JPH0756520B2 - 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 the 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. 1, is returned to the mixing tank 8 outside the reactor containment vessel 11 by the temporary pipe 10, and is again heated and circulated. 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. Further, 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 system, and reference numeral 29 is a boric acid water injection system.

However, with such a test method, the temporary equipment must be assembled and used in parallel with the construction work of the nuclear reactor, and therefore the materials and the dismantling of the temporary portion shown by the chain line in FIG. There is a problem that the number of man-hours becomes large, the construction period becomes long, and mutual interference with the construction work of the nuclear reactor is likely to occur. In order to operate the heating means 3, the auxiliary boiler is operated to generate heated steam. It has to be done, which causes problems such as an increase in cost.

"Object of the Invention and Means for Achieving the Same" The present invention effectively solves the problems of the prior art as described above, makes it almost unnecessary to install temporary equipment, and shortens the construction period and reduces the cost. Therefore, water is supplied from the condensate supply water system to the reactor pressure vessel, etc.
A part of the stored water in the reactor pressure vessel is circulated by a reactor residual heat removal system or the like, and the Joule heat of the circulation pump and the circulating water, that is, heat generated by energy loss of the reactor residual heat removal system pump. And the heat generated by the energy loss during circulation of the circulating water to heat the circulating water, and the reactor pressure vessel and its associated pipes filled with circulating water at the test temperature, the condensate supply system and the residual heat removal of the reactor. With the valve closed between the system and the system, pressurized water is sent to the reactor pressure vessel by the operation of the borate water injection system pump of the borate water injection system, and the reactor pressure vessel and its associated piping are pressurized to the test pressure. It is something like that.

[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. The same parts as those of the conventional example are designated by the same reference numerals to simplify the description.

Also in this one embodiment, the water supply means 2, the heating means 3 and the pressurizing means 4 are respectively provided, but these means may be constructed by combining those which are originally installed in the reactor. The water supply means 2 has a basic configuration using a condensate supply water system 30, the heating means 3 uses a residual reactor heat removal system 28, and the pressurizing means 4 uses a boric acid water injection system 29.

That is, the water supply means 2 is a condensate storage tank in the condensate supply water system 30 in a state before the start of operation of the reactor (before the start of nuclear heating).
The stored water of 31 is sent out by the pump 32 for the condensate supply water system, through a part of the piping of the reactor residual heat removal system 28 and a part of the discharge piping of the reactor cooling water recirculation system 12, The air is sent into the reactor pressure vessel 1 as indicated by an arrow. In this case, air removal and treatment of overflowed water are carried out from the upper mirror of the reactor pressure vessel 1 to the equipment sump tank 24 by a vent pipe 33. The residual air of the reactor pressure vessel 1 and the like that is introduced is eliminated.

The heating means 3 is for shutting off the connection between the water supply means 2 and the piping of the heating means 3 by means of the valve 17, and then for raising the temperature by setting the residual heat removal system 28 of the nuclear reactor in a circulating state. With the heat exchanger 34 of the residual heat removal system 28 in a non-operating state, the residual heat removal system pump 35 is operated, and the reactor pressure vessel 1 which is in a water-filled state by the water supply means 2 and the reactor pressure vessel 1 are connected to this. In addition to sending water to the piping, the circulation of the reactor residual heat removal system pump 35 is performed again, and the Joule heat of the circulation pump (reactor residual heat removal system pump 35 in FIG. 1) and The temperature of the circulating water is gradually raised by the Joule heat generated by circulating the circulating water to reach the desired pressure resistance suitable temperature. The Joule heat mentioned above is work heat and is transferred to the circulating water among the generated heat of the energy loss consumed by the friction etc. when the pump drives the water and when the circulating water passes through the flow path. Means fever.

The pressurizing means closes the valve 17 that is opened in the step of performing the heating means 3, and stores a small amount of pure water in the boric acid water injection system tank 36 of the boric acid water injection system 29. By operating the boric acid water injection system pump 37, the pressurized water is directly sent into the reactor pressure vessel 1 as shown by the arrow, and the pressure resistance test is performed. The pressurizing means 4
Since the boric acid water injection system pump 37 in FIG. 1 has a pressurizing ability of sending boric acid water into the reactor pressure vessel 1 in an emergency, it is possible to independently generate pressure during a pressure resistance test. As shown by the chain line in FIG. 1, depending on the specifications of the boric acid water injection system pump 37, a temporary plunger pump 19 according to the conventional example may be provided to assist the pressurizing means 4. . Alternatively, a control rod drive system pump may be used.

The present invention includes the following embodiments.

(I) In addition to the heating by the operation of the reactor residual heat removal system pump 35, the reactor cooling water recirculation system pump 22 in the reactor cooling water recirculation system 12 is also operated, and the Joule heat causes the water temperature to rise. Try to raise. Alternatively, use another pump that can form a circuit.

(Ii) In the water supply means 2, the condensate supply water system 30 is used to supply water by using the piping of the low pressure core spray system 27.

(Iii) As the pressurizing means, use one that can generate high pressure in accordance with a boric acid water injection system pump.

(Iv) 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 for a nuclear reactor recirculation system of the present invention, the following effects can be achieved.

Since the water supply means, heating means, and pressurizing means are respectively carried out using the main installation equipment of the reactor, a vast amount of temporary equipment is unnecessary compared to the conventional example, and the reduction of materials, installation and dismantling man-hours It can be reduced significantly.

By the above, the installation method is improved and the construction period can be shortened.

As the heating means, Joule heat, that is, the heat transmitted to the circulating water among the generated heat of the energy loss consumed by friction etc. when the pump drives the water and the circulating water passes through the flow path Since it is used, the operation of the auxiliary boiler can be omitted or reduced.

[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 water system, 31 …… Condensate storage tank, 32 …… Condensate Water supply water system pump, 33 …… Vent piping, 34 …… Heat exchanger, 35 …… Reactor residual heat removal system pump, 36 …… Borate water injection system tank, 37 …… Borate water injection system pump .

Claims (2)

[Claims] 1. A reactor pressure vessel (1) is supplied with water from a condensate supply system (30), and a part of the stored water in the reactor pressure vessel is supplied to the residual reactor heat removal system (28). The circulation system is circulated by the operation of the removal system pump (35), and the circulation water is heated by the heat generated by the energy loss of the reactor residual heat removal system pump and the heat produced by the energy loss during the circulation of the circulation water, With the valve (17) closing the reactor pressure vessel filled with circulating water at the test temperature and its associated piping, and the condensate supply system and the residual reactor heat removal system,
A pressure resistance test method for a reactor pressure vessel and its associated piping, which comprises pressurizing the reactor pressure vessel and its associated piping to a test pressure. 2. The reactor pressure vessel (1) is supplied with water from a condensate supply system (30), and a part of the stored water in the reactor pressure vessel is partially removed by the residual reactor heat removal system (28). The circulation system is circulated by the operation of the removal system pump (35), and the circulation water is heated by the heat generated by the energy loss of the reactor residual heat removal system pump and the heat produced by the energy loss during the circulation of the circulation water, With the valve (17) closing the reactor pressure vessel filled with circulating water at the test temperature and its associated piping, and the condensate supply system and the residual reactor heat removal system,
Boric acid water injection system (29) Boric acid water injection system pump (37)
The pressurized pressure water is sent to the reactor pressure vessel by the operation of (1) to pressurize the reactor pressure vessel and its associated piping up to the test pressure, and a pressure resistance test method for the reactor pressure vessel and the associated piping.