JPH0672091U - Containment vessel - Google Patents

Abstract

(57) [Summary] [Purpose] To provide a reactor containment vessel capable of effectively protecting a water supply pipe attached to a pressure suppression pool of the reactor containment vessel from vibration of cooling water and enhancing its durability. [Structure] A pressure suppression chamber 4 forming a pressure suppression pool 4a on an outer peripheral portion of a pedestal 3 supporting a reactor pressure vessel 2.
In the reactor containment vessel in which the vent pipe 7 is opened in the pressure suppression pool 4a, a partition wall 18 is provided in the pressure suppression chamber 4 to partition the pressure suppression pool 4a and the water tank 17, A drainage pipe 6 for draining cooling water is provided on the suppression pool 4a side, and a water supply pipe 5 for supplying cooling water is provided on the water tank 17 side.

Description

[Detailed description of the device]

[0001]

[Industrial applications]

 The present invention relates to a reactor containment vessel, and more particularly to improvement of a pressure suppression chamber formed in the reactor containment vessel.

[0002]

[Prior art]

 The reactor containment vessel used in a nuclear power plant has the structure shown in Fig. 3. As shown in the figure, the reactor containment vessel 1 has a building-integrated structure divided by concrete shielding walls. The reactor containment vessel 1 is provided with a pedestal 3 for supporting the reactor pressure vessel 2, and a pressure suppression chamber 4 is provided around the pedestal 3 so as to surround the pedestal 3. This pressure suppression chamber 4 has a pressure suppression pool 4a in which the cooling water w is stored, and the high temperature and high pressure steam which is expected to be generated in the reactor containment vessel 1 due to an accident or the like is generated. Through the vent pipe 7, it guides into the cooling water w of the pressure suppression pool 4a and condenses to exert the function of suppressing the pressure in the upper dry well 14. The pressure suppression pool 4a is provided with a water supply pipe 5 and a drain pipe 6 for supplying / draining the cooling water w. An emergency core cooling system (ECCS) is branched and connected to the upstream side of the water supply pipe 5, and instead of actually injecting the core cooling water into the core during the periodic operation test, the pressure is supplied by using the water supply pipe 5. The test is carried out on the pump and the like by flowing it into the suppression pool 4a.

[0003]

[Problems to be solved by the device]

 By the way, the water supply pipe 5 provided in the pressure suppression pool 4a has a structure in which the water supply port 9 is exposed in the pressure suppression chamber 4 and the water supply port 9 is inserted into the pressure suppression pool 4a as shown in FIG. . As described above, since the water supply pipe 5 is configured so as to be exposed and inserted into the pressure suppression chamber 4, there are the following problems. When steam is introduced from the vent pipe 7 or the quencher 8, the high-temperature and high-pressure steam sharply raises the water level of the cooling water w in the pressure suppression pool 4a, and the bubble vibration generated in the process of condensation is cooled. It causes a violent pulsation in the water w.

As a result, the vibration load of the cooling water w is applied to the water supply pipe 5, and the vibration load is propagated to the support portion for supporting the water supply pipe 5 and the penetrating portion of the shielding wall, causing the water supply pipe 5 to break. It is expected that this may happen. Further, since the above-mentioned ECCS system pipe is connected to the upstream side of the water supply pipe 5, it is not preferable to directly transmit the vibration stress of the cooling water w to the water supply pipe 5.

Therefore, an object of the present invention is to provide a reactor containment vessel capable of protecting a water supply pipe attached to a pressure suppression pool of the reactor containment vessel from vibration of cooling water and enhancing its durability. To do.

[0006]

[Means for Solving the Problems]

 In order to achieve the above object, the present invention provides a reactor in which a pressure suppression chamber forming a pressure suppression pool is provided on the outer periphery of a pedestal supporting a reactor pressure vessel, and a vent pipe is opened in the pressure suppression pool. In the containment vessel, a partition wall is provided in the pressure suppression chamber to divide it into a pressure suppression pool and a water tank, and a drain pipe for draining cooling water is provided on the pressure suppression pool side, and on the water tank side, It has a water supply pipe that supplies cooling water.

[0007]

[Action]

 With the above configuration, the pressure suppression chamber is partitioned by the partition wall into the pressure suppression pool and the water tank, so even if the cooling water violently vibrates on the pressure suppression pool side, this vibration is blocked by the partition wall. It is not transmitted directly to the water supply pipe on the aquarium side. Further, since the cooling water supplied to the water tank side overflows the partition wall and flows to the pressure suppression pool side, there is no shortage of cooling water on the pressure suppression pool side.

[0008]

【Example】

 An embodiment of the present invention will be described below with reference to FIGS. 1 and 2.

