JP2001305267A - Testing method for nuclear reactor containment vessel - Google Patents

Abstract

PROBLEM TO BE SOLVED: To educe the work quantity in a test executed as the inspection prior to field use of a nuclear reactor containment vessel and the work quantity of a main test appurtenant work to easily perform the test in a short time. SOLUTION: This testing method for nuclear reactor containment vessel comprises a field pressure test c and leakage test d for a reactor containment vessel 1 containing a nuclear reactor pressure vessel and a reactor body foundation base 2 for supporting the nuclear reactor pressure vessel and having a diaphragm floor 7 for partitioning a dry well 4 and a suppression chamber 5, and a leakage ratio test g for the diaphragm floor. Namely, the water charging (a) of the suppression pool, the pressure rising b of the reactor containment vessel, the pressure test c, the leakage test d and the leakage ratio test e are performed. The pressure lowering e of the suppression chamber and the leakage ratio test g of the diaphragm floor are then performed. The pressure lowering h of the dry well, the draining I of the suppression pool, the removal j of a vent pipe temporary closing plate, and the final cleaning k of the suppression chamber are successively performed.

Description

DETAILED DESCRIPTION OF THE INVENTION

[0001]

BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a boiling water reactor containment vessel testing method for performing various tests as a pre-use inspection of a reactor containment vessel.

[0002]

2. Description of the Related Art In the event of an accident in the event of a damage to the primary reactor system, radioactive materials leaked from the reactor core are contained in the reactor building of the nuclear power plant, and the nuclear reactor is protected from releasing radioactivity to the outside. A containment vessel is provided. The reactor containment vessels of the boiling water reactor are all pressure-suppressed, and have a structure in which a dry well and a suppression chamber partitioned by a diaphragm floor are provided in the reactor containment vessel.

[0003] In the drywell, in addition to the equipment belonging to the reactor pressure vessel boundary, such as the reactor pressure vessel, steam piping, and valves, the internal structure of the containment vessel such as the reactor pressure vessel base (pedestal), shielding, and air conditioning. Equipment is stored.
On the other hand, a suppression pool is provided in the suppression chamber, and is usually filled with pool water in order to condense the steam in the containment vessel.

Referring to FIG. 12, the internal structure of a containment vessel in a boiling water reactor is schematically described. That is, the reactor containment vessel 1 has a steel reactor pressure vessel base 2 built in the center of the inside thereof, and the reactor pressure vessel 3 is supported upright on the upper part of the base 2. In the containment vessel 1, a diaphragm floor 7 made of a reinforced concrete slab for partitioning a dry well 4 and a suppression chamber 5 serving as a wet well is provided.

[0005] A vent pipe 8 is installed in the reactor pressure vessel base 2 so as to be vertically erected, and the upper end is open to the dry well 4. A suppression pool 6 is provided in the suppression chamber 5, and the pool 6 normally stores pool water.

[0006] A plurality of horizontal discharge pipes 8a extending in the horizontal direction and located in the suppression pool 6 are connected to the lower side surface of the vent pipe 8, and a closing plate at the time of the test is connected to the opening at the tip of the horizontal discharge pipe 8a. 12 is temporarily installed and removed during reactor operation. Reference numeral 10 in FIG. 12 denotes a device hatch.

At the stage of construction on site, the reactor containment vessel 1 is inspected to confirm that the reactor containment vessel 1 has a predetermined pressure resistance and leakage resistance performance. A pressure test and a leak test are performed. As for the diaphragm floor 7, a diaphragm floor leak rate test is performed at a designed differential pressure instead of the pressure resistance test and the leak test. Furthermore, a containment vessel leak rate test is performed to confirm that the containment vessel 1 satisfies the allowable leak rate.

At the time of the on-site pressure test and leak test of the containment vessel and the leak rate test of the diaphragm floor,
The test is performed without water in the suppression pool 6 without water. Further, when performing a diaphragm floor leak rate test, it is necessary to generate a pressure difference between the dry well 4 and the suppression chamber 5. Therefore, the horizontal discharge pipe of the vent pipe 8 built in the reactor pressure vessel base 2 is required. A closing plate 12 made of a mirror plate is temporarily attached to the opening at the tip of 8a by welding.

