JPS59220643A - Track for surface running of pressure vessel of nuclear reactor - Google Patents

Abstract

PURPOSE:To attain to reduce heat stress and to enhance earthquake-proofness by using an inspection apparatus in two or more of plants in common, by a method wherein a vertical track and a peripheral track are divided and held so as to provide gaps so as to be spaced apart from the pressure vessel of a nuclear reactor while the own wts. of the tracks arranged in adjacent relationship are held in a gamma-shield. CONSTITUTION:The peripheral track crossing vertical tracks 3 and supports 5 consists of upper peripheral tracks 2a, 2b and lower peripheral tracks 2a', 2b' while supports 7 are provided so as to bridge the space between the peripheral tracks 2a, 2a' and the space between the peripheral tracks 2b, 2b'. Vibration dampening tools 8 are also provided between the supports 5, 7 and a gamma-shield 11 so as to bridge both of them and vibration dampening tools 12 bridging the vertical tracks 3 and the gamma-shield 11 are provided to the lower sides of the vertical tracks 3. Tracks 1a, 1b are supported through the vibration dampening tools 8, 12 by the gamma-shield 11. When the heights from the peripheral tracks 2a, 2b to brackets 6 are made equal, the parts below the peripheral tracks 2a, 2b are displaced during thermal deformation while the same relative position is held and heat stress is absorbed by the action of the link mechanisms 8a of the vibration dampening tools 8, 12. The vibration of the tracks 1a, 1b caused by an earthquake becomes stationary because of being elastically supported in the vertical and radius directions and restrained in the movement thereof to the peripheral direction by the vibration dampening tools 8, 12.

Description

[Detailed Description of the Invention] [Field of Application of the Invention] The present invention relates to a surface running track having a vertical track and a circumferential track on which an inspection device for inspecting fuselage weld lines of a nuclear reactor pressure vessel runs. The present invention relates to a running track for a nuclear reactor pressure vessel that allows the above-mentioned inspection equipment to be shared across two or more plants and is excellent in reducing thermal stress and earthquake resistance.

[Background of the invention]

As shown in FIG. 1, a surface running track 1 is arranged surrounding a cylindrical reactor pressure vessel 9, and a vertical track 3 and a circumferential track 2 are arranged along the fuselage weld line of the reactor pressure vessel 9. have. Supports 5 and 7 are connected to the vertical track 3 and the circumferential track 2 to hold them, and the vertical track 3 and the circumferential track 2 are supported by a bracket 6 as a support means and a surface running track 1 having a steady rest structure. When the fuselage welding line inspection device running on the surface running track 1 can be placed on the reactor pressure vessel 9, the surface running track 1 and the reactor pressure vessel 9 should be You need to adjust the spacing. Since this adjustment was made for each plant and was considered fixed, there was an unavoidable drawback that the above-mentioned inspection equipment was shared by two or more plants. Furthermore, there were also disadvantages in that the measures to reduce thermal stress of the surface running track 1 and the earthquake resistance were insufficient.

That is, on the outer circumferential side of the surface traveling track 1 which is disposed surrounding the reactor pressure vessel 9, a γ shield 11 is disposed with a heat insulating material 10 interposed therebetween and at an appropriate interval. or,
A traveling device is provided on the vertical track 3 and the circumferential track 2 along which an inspection device, which will be described in detail later, travels.

Further, a turntable 4 is disposed at the intersection of the vertical track 3 and the circumferential track 2. This turntable 4 is for changing the direction of the inspection device, whereby the inspection device is changed from the longitudinal track 3 to the circumferential track or vice versa.

The support means is constituted by the bracket 6 and the steady rest 8 as described above, and the bracket 6 engages with the upper end side of the vertical track 3, extends toward the γ shield 11 side, and is locked thereto. By this bracket 1-6, the surface running track 1 retains its own weight on the γ shield. Further, the steady rest 8 has one end engaged with the support 5 provided across the circumferential track 2, and the other end fixedly supported by the r-shield 11.

As described above, since the surface running track 1 is formed in a fixed structure, the distance between the outer periphery of the reactor pressure vessel 9 and the surface running track 1 is constant. On the other hand, since an inspection device for inspecting the fuselage weld line of the reactor pressure vessel 9 is inserted within this interval, the above-mentioned interval is set so that the inspection device can run at its best and accurate inspection can be carried out. It is necessary to form. Therefore, the above-mentioned distance between the reactor pressure vessel 9 and the surface running trackwork in one plant is 1.
In many cases, the inspection equipment is different, and therefore, there is a drawback that one inspection device cannot be shared by two or more plants.

