JPS62165184A - Heat insulator for pressure vessel of nuclear reactor - 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 [Technical Field of the Invention] The present invention relates to a nuclear reactor pressure vessel moisturizing device, and more particularly to a nuclear reactor pressure vessel warming device that can improve heat retention.

(Technical background of the invention and its problems) Generally, nuclear reactor pressure vessels are operated at high temperatures during their service life. For this reason, a reactor pressure vessel heat retention device is provided on the outer periphery of the reactor pressure vessel in order to prevent heat loss in the reactor pressure vessel, increase output efficiency, and isolate heat from the outside.

Incidentally, it is necessary to inspect the welded parts of the reactor pressure vessel from the outside using a remote automatic inspection device before and during the service period. For this reason, it is necessary to provide a space between the reactor pressure vessel and the reactor pressure vessel heat retention device that is sufficient to allow the remote automatic inspection device to move.

However, in the conventional reactor pressure vessel thermal insulation device, this interval is not limited only to the parts corresponding to the welded parts of the reactor pressure vessel.
Since they are uniformly provided around the entire circumference of the reactor pressure vessel, there is a problem of poor heat retention.

In addition, in conventional reactor pressure vessel thermal insulation devices, the frontage section for attaching the remote automatic inspection device from the outside to the track provided along the welded part of the reactor pressure vessel is split, so the remote automatic inspection device There is also the problem that inspectors approaching the station to install it on the track will be exposed to a large amount of radiation.

[Purpose of the invention]

The present invention has been made in consideration of these points, and an object of the present invention is to provide a reactor pressure vessel heat retention device that can enhance the heat retention of the reactor pressure vessel and improve the output efficiency.

[Summary of the invention]

The present invention provides remote automatic inspection by arranging a heat insulating material close to the outer peripheral surface of the reactor pressure vessel, and bending the part of the heat insulating material corresponding to the welded part of the reactor pressure vessel toward the outer diameter side. A device mounting section for mounting the device is provided, a track for moving the remote automatic inspection device is installed on the inner wall surface of this device mounting section, and the remote automatic inspection device is placed on the orbit at the required position of the device mounting section. The present invention is characterized in that an opening/closing part is provided for attachment to the reactor pressure vessel, thereby making it possible to bring the heat insulating material as close to the reactor pressure vessel as possible to avoid improving heat retention.

Example of invention C] An embodiment of the present invention will be described below with reference to the drawings.

In Figures 1 to 3, reference numeral 1 indicates a reactor pressure vessel, and the outer periphery of the reactor pressure vessel 1 is designed to prevent heat loss of the reactor pressure vessel 1, increase output efficiency, and communicate with the outside. Reactor pressure vessel heat retention device 2 for thermal isolation
has been set up.

As shown in FIGS. 1 to 3, this reactor pressure vessel heat insulating device 2 includes a heat insulating part 3 provided close to the outer peripheral surface of the reactor pressure vessel 1, and a welded part of the reactor pressure vessel 1. The device mounting portion 4 is provided with a device mounting portion 4 installed at a location corresponding to 1a, and the device mounting portion 4 is bent in a square groove shape toward the outer diameter side from the heat retention portion 3 as shown in FIGS. 1 and 3. It has a cross-sectional shape.

As shown in FIG. 3, a remote automatic inspection device 5 such as an ultrasonic detector is placed on the inner wall surface of the device mounting portion 4. l1
A track 6 has been installed for the remote automatic inspection 'IA purchase 5 to move on the track 6 in the Y-axis direction indicated by the double-headed arrow in Fig. 3 by engaging the rack and pinion. It has become.

This remote automatic inspection device 5 includes the Y
It is equipped with a probe drive mechanism 7 that is driven in the X-axis direction perpendicular to the l1l11 direction to inspect the welded part 1a of the reactor pressure vessel 1, and has a square groove shape. is set to a value that does not interfere with the movement of the probe drive mechanism 7 in the X-axis direction.

As shown in FIGS. 1 and 2, a remote automatic inspection device 5 is installed at a required position of the device mounting portion 4 configured like a mouth.
A closing part 8 for attaching the device to the rail 1ffi 6 from the outside of the device attaching part 4 is pulled in a required number of steps.

Each of these opening/closing parts 8 has a square lid shape that opens and closes an opening 9 provided in the track 6 laying part of the device receptacle part 4, as shown in FIGS. 1, 4, and 5. An auxiliary track 10 that is connected to the track 6 to form an integrated track when the opening/closing part 8 is closed is provided on the inner wall surface thereof.