In the reactor containment vessel leak rate test, since the condition in which the fuel assembly can be loaded into the reactor pressure vessel 3 is a prerequisite for the test, the vent pipe 8 including the suppression chamber 5 is also filled with water. Perform the test in the condition of

A conventional test method of this type will be described with reference to FIG. FIG. 13 shows steps 1 to 14 of the conventional test method. That is, as shown in FIG. 13, the reactor containment vessel 1 is pressurized in a state where water is not filled in the suppression pool 6 (step 1), and the pressure test (step 2) and the leak test ( Step 3) is performed. afterwards,
The pressure of the suppression chamber 5 is reduced (zero) (step 4).

Next, after performing a leak rate test on the diaphragm floor (step 5), the pressure in the dry well 4 is reduced to zero (step 6). Thereafter, a part of the closing plate 12 temporarily attached to the discharge pipe 8a of the vent pipe 8 is drilled (step 7) so that water can be filled in the vent pipe 8, and after the work is completed, the suppression pool 6 is opened.
(Step 8).

[0012] After all the work of filling the suppression pool 6 with water is completed, the reactor containment vessel is again pressurized to a predetermined pressure in order to conduct a reactor containment leak rate test (step 9). A rate test is performed (step 10).

After the completion of the test, the pressure in the containment vessel is reduced to zero (step 11), and the water in the suppression pool 6 is drained (step 12). After draining water from the suppression pool 6 is completed, the closing plate 12 attached to the discharge pipe 8a is completely removed (step 13), and the suppression chamber 5 is finally cleaned (step 14). On-site testing is completed.

[0014]

However, in the conventional reactor containment vessel test method, the pressure rise / fall test of the reactor containment vessel 1 several times, the suppression chamber 5 or the suppression pool 6 is filled with water, and the vent pipe 8 is leveled There are many steps such as drilling a part of the closing plate 12 temporarily attached to the discharge pipe 8a and removing the closing plate 12, and many accompanying operations, resulting in high cost.

SUMMARY OF THE INVENTION The present invention has been made to solve the above-mentioned problems, and its objects are to raise and lower the pressure of the containment vessel several times, fill the suppression chamber or the suppression pool with water, drill a part of the closing plate, A reactor containment vessel that can simplify many steps such as removal work of the closing plate and the accompanying work, and shorten the test period, reduce the cost by shortening the steps, and reduce the cost by reducing the accompanying work. To provide a test method.

[0016]

According to the first aspect of the present invention, there is provided a reactor pressure vessel and a diaphragm floor for storing a reactor body base for supporting the reactor pressure vessel and defining a drywell and a suppression chamber. In a reactor containment vessel test method for performing a pressure containment test and a leak test of a reactor containment vessel, a diaphragm floor leak rate test, and the reactor containment leak rate test on site, the reactor containment chamber is filled with water in a state of being filled with water. The pressure test of the dry well and the leak test of the diaphragm, the leak rate test of the diaphragm floor and the leak rate test of the reactor containment vessel were carried out at least once in order to facilitate the work of raising and lowering pressure by gas for each test. Each of the tests is performed in a series of steps without reducing the pressure to zero. According to the first aspect of the present invention, the step-up / step-down operation by the gas for the test can be easily and efficiently performed, and a series of tests can be continuously performed.

According to a second aspect of the present invention, the order of the tests is a pressure test and a leak test of the containment vessel, a leak rate test of the containment vessel, and a leak rate test of the diaphragm floor. And

According to the second aspect of the present invention, it is possible to reduce incidental operations such as filling the suppression pool with water and partially drilling a closing plate attached to the horizontal discharge pipe, and efficiently increasing and decreasing the pressure of the containment vessel. Work can be performed, and the test period can be shortened and the cost can be reduced.

According to a third aspect of the present invention, there is provided a method for testing a containment vessel according to the first or second aspect, or a pressure test and a leak test of the containment vessel and a diaphragm floor leak rate test performed in the suppression chamber. In the reactor containment pool test method for performing the reactor containment leak rate test on site by filling the suppression pool with no water and not filling the suppression pool with water, the reactor containment vessel In conducting the leak rate test, the water filling into the vent pipe built in the reactor body foundation was performed with the horizontal discharge pipe tip opening of the vent pipe sealed with a closing plate. It is characterized by supplying water from above the vent pipe. According to the third aspect of the present invention, it is possible to easily fill the inside of the vent pipe with the closing plate attached to the horizontal discharge pipe.

According to a fourth aspect of the present invention, when water is filled in the vent pipe, the means for confirming that the water filling level in the vent pipe is the same as the water filling level in the suppression chamber is provided. A water filling level detector is inserted from above to measure the water filling level in the vent pipe. According to the fourth aspect of the present invention, the water filling level in the vent pipe can be easily managed by the water filling level detector.