In addition, even if they are temporarily shared, there is a drawback that it takes time to make adjustments. Furthermore, as shown in the figure, since the steady rest 8 has a fixed structure, it cannot effectively absorb thermal changes in the surface running track 1, resulting in thermal stress. The drawback was that there was no way to prevent it.

[Purpose of the invention]

The present invention has been devised to solve the above-mentioned drawbacks, and its purpose is to easily share inspection equipment in two or more plants, and to create a reactor pressure vessel with reduced thermal stress and excellent seismic resistance. The object of the present invention is to provide a surface running track.

[Summary of the invention]

In order to achieve the above object, the present invention divides the orbit consisting of a longitudinal orbit and a circumferential orbit, and makes each divided orbit adjacent to the outer periphery of a reactor pressure vessel with an appropriate gap between them. At the same time, a bracket is provided to hold the weight of each divided track in the γ shield arranged surrounding the track, and a bracket is installed between the γ shield and the track to reduce the reactor pressure. A support means is provided, which includes a steady rest that is extendable in the radial direction of the container, and a support section that is formed within the steady rest and supports the track movably in the vertical and radial directions. It features a track for running on the surface of the reactor pressure vessel.

[Embodiments of the invention]

Embodiments of the present invention will be described below based on the drawings.

First, the present invention will be explained in detail.

As shown in FIG. 2, the orbit is divided into two, forming orbits 1a and 1b. Supports 5 are provided at the remaining portions of the orbits la and lbO. Further, the vertical track 3 is arranged in parallel with the support 5, and the circumferential track is the upper circumferential track 2a, 2b.

The vertical track 3 is composed of lower tracks 2a' and 2b'.
and the support 5. Also, upper circumferential orbits 2a, 2b and lower circumferential orbit 2a'.

Supports 7 are installed between 2b and 7, respectively.

The tracks 1a and 1b having the above configuration are arranged adjacent to each other on the outer peripheral side of the reactor pressure vessel 9 with an appropriate gap maintained therebetween. On the other hand, the supporting means are a bracket 6, steady rests 8, 1
2! 7, and a support portion 18 is formed within the steady rest device 8°12 as shown in FIG. Bracket 6
is for holding the weight of the tracks 1a and lb on the γ shield 11, and the steady rests 8 and 12 installed astride between the support 5 or 7 and the γ shield 11 are slidably engaged in the block 20. The track 1a is attached to the steady rest bracket 8c.

1b is supported so as to be expandable and retractable in the radial direction of the reactor pressure vessel 9. Further, the support portion 18 is formed of a link mechanism 8a, and supports the tracks 1a, lb so as to be movable in the vertical direction and the above-mentioned radial direction.

With the above configuration, the track 1a is divided into p1 by adjusting the radial direction of the steady rests 8 and 12.

1b and the outer periphery of the reactor pressure vessel 9 can be adjusted to an appropriate dimension. Therefore, it becomes possible to share the above inspection device. Further, thermal changes in the tracks 1a and lb are absorbed by the link mechanism 8a of the support portion 18 of the support means, and no undue thermal stress is generated. Furthermore, in the event of an earthquake, since the spring 13 of the link mechanism 8a of the support section 18 is elastically supported in the vertical and radial directions and fixed in the circumferential direction, this vibration can be effectively suppressed. Can be done. As described above, the inspection equipment can be shared by two or more plants, and the effects of reducing thermal stress and improving earthquake resistance can be achieved.

Next, this embodiment will be explained in more detail.

As shown in FIG. 2, the track 1 in FIG. 1 is divided into two near the turntable 4 into tracks 1a and 1b. Supports 5 are erected at the divided locations. A bracket 6 serving as a supporting means is provided on the upper end side of the support 5 and the vertical track 3 arranged in parallel therewith. Platan I-6 is γ shield 1
A support base i1 extending to the 1 side and formed on the γ shield 11
Supported by c. Although not illustrated, bracket 6
may be formed so that it can be attached to the support stand 11C.

