JPH01114796A - Power supply equipment for coolant pump driving motor for nuclear power generation - Google Patents

Abstract

PURPOSE:To reduce the size of a coolant pump driving motor and the diameter of a power supply cable and to reduce the size of a reactor container by installing a generator with a flywheel for supplying driving power to said motor to the outside of the reactor container. CONSTITUTION:The flywheel is not provided to the motor 31 which is provided in the reactor container 1 and is used for driving the coolant pump. On the other hand, the generator 41 with flywheel is constituted of a generator 42, a revolving shaft 43 and the flywheel 44 mounted thereto and is provided on the outside of the container. The power supply to the generator 41 stops when the power supply is temporally stopped during power generation but the flywheel 44 is provided to the generator and, therefore, the generator 42 continues to generate the power for a while by the inertia force of the flywheel 44 and continues to supply the power to the motor 31 in the container 1. The flywheel is not provided to the motor 31 and since the motor is reduced in size, the container itself is reduced in size further the electric power at the start-up of the motor is small and, therefore, the diameter of the power cable 5 for driving the motor is reduced as well.

Description

DETAILED DESCRIPTION OF THE INVENTION [Field of Industrial Application] This invention relates to power supply equipment for a coolant pump drive motor for nuclear power generation.

[Conventional technology]

FIG. 2 is a diagram showing a general system configuration of a conventional pressurized water nuclear power plant. In the figure, 1 is a containment vessel that houses primary system equipment 2 to 7, which will be described later, 2 is a nuclear reactor, and 3
is a pump for circulating coolant such as water that absorbs the heat generated in the reactor 2, 4 is a motor of general configuration that drives this pump 3, and 5 is connected to this motor 4 and is connected to the containment vessel. 1 a power cable to which power is supplied from the outside; 6 a pressurizer that adjusts the pressure of the coolant to be constant; 7 a steam generator that generates steam to extract heat from the coolant; , 8 indicates that the coolant and steam are contained in the containment vessel 1.
A circulation pipe that allows the flow to flow through each device of the secondary system 11 that generates heat 1 inside and outside the containment vessel 1, 12 a turbine to which the steam is supplied, 13 a generator driven by this turbine 12, 14 a 15 is a safety valve that releases the pressure when the pressure of the secondary system 11 becomes high; 16 is a governor that adjusts the amount of steam; 17 is an adjustment of the governor 16; Bypass valve for bypassing excess steam, 18 is 2 that returns from steam to water
A condensate pump flows the coolant from the next system 11 to the next stage feed water heater 19, and thus the feed water heater 19 preheats the fed water to an optimum temperature.

20 is a water supply pump that circulates the coolant of the secondary system 11;
1 is a water supply control valve that adjusts the amount of water supplied.

FIG. 3 shows the specific configuration of the motor 4. In the figure, 25 is the rotating shaft of the motor 4, and 26 is the rotating shaft 2.
A flywheel is attached to 6, and 27 is a rotor and a stator. Note that the other configuration of the motor 4 is the same as the conventional one, so a description thereof will be omitted.

Next, the operation will be explained. The heat generated in reactor 2 is
It is absorbed by the coolant flowing through the circulation pipe 8 tl by the pump 3 driven by the motor 4 and reaches the steam generator 7 . Therefore, heat is exchanged by the steam generator 7 and steam is generated. This generated steam is passed through the circulation pipe 8 to the containment vessel 1.
It is guided to an external secondary system 11 and reaches a turbine 12. The turbine 12 then rotates, and electrical energy is extracted from the generator 13.

By the way, if the power supply to the motor 4 is momentarily stopped due to some reason, the circulation of the coolant and steam will be stopped, and the temperature and pressure of the reactor 2 will rise rapidly, resulting in a dangerous situation. Therefore, in the conventional system described above, the motor 4 is provided with a flywheel 25. Even after the power supply is stopped, the motor 4 continues to rotate due to the inertial force of the flywheel 25 for a while, and a sudden rise in temperature and pressure in the reactor 1 is suppressed. However, measures are being taken to restore power supply in the meantime.

[Problem that the invention seeks to solve]

Since the conventional coolant pump drive motor for nuclear power generation is configured as described above, a flywheel must be provided within the motor 4 in preparation for momentary power outage. Therefore motor 4
There was a problem in that the shape of the container 1 became larger, and the shape of the containment vessel 1 also became larger.

Furthermore, since the flywheel 25 is provided on the motor 4, a large amount of electric power is required to start the motor 4, so the diameter of the power cable 5 must be increased accordingly. There was also the problem of

This invention was made to solve the above-mentioned problems, and it is possible to miniaturize the coolant pump drive motor, and also to reduce the diameter of the power cable for the motor, thereby reducing the size of the containment vessel of the nuclear reactor. The purpose of this project is to obtain power supply equipment for a coolant pump drive motor for nuclear power generation.

[Means for solving problems]

The power supply equipment for a coolant pump drive motor for nuclear power generation according to the present invention is such that a generator with a flywheel for supplying power to the motor is installed outside the containment vessel of a nuclear reactor.

[Function] ゛The flywheel-equipped generator outside the containment vessel according to the present invention generates electricity when power is normally supplied, and supplies the electric power to the motor inside the containment vessel. Therefore, the motor rotates, the pump operates, coolant flows through the circulation pipe, and the generator generates electricity.

