JP2005308624A - Nuclear reactor facility - Google Patents

Abstract

<P>PROBLEM TO BE SOLVED: To propose a nuclear reactor facility capable of fully securing safety in carrying out a nuclear reactor pressure vessel. <P>SOLUTION: In this nuclear reactor facility 1 having a reactor building 2 wherein a portal crane 13 hoisting up the nuclear reactor pressure vessel 4 is structured so as to be able to run on an operation floor 11, a first opening part 42 to which the portal crane 13 can pass through and having a first airtight door 41 is formed on a part of a side wall 2a arranged on an equipment pool 7 side of the operation floor 11. <P>COPYRIGHT: (C)2006,JPO&NCIPI

Description

  The present invention relates to a method for carrying out a reactor pressure vessel installed in a reactor building from a reactor building.

The nuclear power plant can extend the life of the nuclear power plant by extending the reactor pressure vessel. With regard to carrying out the reactor pressure vessel from the reactor building and carrying it into the reactor building, a method has been proposed in which an opening is provided on the roof of the reactor building and the reactor pressure vessel is carried out and carried in through this opening. (See Patent Document 1).
Also, the reactor pressure vessel placed outside the reactor building is lifted and transported in a lying state, and the reactor is raised in the reverse order to the method of raising the pressure vessel above the opening of the containment vessel and carrying it into the containment vessel. A method for carrying out the pressure vessel to the outside of the reactor building has been proposed (see Patent Document 2).
JP 2003-215294 A JP-A-57-151892

However, in the former technique, since a vertically long reactor pressure vessel is carried in and out while standing, it is necessary to provide a huge gate-type support structure that straddles the reactor building. In addition, it is necessary to take measures in the building so that it does not fall to the spent fuel pool side when the reactor pressure vessel is suspended. There is a problem.
On the other hand, in the latter technique, the procedure for lifting and loading the reactor pressure vessel in a lying state is shown, but for the specific reactor equipment configuration required to carry out the reactor pressure vessel, Not proposed. That is, when carrying out the reactor pressure vessel, it is necessary to prevent the radioactive material from being scattered to the outside, so it is sufficiently safe to carry out the reactor pressure vessel in the reverse procedure of the loading method. There is a problem that it cannot be secured.

  The present invention has been made in view of the above-described circumstances. In a nuclear reactor facility having a reactor building in which a portal crane that lifts a reactor pressure vessel is configured to be able to travel on an operation floor, The purpose is to propose a nuclear reactor facility that can ensure the safety of unloading.

In the nuclear reactor facility according to the present invention, the following means are adopted in order to solve the above problems.
The present invention is a reactor facility having a reactor building in which a portal crane that lifts a reactor pressure vessel is configured to be able to travel on the operation floor, in a part of the side wall disposed on the equipment pool side of the operation floor, A portal crane can be passed, and a first opening having a first hermetic door is provided. According to this invention, when the reactor pressure vessel is carried out, the reactor pressure vessel is transported away from the spent fuel pool, so that the reactor pressure vessel is prevented from falling into the spent fuel pool. can do. Moreover, since the 1st airtight door was provided in the 1st opening part which a portal crane passes, the external discharge | release of a radioactive substance can be prevented.

In addition, if an accessory building that can raise or lower the reactor pressure vessel from the ground floor to the operation floor is connected to the first opening directly or via a crossing passage, a portal crane that lifts the reactor pressure vessel can be easily used. It can be carried outside the reactor building.
In addition, when the reactor pressure vessel can pass through the ground floor of the annex building and a second opening having a second hermetic door that does not open simultaneously with the first hermetic door is provided, the first opening And the second opening are not opened at the same time, the interior of the building can be reliably maintained at a negative pressure, and the release of radioactive material can be prevented.
In addition, in the case where a traversing mechanism for laterally moving the portal crane is provided in the crossing passage, the restriction on the arrangement of the attached building is reduced, and therefore, for example, a plurality of reactor buildings can be connected to one attached building. Thereby, the equipment cost of a nuclear reactor facility can be held down.
In addition, when the attached building has an equipment storage area for storing equipment to be removed from the reactor well or from the reactor pressure vessel when the reactor pressure vessel is carried out, it can be accessed from the reactor well or from the reactor pressure vessel. Since the equipment to be removed is accommodated in the equipment accommodating area so as not to obstruct the work for carrying out the reactor pressure vessel, the safety of the work for carrying out the reactor pressure vessel can be ensured.
Further, in the case where the device storage area has a plurality of layers for storing the devices so as to be stacked in the order in which the devices are removed from the reactor well or the reactor pressure vessel, for example, the space between the reactor building and the attached building Can be used effectively.
In addition, when the floor of the hierarchy is configured to be openable and closable, the equipment removed from the reactor well or the reactor pressure vessel can be easily stacked by closing the floor sequentially from the lower floor. be able to.