As shown in the figure, a substantially cylindrical pedestal 3 is erected on the inner bottom of the reactor containment vessel 1 partitioned by a concrete shielding wall 12, and the pedestal 3 is provided with a reactor pressure vessel 2. It is supported. A pressure suppression chamber 4 defined by a concrete shielding wall 12 is formed on the outer periphery of the pedestal 3, and a pressure suppression pool 4a in which cooling water is stored is formed inside the pressure suppression chamber 4. A diaphragm floor 13 is provided in the pressure suppression chamber 4 at a predetermined distance from the pedestal 3 and the shield wall 12 of the reactor containment vessel 1. The diaphragm follower 13 defines a dry well 14 in the upper part of the reactor containment vessel 1 and a pressure suppression chamber 4 in the lower part thereof. In the dry well 14, a main steam pipe 15 connected to a power generation turbine (not shown) from the reactor pressure vessel 2 and a main steam pipe 15 are branched to escape steam to the pressure suppression chamber 4. The pressure relief valve 16 of FIG. The steam introduced into the pressure relief valve 16 is introduced into the cooling water w of the pressure suppression pool 4a formed in the pressure suppression chamber 4 through the quencher 8 provided at the bottom of the pressure suppression chamber 4. To be done. Further, high-temperature and high-pressure steam due to an accident or the like generated in the dry well 14 is introduced into the cooling water w of the pressure suppression pool 4a via the vent pipe 7 provided inside the pedestal 3. Therefore, a vent pipe 7 for introducing the above-described high temperature and high pressure steam is opened in the pressure suppression pool 4a.

The partition wall 18 is formed of a concrete structure so as to surround the pedestal 3 at a predetermined interval on the outer peripheral portion of the pedestal 3, and is set higher than the water level of the pressure suppression pool 4 a. A water tank 17 partitioned by the pedestal 3 is formed, whereby the overflowing water level or overflow end w1 is set higher than the water level w of the pressure suppression pool 4a. That is, the overflow water level w1 of the water tank 17 is set to a position higher than the water level generated when high-temperature and high-pressure steam is introduced into the pressure suppression pool 4a. A water supply pipe 5 for supplying water to the pressure suppression pool 4 is inserted and supported in the water tank 17 formed in this way. When the water supply pipe 5 penetrates the shield wall 12 that divides the reactor pressure vessel 2 and is inserted into the water tank 17, as shown in the drawing, a horizontal guide pipe is installed in the pipe support 10 provided on the inner wall of the shield wall 12. Will be installed. Further, as shown in the figure, since the partition wall 18 for partitioning the water tank 17 is formed on the outer peripheral portion of the pedestal 3, the vent pipe 7 extending from the pedestal 3 toward the pressure suppression pool 4a is the partition wall 18. The discharge port is opened so as to face the pressure suppression pool 4a. A drain pipe 6 is provided in the pressure suppression pool 4a as in the conventional example.

Next, the operation of this embodiment will be described.

With the above configuration, the high-temperature and high-pressure steam generated in the event of an accident in the dry well 14 of the reactor containment vessel 1 is cooled by the cooling water stored in the pressure suppression pool 4 a via the vent pipe 7. It will be introduced in w. At this time, the high-temperature and high-pressure steam is discharged to the pressure suppression pool 4a and then condensed by the cooling water.

Particularly, in the present invention, even if the high-temperature and high-pressure steam is introduced into the pressure suppression pool 4a and the stored cooling water w violently vibrates, the partition wall 18 blocks and protects the vibration. No damage is caused. Therefore, as described above, the partition wall 18 is formed by a concrete wall having a high vibration absorption rate. Further, since the water supply pipe 5 is inserted in the water tank 17 and the overflow water level is higher than the water level in the water tank 17, the inside of the water tank 17 is kept extremely static in order to prevent high pressure steam from entering from the pressure suppression pool 4a. Therefore, the protection of the water supply pipe 5 is sufficiently achieved. The overflow water level w1 of the water tank 17 is supplied from the water supply pipe 5 and drained from the water discharge pipe 6 so that the overflow water level w1 is maintained at a higher water level than the water level rising by the steam into which the cooling water of the pressure suppression pool 4a is introduced. Therefore, the cooling water w of the pressure suppression pool 4a does not flow back into the water tank 17.

Therefore, since the water supply pipe 5 is not subjected to a vibration load due to the vibration of the pressure suppression pool 4a, the durability of the pipe support 10 or the like supporting the water supply pipe 5 can be improved.

In the embodiment, the water tank 17 defined by the partition wall 18 is formed so as to surround the entire outer peripheral portion of the pedestal 3, but the present invention is not limited to this. It is needless to say that they may be formed in accordance with the number of the water supply pipes 5 at predetermined intervals along the line.

[0016]

[Effect of device]

 As is clear from the above description, the present invention produces the following excellent effects.

(1) The water supply pipe can be completely protected from vibration generated when steam is introduced into the pressure suppression pool, and water can be supplied to the pool.

(2) It is possible to prevent the vibration generated in the pressure suppression pool from propagating to the containment vessel via the water supply pipe.

[Brief description of drawings]

FIG. 1 is a side sectional view showing an embodiment of the present invention.

FIG. 2 is a horizontal sectional view taken along the line AA showing an embodiment of the present invention.

FIG. 3 is a side sectional view showing a conventional technique.

[Explanation of symbols]

 1 Reactor containment vessel 2 Reactor pressure vessel 3 Pedestal 4 Pressure suppression chamber 4a Pressure suppression pool 5 Water supply pipe 6 Drain pipe 17 Water tank 18 Partition wall

Claims (1)

[Scope of utility model registration request] 1. A reactor containment vessel in which a pressure suppression chamber forming a pressure suppression pool is provided in an outer peripheral portion of a pedestal for supporting the reactor pressure container, and a vent pipe is opened in the pressure suppression pool, wherein the pressure suppression is achieved. A partition wall is provided in the room to divide into a pressure suppression pool and a water tank, a drain pipe for draining cooling water is provided on the pressure suppression pool side, and a water supply pipe for supplying cooling water is provided on the water tank side. A containment vessel for a nuclear reactor.