Further, at the lower end of this opening/closing part 8, as shown in FIG.
Wheels 13 that roll on the top are provided, and the opening/closing part 8 is
By grasping the handle 14 provided on the outer surface and pulling outward, it can be easily pulled out along the rail 12 toward the R8W11 side. The opening/closing section 8 also includes a remote automatic inspection device 5 located within the device mounting section 4 and an external control device, as shown in FIGS. 4 and 5. A through-hole 15 is provided for pulling out a cable (not shown) connecting the cable (not shown), and this through-hole 15 is normally closed by a closing flange 16 as shown in FIG. ing.

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

When attaching the remote automatic inspection device 5 to the track 6, first pull out the opening/closing part 8 along the rail 12 to the R8WI I side,
11, and attach the remote automatic inspection device 5 to the auxiliary 1'/l path 10 on the inner wall surface of the ff18.

Next, the closing flange 16 is removed, and a cable (not shown) from the remote automatic inspection device 5 is drawn out through the through hole 15 and connected to a control device (not shown).

Next, the opening/closing part 8 is moved along the rail 12 to the reactor pressure volume F.
Move it to the f1 side and close the opening 9.

Thereafter, the remote automatic inspection device 5 is driven to move to the track 6 by the control.

In this way, since the reactor pressure vessel heat retention device 2 is close to the outer peripheral surface of the reactor pressure vessel 1 except for the part corresponding to the welded part 1a of the reactor pressure vessel 1, compared to the conventional one, Heat retention can be improved.

Furthermore, since an auxiliary track 10 is provided on the inner wall surface of the opening/closing part 8 and is connected to the track 6 to form an integrated track, the remote automatic inspection device 5 can be moved independently of the auxiliary track 10. Therefore, it can be easily moved onto the orbit 6. Therefore, the amount of radiation exposure of the inspection tool when attaching the remote automatic inspection device 5 to the track 6 can be reduced.

In addition, since the n'd closed δl (8) has a structure that slides along the rail 12, it is easy to open and close, and the amount of radiation exposure of the inspector can be further reduced.

In the above embodiment, the opening/closing section 8 slides along the rail 12, but the same effect can be expected even if the opening/closing section 8 is opened/closed with the - side as an axis.

〔Effect of the invention〕

As explained above, in the present invention, the heat insulating material is kept away from the outer periphery of the reactor pressure vessel except for the parts corresponding to the welded parts of the reactor pressure vessel, so that the heat insulating material is improved and In addition, a device mounting part with a track is provided at the part corresponding to the welded part of the reactor pressure vessel, and a remote automatic inspection device is attached to the track in this device mounting part. Since an opening/closing section is provided for the inspection, inspections using a remote automatic inspection device before and during the in-service period can be carried out in the same way as in the past.

[Brief explanation of drawings]

FIG. 1 is a perspective view of the main parts of the reactor pressure vessel heat insulating device according to the present invention as seen from the outside, FIG. 2 is a similar exploded view, and FIG. 3 is the reactor pressure vessel heat insulating device seen from the inside. FIG. 4 is a perspective view of the opening/closing part seen from the inside, and FIG. 5 is a partial sectional view without showing the structure around the opening/closing part. 1... Reactor pressure vessel, 1a... Welded part, 2...
Reactor pressure vessel heat retention device, 3... Heat retention part, 4... Device mounting part, 5... Remote automatic inspection device, 6... υ
l road, 8... opening/closing part, 10... auxiliary track, 12...
・Rail, 13...jI port, 15...81 through hole, 1
6... Closing flange. Applicant's agent 4ji Fujio Figure 4

Claims (1)

[Claims] Remote automatic inspection is performed by arranging a heat insulating material close to the outer peripheral surface of the reactor pressure vessel, and bending the part of the heat insulating material corresponding to the welded part of the reactor pressure vessel toward the outer diameter side. A device mounting portion for mounting the device is provided, a track for moving the remote automatic inspection device is attached to the inner wall surface of the device mounting portion, and the remote automatic inspection device is mounted at a required position of the device mounting portion. A nuclear reactor pressure vessel heat retention device characterized by having an opening/closing part for installation on a track. 2. The reactor pressure vessel heat retention device according to claim 1, wherein an auxiliary track connected to the track is provided on the inner wall surface of the opening/closing part.