According to the present invention, the following effects can be obtained.
The present invention is a reactor facility having a reactor building in which a portal crane that lifts a reactor pressure vessel is configured to be able to travel on the operation floor, in a part of the side wall disposed on the equipment pool side of the operation floor, A portal crane can be passed, and a first opening having a first hermetic door is provided. As a result, it is possible to prevent the reactor pressure vessel from falling into the spent fuel pool when the reactor pressure vessel is carried out, and to prevent the radioactive material from being released to the outside. Therefore, it is possible to reliably prevent the radioactive material from being released to the outside when the reactor pressure vessel is carried out, and to avoid internal exposure due to the radioactive material uptake by the surrounding residents.
In addition, since the attached building that can raise and lower the reactor pressure vessel from the ground floor to the operation floor is connected to the first opening directly or via a crossing passage, the reactor pressure vessel can be easily installed outdoors. Can be carried out to
In addition, since the reactor pressure vessel can pass through the ground floor of the annex building and a second opening having a second hermetic door that does not open at the same time as the first hermetic door is provided. The inside of the building can be maintained at a negative pressure, and the release of radioactive substances can be prevented.
In addition, since a traversing mechanism for laterally moving the portal crane is provided in the crossing passage, restrictions on the arrangement of the attached building are reduced, and the equipment cost of the reactor facility can be reduced.
In addition, since the attached building has an equipment storage area for storing equipment to be removed from the reactor well or the reactor pressure vessel when the reactor pressure vessel is carried out, the safety of carrying out the reactor pressure vessel is safe. Sex can be secured.
In addition, since the equipment storage area is provided with a plurality of layers for storing equipment in the order in which the equipment is removed from the reactor well or the reactor pressure vessel, the space available in the reactor facility is effectively used. be able to.
In addition, since the floor of the floor is configured to be openable and closable, equipment removed from the reactor well or the reactor pressure vessel can be easily accommodated.

Hereinafter, an embodiment of a nuclear reactor facility of the present invention will be described with reference to the drawings.
FIG. 1 is a longitudinal sectional view showing a configuration of a nuclear reactor facility 1 which is a part of a boiling water nuclear power plant (BWR plant).
The nuclear reactor facility 1 includes a nuclear reactor building 2, an attached building 20, and a crossing passage 30 that connects the nuclear reactor building 2 and the attached building 20.

The reactor building 2 is erected on the ground and includes a reactor containment vessel 3 (Primary Containment Vessel) inside.
The reactor containment vessel 3 is an important building for the safety of the reactor, and houses structures such as the reactor pressure vessel 4 and cooling system equipment. Generally, it is made of light bulb-shaped or bell-shaped steel or reinforced concrete and has an airtight and pressure-resistant structure, and radioactive materials are released to the outside in the event of an accident such as a reactor accident or damage to the reactor cooling system. It serves to prevent. In addition, in this embodiment, it forms in a bell shape.
The reactor pressure vessel 4 (Reactor Pressure Vessel) is a vertical cylindrical shape with a hemispherical top and bottom, and includes a reactor pressure vessel upper lid (RPV upper lid 53) and a reactor pressure vessel body 4b. The reactor pressure vessel 4 is installed on the pedestal 9 and is fixed by a foundation bolt and is self-supporting. Note that the pedestal 9 is a structure of concrete and a steel plate frame or a reinforcing bar because it serves as the foundation of the reactor pressure vessel 4.
A reactor shielding wall 5 for shielding radiation from the reactor is provided outside the reactor pressure vessel 4. The reactor shielding wall 5 is an iron plate frame concrete structure having a thickness of 600 to 700 mm.
The RPV upper lid 53, which is the upper lid of the reactor pressure vessel 4, is fixed to the flange 4c of the reactor pressure vessel body 4b by bolts. In addition, a nozzle such as a main steam outlet nozzle 80 is attached to the reactor pressure vessel 4 and is connected to piping outside the reactor pressure vessel 4.