According to a fifth aspect of the present invention, there is provided a method for testing a containment vessel according to any one of the first to fourth aspects,
Before the water in the vent pipe after the end of each test,
Alternatively, before the containment vessel leak rate test, a tap is attached to a closing plate attached to a tip of a horizontal discharge pipe of the vent pipe to fill the vent pipe with water.

According to the invention of claim 5, after each test is completed,
When removing the closing plate, it is necessary to drain the water in the vent pipe. At this time, the tap can be removed to easily discharge the water in the vent pipe. In addition, after conducting the on-site pressure test and leak test of the containment vessel and the diaphragm floor leak rate test without the suppression pool water, before filling the suppression pool with water and conducting the reactor containment leak rate test, The tap can be easily removed to fill the vent pipe with water.

According to a sixth aspect of the present invention, in removing the closing plate attached to the opening of the end of the horizontal discharge pipe of the vent pipe, a water discharging pipe and a hose inlet are attached to the closing plate. After draining the water, the work of removing the closing plate is performed. According to the invention of claim 6, in removing the closing plate, water in the vent pipe can be easily discharged.

According to a seventh aspect of the present invention, after the on-site reactor containment vessel leak rate test is completed, a pipe or a hose is attached to the water discharge pipe and the hose connection, and water in the vent pipe is sucked and drained by a pump. It is characterized by the following.

According to the seventh aspect of the present invention, by connecting a suction pipe or a hose and a pump to the pipe and the hose connection, the vent inside the vent pipe is taken out of the reactor containment vessel using the through-hole of the suppression chamber inlet / outlet. Water can be easily drained.

According to an eighth aspect of the present invention, in the operation of removing the closing plate attached to the horizontal discharge pipe of the vent pipe, a suction hose is inserted into the vent pipe from above the vent pipe to remove water in the vent pipe. It is characterized by sucking and draining water from above with a pump. According to the invention of claim 8,
By using a pump installed on the diaphragm floor from above the vent pipe, water in the vent pipe can be sucked and discharged to the outside of the reactor containment vessel using a through-hole of an equipment hatch or the like.

The ninth aspect of the present invention is characterized in that the reactor containment vessel leak rate test is performed in a state where the vent pipe is not filled with water. According to the ninth aspect of the present invention, it is not necessary to perform water filling work in the vent pipe by performing the reactor containment vessel leak rate test in a state where water is not filled in the vent pipe, and the cost can be reduced by omitting the work. it can.

According to a tenth aspect of the present invention, in the removing operation of the closing plate, the horizontal discharge pipe and the closing plate are connected in a hinge bolt and nut structure with a bracket, and the bolt and nut are removed after the test is completed. The closing plate is removed from the horizontal discharge pipe. Claim 10
According to the invention, the closing plate can be easily removed, and the cost can be reduced.

An eleventh aspect of the present invention is characterized in that the bracket is also removed after the bolts and nuts are removed. According to the eleventh aspect of the present invention, by removing the bracket, there is no excess, and the effect on the vapor condensation performance can be ignored.

According to a twelfth aspect of the present invention, in the operation of removing the closing plate, a flange is attached to the opening at the tip of the horizontal discharge pipe, and the closing plate is connected to the flange with bolts and nuts. , Nuts are removed and the closing plate is removed from the horizontal discharge pipe.

According to the twelfth aspect of the present invention, since the structure of the closing plate is a flange and bolt mounting structure, the closing plate can be easily removed, and the cost can be reduced.

According to a thirteenth aspect of the present invention, the flange is also removed after removing the bolt and the nut. According to the invention of claim 13, by removing the flange, the influence on the steam condensation performance can be ignored.

According to a fourteenth aspect of the present invention, in the removing operation of the closing plate, the horizontal discharge pipe and the closing plate are connected in a screwed structure, and after the test is completed, the screwing is released to move the closing plate to the horizontal position. It is characterized in that it is removed from the discharge pipe. According to the fourteenth aspect, the structure is simple, the closing plate can be easily removed after the test is completed, and the cost can be reduced.

According to a fifteenth aspect of the present invention, in the removing operation of the closing plate, after the test is completed, the closing plate is removed from the horizontal discharge pipe by an underwater operation while the suppression pool is filled with water. .

According to the fifteenth aspect, there is no need to drain the water in the suppression pool after the test.
Since the closing plate can be directly removed in a water-filled state, the man-hour and cost can be reduced accordingly.