As mentioned above, the circumferential tracks intersecting the vertical track 3 and the support 5 are the upper circumferential tracks 2a, 2b and the lower circumferential tracks 2a', 2.
A support 7 is provided between the orbits b' and 2a, between the orbits 2a and 2a, and between the orbits 2b and 2b'. Further, a steady rest 8, which is one of the supporting means, is provided astride between the supports 5 and 7 and the γ shield 11. Further, on the lower side of the vertical track 3, a steady rest 12 is provided which is similarly installed across the vertical track 3 and the γ shield 11. This steady rest 8°12
Therefore, the orbits 1a and lb are supported by the γ shield 11.

Next, the structures of the steady rests 8 and 12 of the support means and the support portion 18 formed therein will be explained.

A support stand 11d protruding from the inner circumferential side of the γ shield 11
A block 20 is placed on top. One end side of the steady rest bracket 8C is slidably inserted into this block 20, and fixed with a set screw 19 at an appropriate position. A stopper 8b is provided on the other end side of the steady rest bracket 8C via a support portion 18, and the stopper 8b is fixed to the support 7 (also below the support 5 and the vertical track 3).

With the above configuration, by expanding and contracting the steady rest bracket 8C in its longitudinal direction (radial direction of the reactor pressure vessel), the reactor pressure vessel 9 and the track 1a can be fixed.

The gap between lbs can be adjusted freely. Note that, as a matter of course, a through hole loc is formed in the heat insulating material 10 interposed between the γ shield 11 and the support 7, through which the steady rest platen 8C passes.

Next, the support portion 18 includes a link mechanism 8a and a link mechanism 8a.
It is formed from a spring 13 that is installed astride a.

As shown, the link mechanism 8a is formed from parallel links and is configured to be displaceable in the longitudinal and radial directions. Therefore, even if the steady rest bracket 8C is fixed at a fixed position, the track 1a.

1b becomes movable longitudinally and radially.

Further, the spring 13 is used to elastically support the above-mentioned vertical and radial movement.

As described above, the support means elastically supports the tracks 1a and lb in the longitudinal and radial directions, but is fixed in the circumferential direction. This restricts movement in the circumferential direction, and orbit 1a
, prevents lateral vibration of lb.

In addition, by providing another support part (not shown) between the block 20 and the support part 18, forming the support part 18 into a link mechanism, and arranging it perpendicularly to the support part 18, it is possible to It is also possible to provide elastic support.

Next, vertical orbit 3 and circumferential orbit 2a of orbit 1a and lb.

An inspection device that runs on 2a', 2b, and 2b' will be explained.

As shown in FIG. 4, on the surface of the vertical track 3 facing the reactor pressure vessel 9, an elongated running portion 14 protrudes from the end of the vertical track 3.
is attached, and a traveling device 15 is vertically slidably inserted onto the traveling section 14 by means of holding rollers 15a. The traveling device 15 is configured to be able to move up and down (by a pinion (not shown) that meshes with a rack 14a provided on the traveling portion 14).

A probe 16 that is an inspection device that moves on the holding arm 17 is provided on the traveling device 15 via a holding arm 17 . The probe 16 detects the welding state of the fuselage weld line of the reactor pressure vessel 9, and is connected to a detection device (not shown). Further, since the holding arm 17 is provided perpendicularly to the running portion 14, the probe 16 is supported so as to be movable up and down and in directions perpendicular thereto.

FIG. 5 shows a state in which the direction of the inspection apparatus having the above-mentioned structure is changed in the direction perpendicular to the turntable 4 (circumferential direction). Therefore, the probe 16 can move in the circumferential direction along the circumferential orbit 2a and the like, and can also move in the vertical direction. or,
A protrusion 15b is formed on the traveling device 15, and the protrusion 15
By providing the holding arm 17 at the b end, it is possible to inspect the gap in the circumferential direction between the divided tracks 1a and 1b.Example: The above-mentioned inspection device can inspect the longitudinal track 3 and the circumferential track of the tracks 1a and lb. The probe 16 is inserted into the gap between the reactor pressure vessel 9 and the reactor pressure vessel 9, and the welded joint is inspected by the probe 16.

Therefore, the above-mentioned gap can be adjusted to a size that allows the probe 16 to run smoothly and allows accurate welding inspection. Note that the trajectory 1a of the inspection device.

Attachment and detachment to and from the heat insulator io and r shield 11 are carried out through holes 10a formed above and below.

10b, lla, and llb.