  The upper part of the reactor containment vessel 3 is provided with shielding water that shields radiation from the fuel assembly or the like when the fuel assembly or the structure in the reactor pressure vessel 4 (both not shown) is exchanged or taken out. A reactor well 6 is provided. When exchanging the reactor pressure vessel 4, the reactor pressure vessel 4 is unloaded from the reactor well 6 and loaded.

FIG. 2 is a plan layout view of the operation floor 11 of the reactor building 2.
The operation floor 11 in the reactor building 2 includes a spent fuel pool 7 for storing used fuel assemblies and an equipment pool 8 for storing in-reactor structures taken out of the reactor. They are arranged symmetrically across the reactor well 6. The spent fuel pool 7 is filled with water to shield radiation from the spent fuel assembly.

A traveling rail 12 is laid on the operation floor 11 so as to straddle the reactor well 6, the spent fuel pool 7, and the equipment pool 8. A portal crane 13 that suspends and conveys the reactor pressure vessel 4 is placed on the traveling rail 12.
A first opening 41 through which the portal crane 13 can pass is provided on the side wall 2a on the equipment pool 8 side of the reactor building 2, and a first hermetic door 42 is further provided in the first opening 41. . Thereby, it is prevented that a radioactive substance is discharged | emitted from the reactor building 2 outside at the time other than passage of the portal crane 13. FIG.

Returning to FIG. 1, the attached building 20 is connected to the reactor building 2 through the transfer passage 30. The attached building 20 is a facility used to carry out and carry in the reactor pressure vessel 4, and is erected at substantially the same height as the reactor building 2, and its inside is hollow.
The traveling rails 12 are also laid in the attached building 20 and the crossing passage 30. Therefore, the portal crane 13 can reciprocate through the passage 30 between the reactor building 2 and the attached building 20.
In addition, the ground floor 21 of the annex building 20 is provided with a second opening 43 through which a heavy goods transporting vehicle 22 (see FIG. 8) loaded with the reactor pressure vessel 4 can pass. A second hermetic door 44 is provided at 43. The second hermetic door 44 is interlocked so as not to be opened simultaneously with the first hermetic door 42. Thereby, when the reactor pressure vessel 4 is carried out, the inside of the reactor building 2 can be maintained at a negative pressure, and the radioactive substance is prevented from being released to the outside.

In the space between the reactor building 2 and the annex building 20 below the floor of the transfer passage 30 that connects the reactor building 2 and the annex building 20, in other words, the reactor well 6 A device storage area 60 is provided to store the device 50 to be removed from the inside or the reactor pressure vessel 4, for example, the PCV top head 51, the RPV upper lid heat insulating material 52, the RPV upper lid 53 and the like. Normally, these devices 50 are temporarily placed on the operation floor 11 of the reactor building 2, but there are not a few cases where these devices 50 get in the way when the reactor pressure vessel 4 is carried out. For this reason, the safety | security of carrying out work may be impaired. Therefore, by storing these devices 50 in the device storage area 60, the safety of the unloading work is ensured.
The device storage area 60 includes a plurality of levels 61. The floor surface 62 of each floor 61 is configured to be openable and closable. That is, by closing the floor surface 62 of each level 61, a plurality of devices 50 removed from the reactor well 6 or the reactor pressure vessel 4 can be accommodated so as to be stacked.