[0036]

DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS Referring to FIGS. 1 and 2, a first method of testing a containment vessel according to the first and second aspects of the present invention will be described.
An embodiment will be described. FIG. 1 shows step a including the incidental work of the on-site test of the PCV according to the present embodiment.
2 is a longitudinal sectional view schematically showing the inside of the reactor containment vessel 1 for explaining the present embodiment.

As shown in FIG. 1, first, before the on-site test of the PCV, the work of filling the suppression pool 6 with water is performed (step a). Thereafter, the pressure in the reactor containment vessel 1 is increased to make the pressure in the reactor containment field test (step b). When the pressure reaches the pressure test pressure, the pressure increase is stopped and the pressure test of the reactor containment vessel 1 is performed (step b). c).

After the pressure test of the containment vessel 1 is completed, a leak test of the containment vessel 1 (step d) and a leak rate test of the containment vessel 1 (step e) are performed, and the pressure of the suppression chamber 5 is reduced to zero. (Step f).

After the leak test and the leak rate test of the reactor containment vessel 1 are completed, the pressure of the suppression chamber 5 is reduced (step f) to perform the leak rate test of the diaphragm floor 7 (step g). Is performed (step g). Then, after the leakage rate test (step g) of the diaphragm floor 7 is completed, the pressure of the dry well 4 is reduced (zero) (step h), thereby completing a series of tests.

Thereafter, the suppression pool 6 is drained (step i), the closing plate 12 attached to the horizontal discharge pipe of the vent pipe 8 is removed (step j), and the final cleaning of the suppression chamber 5 (step k). All the work related to the on-site testing of the PCV is completed.

According to the present embodiment, compared to the steps of the conventional example shown in FIG. 13, additional work such as filling the suppression pool 6 and partially piercing the closing plate 12 attached to the horizontal discharge pipe is performed. This makes it possible to reduce and increase the pressure of the containment vessel efficiently, thereby shortening the test period and reducing costs.

Next, a second embodiment of the test method for a containment vessel according to the third and fourth aspects will be described with reference to FIG. 2, the same components as those in FIG. 12 are denoted by the same reference numerals, and the description of the duplicated components will be omitted.

In the present embodiment, the test method of the reactor containment vessel in the first embodiment, or the pressure test, the leak test, and the diaphragm floor leak rate test of the reactor containment vessel without the suppression pool water in the first embodiment. After that, in the on-site reactor containment vessel test method for filling the suppression pool with water and performing a reactor containment leak rate test, upon conducting the reactor containment leak rate test,
Using a closing plate temporarily attached to the opening at the tip of the horizontal discharge pipe, the inside of the vent pipe is filled with water by supplying water into the vent pipe from above the dry well side vent pipe.

FIG. 2 shows a method for filling the vent pipe 8 with water, measuring the filling level of the water inside the vent pipe 8,
This embodiment is a diagram for explaining a detection method. In this embodiment, water is filled in the vent pipe 8 from above the vent pipe 8 on the dry well 4 side by using a water supply hose 9.

Further, when the vent pipe 8 is filled with water according to the present embodiment, the filling level is set to be the same as the filling level of the suppression pool 6, so that the filling level detector 11 and the like are inserted into the horizontal vent pipe 8. And measure.

In the present embodiment, the pressure containment vessel withstand pressure test, the leak test, and the diaphragm floor leak rate test, which were conventionally performed as shown in FIG. 12, were carried out without suppression pool water. After that, the method can also be applied to a case where the suppression pool is filled with water and the on-site reactor containment vessel test method for performing a reactor containment vessel leak rate test is carried out.

According to this embodiment, it is possible to easily fill the inside of the vent pipe 8 with the closing plate 12 attached to the horizontal discharge pipe 8a, and it is possible to control the filling level. .

Next, referring to FIGS. 3A and 3B, claim 5 will be described.
A third embodiment of a test method for a reactor containment vessel corresponding to FIG. In this embodiment, the reactor containment vessel testing method according to the first and second embodiments includes a reactor containment vessel pressure resistance test and a leak test, a reactor containment vessel leak rate test, and a diaphragm floor leak rate test. To remove the closing plate, it is necessary to drain the water in the vent pipe. A tap 13 is attached to the closing plate 12 so that the water in the vent pipe 8 can be easily drained.

The containment vessel pressure resistance test, leak test, and diaphragm floor leak rate test are performed without suppression pool water, and then the suppression pool is filled with water and the reactor containment vessel leak rate test is performed. In the containment vessel test method, a tap 13 is attached to the closing plate 12 so that the vent pipe can be easily filled with water before the reactor containment vessel leak rate test.