By the way, if the power supply is temporarily stopped during such power generation, the power supply to the flywheel-equipped generator outside the containment vessel is also stopped, but because the flywheel is attached, the generator Due to the inertial force of the flywheel, power generation will continue for a while, and power will continue to be supplied to the motor inside the containment vessel. Therefore, the motor continues to rotate for a while even though the power supply is stopped, thereby preventing a sudden rise in the temperature and pressure of the nuclear reactor.

〔Example〕

An embodiment of the present invention will be described below with reference to the drawings. In this example, it is assumed that the pressurized water nuclear power plant system described above with respect to FIG. 2 is utilized. Therefore, with regard to FIG. 2, the configuration excluding the motor 4 is also used in this embodiment.

FIG. 1 is a diagram showing a motor 31° flywheel-equipped generator 41 that replaces the motor 4. As shown in FIG.

That is, in FIG. 1, 31 is a general motor replacing the motor 4 shown in FIGS. 2 and 3, 32 is a rotating shaft of this motor 31, and 33 is a rotor and a stator. Therefore, the motor 31 of the present invention, that is, the motor 31 for driving the pump 3 for circulating coolant such as water and steam generated by the steam generator 7 in the circulation pipe 8, is not provided with a flywheel. , therefore only motor 3
The overall shape of the motor 1 is smaller than that of the conventional motor 4.

41 is a generator with a flywheel according to the present invention;
2 is the generator, 43 is the rotating shaft, and 44 is a flywheel attached to the rotating shaft 43. In this case, the specific construction of this flywheel generator 41 is similar to the conventional motor 4 described with reference to FIG. The power generated by the generator 42 is supplied to the motor 31 via the power cable 5.

Next, the operation will be explained. When the power supply is normal, the flywheel generator 41 operates normally and generates 1t1J.
L force is supplied to the motor 31 via the power supply cape 5. The heat generated in the nuclear reactor 2 is absorbed by the coolant flowing through the circulation pipe 8 by the pump 3 driven by the motor 31, and reaches the steam generator 7. Therefore, heat is exchanged by the steam generator 7 and steam is generated. This generated steam is guided to a secondary system 11 outside the containment vessel 1 via a circulation pipe 8 and reaches a turbine 12. The turbine 12 then rotates, and electrical energy is extracted from the generator 13.

By the way, if the supply of the stain source is momentarily stopped for some reason, the power supply to the generator 42 is also stopped. However, since a flywheel 44 is attached to this generator 42, even after the power supply is stopped, the flywheel 44 rotates due to its inertial force, and the generator 42 continues to generate electricity. Therefore, even though the main power supply to the power cable 5 has stopped, the motor 3 inside the containment vessel 1
1 continues to be supplied with electric power from the generator 42, and the pump 3 continues to be driven. Therefore, the temperature of reactor 2,
A sudden increase in pressure is prevented. Then, while the generator 42 continues to generate electricity due to the inertial rotation of the flywheel 44, the main power supply stop cancellation process is executed, and the power state returns to the normal state.

In the above embodiment, a general motor is used as the motor 31, but the present invention can be similarly implemented with special motors such as a canned motor and a wet motor.

Further, in the above embodiments, the present invention has been described with respect to a pressurized water type nuclear power plant, but the present invention can also be implemented in other types of nuclear power plants such as a boiling water type and a double heavy water type.

〔Effect of the invention〕

As described above, according to the present invention, the flywheel-equipped generator that supplies power to the pump drive motor to prevent the temperature and pressure of the reactor from rising is installed outside the containment vessel of the reactor. Therefore, there is no need to provide any flywheel to the pump drive motor inside the containment vessel. In the event of a momentary power outage, the pump drive motor inside the containment vessel is supplied with power by the flywheel-equipped generator outside the containment vessel, and can continue to drive the pump. Therefore, instead of providing a flywheel for the pump drive motor inside the containment vessel, a generator with a 72-inch foil is provided outside the containment vessel, so that the shape of the pump drive motor is significantly reduced, and therefore the containment vessel This has the advantage that it can be made smaller in size, and maintenance and inspection of the pump drive motor can be easily performed.

In addition, since the pump drive motor is not provided with a flywheel, the electric power required for starting the motor is small.
There is also the advantage that the diameter of the power cable for the pump drive motor is correspondingly reduced.

[Brief explanation of the drawing]

FIG. 1 is a configuration diagram of an embodiment of the present invention, FIG. M2 is a system configuration diagram of a pressurized water nuclear power plant, and FIG. 3 is a sectional view of a conventional pump drive motor. 1 is a containment vessel, 2 is a nuclear reactor, 3 is a pump, 4 (31) is a coolant pump drive motor, and 41 is a generator with a flywheel. In addition, in the figures, the same reference numerals indicate the same or equivalent parts. Patent applicant: Mitsubishi Electric Corporation, -1- Agent: Patent attorney 1) Hiroshi Sawa'' (2 other names - Figure 1, Figure 2): Introduction, I'll device 2: Atomic energy 3: Pump 4 :
Motor 5: Electric! Cable 26: Fufuihoil procedural amendment (voluntary)

Claims (1)

[Claims] In a power supply equipment for a coolant pump drive motor for nuclear power generation, which is equipped with a motor that drives a pump for circulating coolant and extracting heat generated in a nuclear reactor in a containment vessel to the outside of the reactor, power is supplied to the motor. A power source equipment for a coolant pump drive motor for nuclear power generation, characterized in that a generator with a flywheel for supply is installed outside the containment vessel.