FIG. 3 is a view showing the crossing passage 30 and the traversing mechanism 31. As shown in FIG. 3A, a traversing mechanism 31 that moves the portal crane 13 laterally may be installed in the crossing passage 30. Thereby, in order to lay the linear running rail 12, the position of the reactor building 2 and the attached building 20 needs to be in a predetermined relationship (the attached building 20 is constructed on the side wall 2a side of the reactor building 2). Disappear.
That is, by providing the traversing mechanism 31 in the crossing passage 30, the portal crane 13 can be laterally moved in the direction intersecting the traveling rail 12. In other words, as shown in FIG. 3 (b), even if the positional relationship between the reactor building 2 and the attached building 20 is arbitrarily selected, the portal crane 13 is connected between the reactor building 2 and the attached building 20. It can be reciprocated.
Further, for example, it is possible to construct so that one attached building 20 is connected to a plurality of reactor buildings 2, and the equipment cost of the reactor facility 1 can be suppressed.

Next, replacement work of the reactor pressure vessel 4 will be described with reference to FIGS.
First, prior to carrying out the reactor pressure vessel, disassembly and reactor pressure vessel peripheral disassembly are performed.
In the disconnection process, the PCV top head 51, the RPV upper lid heat insulating material 52, the RPV upper lid 53, and the like are removed from the reactor well 6 or the reactor pressure vessel 4.
As shown in FIG. 4, these devices are accommodated from the lower floor of the device accommodating region 60 in the order of removal from the reactor well 6 or the reactor pressure vessel 4. Specifically, the floor surface 62 other than the lowest floor in the device accommodation area 60 is opened, and the PCV top head 51 is accommodated in the lowest hierarchy 61. Next, the floor surface 62 immediately above the lowest floor 61 is closed to accommodate the RPV upper lid heat insulating material 52. Similarly, the RPV upper lid 53 and the like are accommodated so as to be stacked on the uppermost layer 61.

  Subsequently, the reactor well 6 and the equipment pool 8 are filled with water, and the in-furnace structures such as the steam dryer and the shroud head are removed from the furnace and transferred to the equipment pool 8. Next, the pool gate of the spent fuel pool 7 is opened, the fuel assembly is taken out from the furnace, and transferred to the spent fuel pool 7.

Next, in the reactor pressure vessel peripheral dismantling process, all the internal structures (all not shown) such as the control rod, control rod guide tube, control rod drive mechanism and neutron flux measurement monitor are removed. Furthermore, piping and support structures connected to the reactor pressure vessel 4 are removed.
Before and after this, the suspension pins 71 and 72 are attached to the reactor pressure vessel 4 (see FIG. 5). A plurality of suspension pins 71 and 72 are provided above and below the center of gravity of the reactor pressure vessel 4. As a result, the reactor pressure vessel 4 can be laid down while being lifted by the portal crane 13.
A shielding lid 70 is attached to the reactor pressure vessel 4. Then, the reactor pressure vessel 4 is separated from the reactor shielding wall 5.

Next, as shown in FIGS. 5, 6, and 7, the reactor pressure vessel 4 is unloaded.
First, the gate crane 13 is moved from the attached building 20 to the upper part of the reactor well 6. Then, the wire of the portal crane 13 is hung on the suspension pins 71 and 72 provided in the reactor pressure vessel 4. Subsequently, the reactor pressure vessel 4 is lifted and separated from the pedestal 9 (see FIG. 5).
When the reactor pressure vessel 4 is lifted to just below the portal crane 13, the reactor pressure vessel 4 becomes an interference (bulkhead opening, reactor well wall on the spent fuel pool 7 side, reactor building ceiling truss, etc.) In order not to collide, the portal crane 13 is gradually tilted toward the equipment pool 8 while moving (see FIG. 6).
Then, when the reactor pressure vessel 4 becomes substantially horizontal (side-down state) with respect to the operation floor 11, the portal crane 13 is caused to travel toward the attached building 20 (see FIG. 7).