FIG. 3A is a view showing a structure in which a tap 13 is attached to a closing plate 12 attached to the horizontal discharge pipe 8a of the vent pipe 8 in the present embodiment, and FIG. FIG. 4 is an enlarged view of a portion A in FIG.

In this embodiment, as shown in FIG. 3, a tap 13 is attached to the closing plate 12, and when draining water from the vent pipe 8, the tap 13 is removed to drain water from the vent pipe 8. Things.

The test method according to the present embodiment is shown in FIG.
The conventional containment vessel pressure test, leak test, and diaphragm floor leak rate test shown in Fig. 12 were conducted without suppression pool water, and then the suppression pool was filled with water to conduct the reactor containment leak rate test. It can also be used when conducting on-site reactor containment vessel testing methods.The reactor pressure vessel containment vessel pressure test, leak test, and diaphragm floor leak rate test are performed without suppression pool water, and then tap 13 is removed and water is filled in the vent pipe 8. According to the present embodiment, it is possible to easily discharge the water in the vent pipe 8 or fill the vent pipe 8 with water.

Next, a fourth embodiment of the test method for a reactor containment vessel according to the sixth and seventh aspects of the present invention will be described with reference to FIGS. 4 (a), 4 (b) and 5. In this embodiment,
In the test method for the reactor containment vessel according to the first to third embodiments, in performing the removal work of the closing plate, in the closing plate which needs to discharge water in the vent pipe,
At the end of the closing plate 12, a water discharge pipe and a valve at the hose connection are provided so that the water in the vent pipe 8 can be easily discharged.
Attach 14. FIG. 4A is a view showing a structure to which the valve 14 is attached, and FIG. 4B is an enlarged view of a portion A in FIG. 4A.

In this embodiment, as shown in FIG. 5, after the reactor containment vessel test is completed at the valve 14 of the water discharge pipe connection, a pipe or a hose 14a is attached, and a pump is used to draw water. .

That is, in the present embodiment, FIG.
As shown in (b), a closing plate attached to the vent pipe 8
A pipe 14 and a valve 14 at an inlet of a hose are attached to 12 so that water in the vent pipe 8 can be discharged.

As shown in FIG. 5, a valve 14 for connecting a pipe and a hose is attached to a closing plate 12 attached to the vent pipe 8, and a suction pipe or a hose 14a and a pump are attached to this valve.
Connect 14b. In other words, piping and hose inlet valves
Attach a suction pipe or hose 14a to 14 and connect it to the pump 14b installed on the platform 16, and attach the hose 14a to the pump 14b and use the through-hole of the suppression chamber inlet / outlet 15 to outside the containment vessel 1. ,
The water in the vent pipe 8 is sucked and discharged. According to the present embodiment, the water in the vent pipe 8 can be easily discharged.

Next, a fifth embodiment of the test method for a containment vessel according to the present invention will be described with reference to FIG. In the present embodiment, in the reactor containment vessel testing method according to the first to third embodiments, it is necessary to drain water from the vent pipe 8 when removing the closing plate 12 after the test. In the containment vessel 1, a suction hose 17 is inserted from above the vent pipe 8 to the vicinity of the bottom, and the water in the vent pipe 8 is sucked up by the pump 17a and drained.

In FIG. 6, water in the vent pipe 8 to which the closing plate 12 is attached is drained from the vent pipe 8 on the dry well 4 side.
The suction hose 17 and the pump 17a are installed in the vent pipe 8 in order to suck and discharge from above.

In FIG. 6, water in the vent pipe 8 to which the closing plate 12 is attached is drained from the vent pipe 8 on the dry well 4 side.
The suction hose 17 and the pump 17a installed on the diaphragm floor 7 draw water from the vent pipe 8 to the outside of the reactor containment vessel 1 by using a through-hole such as an equipment hatch from above.
To discharge. According to the present embodiment, water in vent pipe 8 can be easily discharged.

Next, a sixth embodiment of the test method for a containment vessel according to the ninth aspect of the present invention will be described with reference to FIG. This embodiment does not fill the suppression pool 6 with the test method for the PCV or the on-site pressure test, leak test, and diaphragm floor leak rate test of the PCV according to the first to fifth embodiments. The test was performed without water, and then the suppression pool 6 was filled with water. In the reactor containment vessel test method for performing the reactor containment leak rate test, the vent pipe was used to carry out the reactor containment leak rate test. In order to simplify the operation of filling the inside of the vent 8, a leak rate test of the containment vessel is performed in a state where no water exists in the vent pipe 8.

