JPH083551B2 - Pressure resistance test method for reactor pressure vessel and attached piping - Google Patents

Description

The present invention relates to a pressure test method for a reactor pressure vessel and auxiliary piping.

"Prior art and its problems" The auxiliary piping of the reactor pressure vessel is subjected to a required pressure resistance test before the start of operation of the reactor to confirm its soundness.

A conventional example of a pressure resistance test method for a reactor pressure vessel and attached piping in a boiling water reactor will be described with reference to FIG. 2. The reactor pressure vessel 1 is filled with water (pure water) by a water supply means 2. At the same time, the heating means 3 heats up the test water to a suitable temperature during the water supply, and then the pressurizing means 4 is operated to increase the test pressure, for example, a water pressure of 115 kg / cm ^2, to carry out the pressure resistance test, and The means shown by the chain line in FIG. 2, that is, the water supply means 2, the heating means 3, and the pressurizing means 4 are provisionally installed regardless of the original facilities of the boiling water nuclear power plant.

The water supply means 2 sends pure water from a pure water tank 5 to a filtered water tank 7 by a pump 6 to filter it, and then sends the filtered water to a heating means 3 as indicated by an arrow. The means 3 stores the filtered water in the mixing tank 8 and feeds the stored water with steam from a steam supply system (auxiliary boiler etc.) 9 to heat it up to an appropriate temperature for the test, and by operating the pump 6, as shown by the arrow. , Appropriate temperature water is joined to the reactor cooling water recirculation system 12 in the reactor containment vessel 11 via the temporary pipe 10, and via the pump discharge side pipe of the reactor cooling water recirculation system 12 It is fed into the reactor pressure vessel 1 as shown by the arrow. Then, the water stored in the reactor pressure vessel 1 passes through a lower mirror of the reactor pressure vessel 1 and a part of the piping of the reactor cooling water purification system 13 in order to circulate again.
It is taken out of the reactor pressure vessel 1, returned to the mixing tank 8 outside the reactor containment vessel 11 by a temporary pipe 10, and heated and circulated again. Further, the return water when the heating means 3 is operated is returned from the upper mirror of the reactor pressure vessel 1 through another temporary pipe 14 to a temporary pipe in the reactor containment vessel 11.
The main steam pipe 15 and the reactor isolation cooling system 16 can be led together to join the temporary pipe 10.

Further, when the pressurizing means 4 is carried out, the valves 17 are closed, and the heated water discharged from the heating means 3 is guided to the plunger pump 19 through the branch pipe 18 from the middle of the temporary pipe 10 or the like. Pressurized water is generated by the plunger pump 19, the pressurized water is sent to the reactor cooling water recirculation system 12 via the header 20 and the pressurized water supply pipe 21, and the pump suction side pipe of the reactor cooling water recirculation system 12 Through the reactor cooling water recirculation pump 22 and the pump discharge pipe, it is sent to the reactor pressure vessel 1 as shown by the arrow, and the pressure is raised to the required pressure. In FIG. 2, the thick line piping is the target portion of the pressure resistance test.

After the pressure resistance test is completed, the water in the reactor pressure vessel 1 is drained by the drainage pipe 23 and dropped into the equipment sump tank 24 for treatment. Reference numeral 25 is a water supply system, reference numeral 26 is a high pressure core spray system, reference numeral 27 is a low pressure core spray system, reference numeral 28 is a reactor residual heat removal section, and reference numeral 29 is a boric acid water injection system.

However, with such a test method, the construction work of the nuclear reactor must be performed in parallel and the temporary equipment must be assembled and used. Therefore, in particular, the materials and the dismantling of the temporary portion shown by the chain line in FIG. 2 are required. As a result, the number of man-hours becomes large, the work period becomes long, and mutual interference with the construction work of the reactor is likely to occur.

"Object of the Invention and Means for Achieving the Same" The present invention effectively solves the problems of the prior art as described above, and almost eliminates the need to install temporary equipment.
It is possible to shorten the construction period and cost,
For this reason, water is supplied from the condensate supply system to the reactor pressure vessel, etc., and the supplied water is heated by the plant auxiliary steam system to the optimum test temperature, and the reactor pressure vessel and its associated piping that have been supplied at the optimum test temperature With the valve closed between the water supply system and the boric acid water injection system, the pump for the boric acid water injection system sends pressurized water to the reactor pressure vessel, and the reactor pressure vessel and its ancillary pipes up to the test pressure. It is designed to be pressurized.

[Example] An example of a pressure resistance test method for a reactor pressure vessel and auxiliary piping of the present invention will be described below with reference to FIG. In addition,
The parts common to the conventional example are given the same reference numerals to simplify the description.

This embodiment also has a water supply means 2, a heating means 3 and a pressurizing means 4 in common with the prior art example of FIG. 2, but these means in one embodiment are , The components originally installed in the nuclear reactor are combined and configured, the water supply means 2 is the condensate supply system 30, the heating means 3 is the condensate supply system 30 and the plant auxiliary steam system 31, the pressurization Means 4 is a basic configuration using a boric acid water injection system 29.