Next, the functions and effects of this embodiment will be explained.

Tracks 1a and lb are arranged adjacent to each other at opposite positions on the outer circumferential side of the reactor pressure vessel 9, and are suspended by the brackets 6, and are secured to the outer circumference of the reactor pressure vessel 9 with appropriate gaps by the steady rests A8 and 12. Install it in a position that has the following characteristics. Next, the steady rest bracket 8C is expanded and contracted, and the tracks 1a and 1b are moved independently to form a predetermined gap, and at that position, the steady rest platen 8C is fixed to the setscrew 19.
Fix it in place.

Next, the probe 16 of the inspection device is inserted through the holes 10a and lla.
etc., and attach it to the running section 14 of the vertical track 3 etc. This allows the probe 16 to be set at an accurate position. or,
This set-up, as described above, is very easy to perform.

Share common inspection equipment with other plants' track 1a.

1b, a highly accurate set can be achieved by carrying out the same procedure as described above.

On the other hand, in Fig. 2, if the heights of the brackets 6 are made equal from the circumferential tracks 2a and 2b, during thermal deformation, the lower parts of the circumferential tracks 2a and 2b will be displaced while maintaining the same relative position, and the steady rest Thermal stress is absorbed by the action of the 8,120 link mechanism 8a. Therefore, unlike the prior art, unreasonable thermal stress does not occur. In addition, in case of earthquake etc., orbit 1a, lb
Even if it vibrates, the steady rests 8 and 12 elastically support it in the vertical and radial directions, and restrain movement in the circumferential direction, making it possible to suppress the vibration. Note that by providing another support portion in the circumferential direction as described above, it is also possible to elastically support the circumferential direction and damp vibration. This makes it possible to improve earthquake resistance.

In this embodiment, the expansion and contraction structure of the steady rest 8c is not limited to the above-mentioned structure, and a screw mechanism, an electric mechanism, or a hydraulic pressure mechanism may be used. Also, a spring 1 is attached to the link mechanism 8a.
In addition to 3, a damper may also be used. Moreover, the support part 18
is not limited to parallel links.

〔Effect of the invention〕

As is clear from the above explanation, according to the present invention, two
Inspection equipment can be shared by the above plants, and the effects of reducing thermal stress and improving earthquake resistance can be achieved.

[Brief explanation of the drawing]

Fig. 1 is an explanatory diagram showing the structure of a conventional surface running track of a reactor pressure vessel and its support means, Fig. 2 is an explanatory diagram of an embodiment of the present invention, and Fig. 3 is a detailed diagram of the track support means. FIGS. 4 and 5 are explanatory diagrams showing a method of supporting an inspection device running on a track and its configuration. ■...Surface running track, la, lb...orbit, 2゜2a, 2a', 2b, 2b'-peripheral orbit, 3...
・Vertical track, 4... Turntable, 5, 7... Support, 6... Platinum), 8. '12... Steady rest, 8a... Link mechanism, 8b... Clasp, 8C.
・Bracket for steady rest, 9 ・Reactor pressure vessel,
10... Heat insulation material, 10a, 10b, lla, 1lb-
Hole, 10 C... Through hole, 11... γ shield, I
IC, lid...support stand, 13...spring, 14...
- Traveling section, ], 4a... Rack, -15... Traveling device, 15a... Holding roller, 15b Funeral Figure 3//.

Claims (1)

[Claims] 1. A track that surrounds the cylindrical reactor pressure vessel and has a vertical track and a circumferential track along the fuselage weld line, and a track that is provided at the intersection of the vertical track and the circumferential track, and that runs on the track. An atom having a turntable for changing the direction of an inspection device for inspecting the fuselage weld line, and support means for supporting the orbit on a γ shield disposed surrounding the orbit at an appropriate interval. In the surface running track of the reactor pressure vessel, the track is divided vertically, and each of the divided tracks is arranged adjacent to the outer periphery of the reactor pressure vessel with an appropriate gap between them. At the same time, the support means includes a bracket that allows the γ shield to hold the weight of each of the divided tracks, and a bracket that is installed astride between the γ shield and the track, and is expandable and retractable in the radial direction of the reactor pressure vessel. 1. A track for running on the surface of a nuclear reactor pressure vessel, characterized in that it is formed of a steady rest formed to adjust the movement thereof, and a support portion movably supported in the radial direction.