FIG. 7 shows a state in which water does not exist in the vent pipe 8 to which the closing plate 12 is attached. In this embodiment, there is no water in the vent pipe 8 to which the closing plate 12 is attached. Conduct a containment vessel leak rate test. The work of filling the water inside the vent pipe 8 is simplified, and the cost can be reduced.

Next, referring to FIGS. 8 (a) and 8 (b),
A seventh embodiment of the test method for a containment vessel according to the tenth and eleventh inventions will be described. In the present embodiment, the reactor containment vessel testing method or the reactor containment vessel pressure test and leak test according to the first to sixth embodiments are tested without the suppression pool water, and the diaphragm floor leak rate test is performed. With the containment pool filled with water and the containment vessel leak rate test performed in the reactor containment vessel test method, it is possible to easily remove the closure plate 12 when removing the closure plate after the test. For this purpose, the bracket 18 and the hinge bolt 18a are attached to the structure of the closing plate 12. After the removal of the closing plate, not only the hinge bolt but also the bracket 18 is removed.

FIG. 8A is a view showing that the fitting structure of the closing plate 12 attached to the vent pipe 8 is a hinge bolt type with a bracket, and FIG. 8B is a view showing A of FIG. 8A. It is a part enlarged view.

8 (a) and 8 (b), a gasket 19 is installed between the horizontal vent pipe 8 and the closing plate 12, and a bracket 18 is attached to the vent pipe 8 and the closing plate 12, and further attached to the bracket 18. Attach the hinge bolt 18a. Also,
When the closing plate 12 is removed after the test, not only the hinge bolt 18a but also the bracket 18 attached to the vent pipe 8 is removed.

According to the present embodiment, the closing plate 12 can be easily removed, the cost can be reduced, and by removing the bracket 18, the effect on the vapor condensation performance can be ignored.

Next, referring to FIGS. 9 (a) and 9 (b),
An eighth embodiment of a test method for a containment vessel corresponding to the inventions of the twelfth and thirteenth aspects will be described. In the present embodiment, the reactor containment vessel testing method or the reactor containment vessel pressure test, leak test, and diaphragm floor leak rate test according to the first to sixth embodiments are performed without suppression pool water, and thereafter, Fill the suppression pool with water,
In the reactor containment vessel test method for performing a PCV leak rate test, when the closure plate 12 is to be removed after the test is completed, the closure plate 12 is easily removed. The structure of the flange 20 and bolt nut 21
Format. When the closing plate 12 is removed,
In addition, the flange 20 is also removed.

FIG. 9A is a view showing that the fitting structure of the closing plate 12 attached to the vent pipe 8 is of a flange and bolt-nut type, and FIG. 9B is a view showing A in FIG. 9A. It is a part enlarged view. 9 (a) and 9 (b), a flange 20 is attached to the vent pipe 8, and a bolt and nut 21 are attached together with the flat closing plate 12. In addition, the closing plate after the end of the test
When removing 12, not only the bolt and nut 21 but also the flange 20 attached to the vent pipe 8 is removed.

According to the present embodiment, the closing plate 12 can be easily removed, the cost can be reduced, and the removal of the flange 20 does not affect the steam condensation performance. Become.

Next, referring to FIGS. 10 (a) and 10 (b),
A ninth embodiment of a test method for a reactor containment vessel corresponding to the fourteenth invention will be described. In this embodiment, the reactor containment vessel testing method or the reactor containment vessel pressure test, leak test, and diaphragm floor leak rate test according to the first to sixth embodiments are performed without suppression pool water.
Thereafter, the suppression pool is filled with water, and the containment vessel leak test is carried out in the reactor containment vessel test method. After the test is completed, the closure plate 12 is easily removed when the work for removing the closure plate 12 is performed. In order to make this possible, the structure of the closing plate 12 is provided with a screw thread 23 and is of a screw fastening type.

FIG. 10 (a) is a view showing that the fitting structure of the closing plate 12 attached to the vent pipe 8 is of a screw type, and FIG. 10 (b) is an enlarged view of a portion A in FIG. 10 (a). FIG.
In FIG. 10, a thread 23 is formed on the vent pipe 8 and
A screw thread 23 is also formed on the closing plate 12, and both are screwed and closed. According to the present embodiment, the closing plate 12 can be easily removed, and the cost can be reduced.

