressure vessel which will be described later.

A pressure vessel support 2 is firmly fixed to the upper surface of the pedestal 3 by bolts 41ζ, and this pressure vessel support 2ζ
Accordingly, the pressure vessel 1 is mounted with the axis perpendicular to the drawing, and its intermediate portion is supported so as to be pressed from the side toward the center of the axis by the stabilizer 7. In addition, 21, 21... are the 3rd stabilizers attached between the shielding body 10 and the heat shielding body 5.

Furthermore, a plurality of supports 1212 are provided at positions that are part of the shield 10 and are opposed to the side surface of the head of the pressure vessel 1, and these supports 12,12... Stabilizers 13, 13, etc. are respectively attached, and are brought into contact with the side walls of the head of the pressure vessel 1, and work together with the first stabilizer to maintain support and reinforcement of the pressure vessel 1, and thereby stabilize the reactor. The pressure vessel support device 1001 is configured as follows.

The pressure vessel support device 100 for a nuclear reactor according to the present invention includes first and second stabilizers 7.7..., 13, 13... distributed at predetermined positions in the longitudinal direction of the pressure vessel 1 (
As a result, each stabilizer jointly performs a photographic suppression effect against vibrations from the sides, so compared to a single stabilizer, the supporting force as a whole is strong even though each stabilizer itself does not have to be as strong. This has an extremely advantageous effect on the expansion and contraction of the pressure vessel.

FIG. 2 shows another example of the pressure vessel support device for a nuclear reactor according to the present invention, in which instead of supporting the head of the pressure vessel 1, a fourth It is attached as a stabilizer.

The supports 14, 14... and the fourth stabilizer 15, 15 are arranged so that they are balanced at positions with the same gap vertically with the center y in the longitudinal direction of the pressure vessel l as the midpoint.
... were installed to constitute a reactor pressure vessel support device 100.

In this case as well, it has been demonstrated that the supporting force is extremely stable, as in the above embodiments.

FIG. 3 shows yet another embodiment, in which the area around the piping for sucking and discharging liquid sodium, etc. to the pressure vessel 1 is used, and an elastic support is interposed in this area to stabilize it against vibrations. It is.

That is, although the description is omitted in Examples 1 and 2 above, there is actually a pipe 17 for introducing a filler (agent) such as liquid sodium to be filled or discharged into the pressure vessel 1.
17 and 17, and piping attachment nozzles 16, 16, and 16 for attaching the same are attached, respectively.

The elastic support 18 provided so as to surround each pipe 17 and the pipe attachment nozzle 16 is formed in a conical shape, and is mounted so that the large part is in contact with the heat shield 5, thereby reducing the pressure. The container 1 and the thermal shield 5 are elastically supported. The number of pipes 17 may be equal to the number of pipes 17, but not all of them are necessarily provided.

The elastic support 18 can also have a radiation shielding effect by using a material having a large neutron absorption cross section, such as (B).

With the above configuration, the elastic support 18 is interposed between the pressure vessel 1 and the heat shield 5 and elastically supports the required portions, and the support is distributed in the axial direction, so that the elastic support 18 is disposed between the pressure vessel 1 and the heat shield 5. The burden placed on it is lighter, its lifespan is longer, and maintenance is easier.

”^1 The pressure vessel support device for the nuclear reactor of the present invention is a pressure vessel supporting device for a long pressure vessel 1.
Since the stabilizers are distributed and supported in the longitudinal direction of the pressure vessel, the impact on the stabilizers etc. can be softened by dispersing the imaging load applied to the pressure vessel. Therefore, the fatigue level of the stabilizers and elastic support 18 can be reduced. Since the damage is reduced, its lifespan is long and maintenance is easy. In addition, the pressure vessel is held vertically extremely stably by the holding action of the stabilizers distributed in the axial direction, and various effects such as being able to sufficiently cope with expansion and contraction of the pressure vessel due to temperature changes, etc. playing 0

[Brief explanation of the drawing]

1 to 3 are sectional views of essential parts of an embodiment of a pressure vessel support device for a nuclear reactor according to the present invention, and FIG. 4 is a sectional view of essential parts of a conventional nuclear reactor. 1... Pressure vessel, 5... Heat shield, 7.13...
Stabilizer, 18...elastic support 0

Claims (1)

[Claims] (1) At least 2 in the long axis direction of the long reactor pressure vessel.
1. A pressure vessel support device for a nuclear reactor, characterized in that stabilizer support means for supporting the pressure vessel are provided in dispersed locations.