Next, the first airtight door 42 of the first opening 41 is opened, and the portal crane 13 is passed through and moved to the crossing passage 30. The first hermetic door 42 is closed immediately after passing through the portal crane 13 to prevent the radioactive material from diffusing out of the reactor building 2.
When the transfer passage 30 is not linear, the portal crane 13 is moved laterally by driving the traversing mechanism 31 provided in the transfer passage 30, and the reactor pressure vessel 4 is transported to the attached building 20. .
Then, as shown in FIG. 8, when the reactor pressure vessel 4 is moved to the attached building 20, the wire is extended again, and the reactor pressure vessel 4 is hung down to the ground floor 21 while lying down.
At this time, on the ground floor 21 of the annex building 20, the heavy material transporting vehicle 22 is put on standby and the suspended reactor pressure vessel 4 is mounted.
Then, the wire is removed, and the heavy goods transporting vehicle 22 loaded with the reactor pressure vessel 4 is moved out of the attached building 20 through the second opening 43. The second hermetic door 44 provided in the second opening 43 is interlocked so as not to be opened at the same time as the first hermetic door 42. Is further prevented.

  After the reactor pressure vessel 4 is carried out in this way, the work of the inner surface of the reactor shielding wall, the introduction of a new reactor pressure vessel, the restoration of the periphery of the reactor pressure vessel, and the fuel reloading are performed. Replacement of the container 4 is completed.

As described above, according to the present invention, when the reactor pressure vessel 4 is carried out, the reactor pressure vessel 4 is transported away from the spent fuel pool 7, so that the reactor pressure vessel 4 is used. It can prevent falling to the fuel pool 7 beforehand.
Moreover, since the 1st airtight door 42 was provided in the 1st opening part 41 through which the portal crane 13 passes, the discharge | release of a radioactive substance outside can be prevented. Therefore, it is possible to reliably prevent the radioactive substance from being released to the outside when the reactor pressure vessel 4 is carried out, and to avoid internal exposure due to the radioactive substance uptake by the surrounding residents.

  It should be noted that the present invention is not limited to the above-described embodiment, and various modifications can be made without departing from the scope of the present invention.

Longitudinal sectional view showing the configuration of nuclear reactor facility 1 Plan view of the operation floor 11 of the reactor building 2 The figure which shows the crossing passage 30 and the traversing mechanism 31 The figure explaining the exchange work of the reactor pressure vessel 4 Replacement work diagram following FIG. Replacement work diagram following FIG. Replacement work diagram following FIG. Replacement work diagram following FIG.

Explanation of symbols

DESCRIPTION OF SYMBOLS 1 Reactor facility 2 Reactor building 2a Side wall 4 Reactor pressure vessel 6 Reactor well 8 Equipment pool 11 Operation floor 13 Gate type crane 20 Attached building 21 Ground floor 30 Crossing passage 31 Traversing mechanism 41 1st opening part 42 1st airtightness Door 43 Second opening 44 Second hermetic door 50 Equipment 60 Equipment accommodation area 61 Level 62 Floor

Claims (7)

In a reactor facility having a reactor building in which a portal crane that lifts a reactor pressure vessel is configured to be able to travel on the operation floor,
A nuclear reactor facility characterized in that a part of a side wall disposed on the equipment pool side of the operation floor is provided with a first opening portion through which the gate crane can pass and a first hermetic door.   2. The nuclear reactor facility according to claim 1, wherein an accessory building capable of raising and lowering the reactor pressure vessel from the ground floor to the operation floor is connected to the first opening directly or via a crossing passage. .   The second floor having a second hermetic door that does not open at the same time as the first hermetic door is provided on the ground floor of the annex building, and the reactor pressure vessel can pass therethrough. Item 3. Reactor facility according to item 2.   The nuclear reactor facility according to claim 2 or 3, wherein a traverse mechanism for moving the portal crane laterally is provided in the transfer passage.   5. The apparatus according to claim 2, wherein the attached building has a device storage area for storing a device to be removed from the reactor well or the reactor pressure vessel when the reactor pressure vessel is carried out. The nuclear reactor facility described in any one of them.   6. The nuclear reactor facility according to claim 5, wherein the equipment storage area includes a plurality of layers for storing the equipment in a stacked order in the order of removal from the reactor well or the reactor pressure vessel. . The nuclear facility according to claim 6, wherein the floor surface of the hierarchy is configured to be openable and closable.

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