Next, a tenth embodiment of the test method for a containment vessel according to the fifteenth aspect of the present invention will be described with reference to FIG. In the present embodiment, the reactor containment vessel testing method or the reactor containment vessel pressure test, leak test, and diaphragm floor leak rate test according to the first to sixth embodiments are performed without suppression pool water, and thereafter, In the reactor containment vessel testing method for filling the suppression pool with water and performing a reactor containment vessel leak rate test, after removing the closing plate 12 after the test, draining water from the suppression pool 6 after the test was completed In order to avoid the work, the closing plate 12 is removed by underwater work while the suppression pool 6 is filled with water.

FIG. 11 shows a closing plate attached to the vent pipe 8.
FIG. 11 is a cross-sectional view showing a situation where a diver 22 removes 12 by underwater work. In FIG. 11, the suppression pool 6
In the water-filled state, the diver 22 removes the closing plate 12 attached to the vent pipe 8 by underwater work.

According to the present embodiment, since the closing plate 12 is removed, the work of draining the water from the suppression pool 6 becomes unnecessary, and the construction period and cost can be reduced. The closing plate 12 in the present embodiment may have any structure as long as it can be attached to the horizontal discharge pipe 8a.

[0074]

According to the present invention, many steps and costs are involved in the auxiliary work such as raising and lowering the pressure of the containment vessel, filling the suppression chamber and the suppression pool with water, partially drilling the closing plate, and removing the closing plate. In this way, it is possible to simplify what has been involved, reduce the test period, reduce the cost by shortening the steps, and reduce the cost due to the auxiliary work with relatively easy work.

[Brief description of the drawings]

FIG. 1 shows a first method of a test method for a containment vessel according to the present invention.
5 is a flowchart for explaining steps in the embodiment.

FIG. 2 shows a second method of the test method for the containment vessel according to the present invention.
FIG. 3 is a longitudinal sectional view for explaining the embodiment.

FIG. 3 (a) is a side view for explaining a main part of a third embodiment of the test method for a containment vessel according to the present invention,
(B) is an enlarged sectional view of a part A in (a).

FIG. 4A is a side view for explaining a main part of a fourth embodiment of the test method for a containment vessel according to the present invention,
(B) is an enlarged sectional view of a part A in (a).

FIG. 5 is a fourth method for testing the containment vessel according to the present invention.
FIG. 3 is a longitudinal sectional view for explaining the embodiment.

FIG. 6 shows the fifth method of the test method for the containment vessel according to the present invention.
FIG. 3 is a longitudinal sectional view for explaining the embodiment.

FIG. 7 is a sixth method for testing a containment vessel according to the present invention.
FIG. 3 is a longitudinal sectional view for explaining the embodiment.

FIG. 8A is a side view for explaining a main part of a seventh embodiment of the test method for a containment vessel according to the present invention,
(B) is an enlarged sectional view of a part A in (a).

FIG. 9A is a side view for explaining a main part of an eighth embodiment of the test method for a containment vessel according to the present invention,
(B) is an enlarged sectional view of a part A in (a).

10A is a side view for explaining a main part of a ninth embodiment of the test method for a reactor containment vessel according to the present invention, and FIG. 10B is an enlarged sectional view of a part A in FIG. .

FIG. 11 is a diagram showing a second embodiment of the test method for the containment vessel according to the present invention.
FIG. 13 is a longitudinal sectional view for explaining the tenth embodiment.

FIG. 12 is a longitudinal sectional view for explaining a conventional test method for a containment vessel.

FIG. 13 is a flowchart for explaining steps of a conventional test method for a containment vessel.

[Explanation of symbols]

1 ... Reactor containment vessel, 2 ... Reactor pressure vessel base, 3 ...
Reactor pressure vessel, 4 ... dry well, 5 ... suppression chamber, 6 ... suppression pool, 7 ... diaphragm floor, 8 ... vent pipe, 8a ... horizontal discharge pipe, 9 ... water supply hose, 10 ... equipment hatch, 11 ... water filling Level detector, 12… Closed plate, 13… Tap, 14… Piping and hose inlet valve, 14a… Suction pipe or hose, 14b… Pump, 15… Suppression chamber entrance and exit, 16… Platform, 17… Suction hose, 17a pump, 18 bracket, 18a hinge bolt and nut, 19 gasket,
20 ... flange, 21 ... bolt, nut, 22 ... diver, 23 ...
Screw thread.