That is, the water supply means 2 and the heating means 3 are connected to the heat exchange section 33 in the condensate storage tank 32 in the condensate supply system 30 in a state before the start of the operation of the reactor (before the start of the nuclear heating), and the plant auxiliary By sending the heating steam of the steam system 31 to raise the temperature of the stored water, it is sent out as shown by the arrow by the condensate supply system pump 34, and a part of the piping of the residual heat removal system 28 of the reactor, It is sent into the reactor pressure vessel 1 as shown by an arrow through a part of the discharge pipe in the reactor cooling water recirculation system 12, and air removal and overflow water treatment in this case are performed by the reactor. From the upper mirror of the pressure vessel 1, it is guided to the equipment sump tank 24 by the vent pipe 35, and the reactor pressure vessel 1
I try to eliminate residual air such as. Further, when the heating means 3 is carried out, the residual reactor heat removal system 28 is operated as necessary to form a circulation state as shown by an arrow so that the internal temperature of the reactor pressure vessel 1 is made uniform. Can be planned. In this case, the heat exchanger 36 of the reactor residual heat removal system 28
In the non-operating state, the reactor residual heat removal system pump 37 is operated, and water is sent to the reactor pressure vessel 1 which is filled with water by the water supply means 2 and the pipe communicating therewith, Reactor residual heat removal system pump 37
Or by feeding hot water through the reactor isolation cooling system 16 as shown by the broken line arrow, the target pressure-resistant optimum temperature is reached.

The pressurizing means closes the valve 17 which is opened in the process of performing hot water circulation by the water supplying means 2, the heating means 3 and the residual heat removal system 28 of the reactor and injecting boric acid water of the boric acid water injection system 29. By storing a small amount of pure water in the system tank 38 and operating the boric acid water injection system pump 39, the pressurized water is directly fed into the reactor pressure vessel 1 as indicated by the arrow. The withstand voltage test is carried out. The boric acid water injection system pump 39 in the pressurizing means 4 has a pressurizing capability of sending boric acid water into the reactor pressure vessel 1 in an emergency, and can independently generate pressure during a pressure resistance test. However, as shown by the chain line in FIG. 1, a temporary plunger pump 19 according to the conventional example may be provided to assist the pressurizing means 4 in accordance with the specifications of the boric acid water injection system pump 39. possible. Alternatively, a control rod drive system pump may be used.

The present invention includes the following embodiments.

(I) In the water supply means 2, water is supplied by using the condensate supply system 30 and by using the piping of the low pressure core spray system 27.

(Ii) The pressurizing means should be capable of generating a high pressure in accordance with a boric acid water injection system pump.

(Iii) Drain the reactor pressure vessel 1 through the piping of the reactor cooling water recirculation system 12 or the reactor residual heat removal system 28.

"Effects of the Invention" As described above, according to the pressure resistance test method of the reactor recirculation system of the present invention, water is supplied from the condensate supply system to the reactor pressure vessel, etc., and the supplied water is supplied to the plan and the auxiliary steam system. The heating water is heated to a suitable temperature by the test, and after the heating, pressurized water is sent to the reactor pressure vessel by the operation of the boric acid water injection system pump, etc., and it is pressurized to the test pressure. Compared with the conventional example, a huge amount of temporary equipment is not required because the pressure means and the main equipment of the nuclear reactor are used respectively, and it is possible to significantly reduce the materials, reduction, installation and dismantling man-hours. As a result, the installation method is improved, and an excellent effect such that the construction period can be shortened is exhibited.

[Brief description of drawings]

FIG. 1 is a piping system diagram showing an embodiment of a pressure resistance test method for a reactor pressure vessel and auxiliary piping according to the present invention, and FIG. 2 is a piping system diagram showing a conventional pressure resistance test method. 1 ... Reactor pressure vessel, 2 ... Water supply means, 3 ... Heating means, 4 ... Pressurizing means, 5 ... Pure water tank, 6 ... Pump, 7 ... Filtered water tank, 8 ... Mixing Tank, 9
... Steam supply system, 10 ... Temporary piping, 11 ... Reactor containment vessel, 12 ... Reactor cooling water recirculation system, 13 ... Reactor cooling water purification system, 14 ... Temporary piping, 15 ... Main steam piping, 16 …… Reactor isolation cooling system, 17 …… Valve, 18 …… Branch piping, 19 ……
Plunger pump, 20 …… Header, 21 …… Pressurized water supply pipe, 22 …… Reactor cooling water recirculation pump, 23 …… Drainage pipe, 24 …… Device sump tank, 25 …… Water supply system, 26 …… High pressure Core spray system, 27 …… Low pressure core spray system, 28 …… Reactor residual heat removal system, 29 …… Boric acid water injection system, 30 …… Condensate supply system, 31 …… Plant auxiliary steam system, 32 …… Recovery Water storage tank, 33 ... Heat exchange section, 34 ... Condensate supply system pump, 35 ...
… Vent pipe, 36 …… Heat exchanger, 37 …… Reactor residual heat removal system pump, 38 …… Boric acid water injection system tank, 39 ……
Pump for boric acid injection system.

Claims (1)

[Claims] 1. Atomic water supplied to a reactor pressure vessel (1) from a condensate supply system (30) and heated to a test optimum temperature by a plant auxiliary steam system (31) to supply water at the test optimum temperature. Pressurized water was supplied by the operation of the boric acid water injection system pump (39) of the boric acid water injection system (29) with the valve (17) closed between the reactor pressure vessel and its associated piping and the condensate supply system. A pressure test method for a reactor pressure vessel and its associated piping, which comprises sending the reactor pressure vessel and its associated piping to a test pressure.