Continued on the front page (72) Inventor Yoshihiro Naruse 8 Shinsugita-cho, Isogo-ku, Yokohama-shi, Kanagawa Prefecture F-term in Toshiba Yokohama Office (reference) 2G075 AA04 BA01 CA10 DA10 DA16 EA01 FA03 FC06 FC14 FC18 GA15 GA16 GA35

Claims (15)

[Claims] A pressure test and a leak test of a reactor containment vessel containing a reactor pressure vessel and a reactor body base supporting the reactor pressure vessel and having a diaphragm floor for partitioning a drywell and a suppression chamber;
In a reactor containment vessel test method for performing a diaphragm floor leak rate test and a reactor containment vessel leak rate test on site, a pressure test and a leak test of the reactor containment vessel performed with the suppression chamber filled with water, the diaphragm floor The leak rate test and the reactor containment vessel leak rate test are performed in a series of steps without lowering the pressure of the drywell to zero in order to facilitate the step-up and step-down operation by gas for each of the tests. A test method for a reactor containment vessel, wherein each test is performed. 2. The method according to claim 1, wherein the order of the tests includes a pressure test and a leak test of the containment vessel, a leak rate test of the containment vessel, and a leak rate test of the diaphragm floor. Test method for containment vessel described. 3. The method for testing a containment vessel according to claim 1 or 2, wherein a pressure test, a leak test, and a diaphragm floor leak rate test of the containment vessel are carried out by supplying water to a suppression pool in the suppression chamber. The reactor containment vessel leak rate test is performed in a reactor containment vessel test method in which the suppression pool is filled with water and then the reactor containment vessel leak rate test is performed on site. In the meantime, filling the inside of the vent pipe built in the reactor body foundation with the horizontal discharge pipe tip opening of the vent pipe sealed with a closing plate, from above the vent pipe on the drywell side A test method for a containment vessel, characterized by supplying water. 4. A water filling level is detected from an upper portion of the vent pipe as a means for confirming that the water filling level in the vent pipe is the same as the water filling level of the suppression chamber when filling the water into the vent pipe. 4. The test method for a containment vessel according to claim 3, wherein a water filling level in the vent pipe is measured by inserting a vessel. 5. The reactor containment vessel test method according to claim 1, wherein after the tests are completed, before the water in the vent pipe is discharged, or before the reactor containment vessel leak rate test. 5. The test method for a containment vessel according to claim 1, wherein a tap is attached to a closing plate attached to a tip end of the horizontal discharge pipe of the vent pipe to fill the vent pipe with water. 6. In removing the closing plate attached to the horizontal discharge pipe tip opening of the vent pipe, a water discharging pipe and a hose inlet are attached to the closing plate to discharge water in the vent pipe. 5. The test method for a containment vessel according to claim 1, wherein the operation of removing the closing plate is performed after the step. 7. A pipe or a hose is attached to the water discharge pipe or the hose connection after the on-site reactor containment vessel leak rate test is completed, and water in the vent pipe is sucked up and drained by a pump. A method for testing a containment vessel according to claim 6. 8. In removing the closing plate attached to a horizontal discharge pipe of the vent pipe, a suction hose is inserted into the vent pipe from above the vent pipe, and water in the vent pipe is pumped from above by a pump. 7. The test method for a containment vessel according to claim 6, wherein the test method is performed. 9. The test method for a reactor containment vessel according to claim 1, wherein the reactor containment vessel leak rate test is performed in a state where the vent pipe is not filled with water. 10. In the removal operation of the closing plate, the horizontal discharge pipe and the closing plate are connected in a hinge bolt and nut structure with a bracket, and after the test is completed, the bolts and nuts are removed and the closing plate is removed. 7. The method for testing a containment vessel according to claim 1, wherein the containment vessel is removed from the horizontal discharge pipe. 11. The method according to claim 10, wherein the bracket is also removed after the bolts and nuts are removed. 12. In the removing operation of the closing plate, a flange is attached to the opening at the tip of the horizontal discharge pipe, the closing plate is connected to the flange by bolts and nuts, and the bolts and nuts are removed after the test is completed. 7. The test method for a containment vessel according to claim 1, wherein said closing plate is removed from said horizontal discharge pipe. 13. The method according to claim 1, further comprising removing the flange after removing the bolt and the nut.
Test method for containment vessel described in 12. 14. In the removing operation of the closing plate, the horizontal discharge pipe and the closing plate are connected in a screw-in structure,
The screw is released after the test is completed, and the closing plate is removed from the horizontal discharge pipe.
7. A test method for a containment vessel according to any one of items 6 to 6. 15. In the removing operation of the closing plate, after the test is completed, the closing plate is removed from the horizontal discharge pipe by an underwater operation while the suppression pool is filled with water. Test method for containment vessel described.