JPH09281283A - Pump driving device for atomic powder plant - Google Patents

Abstract

PROBLEM TO BE SOLVED: To improve power generation efficiency by reducing the construction cost and maintenance cost of an atomic power plant, facilitating control and enhancing energy conversion efficiency. SOLUTION: A generator 4 is connected to a main turbine 3 to which a high-pressure turbine 3a and first to third stage low-pressure turbines 3b are directly coupled. An exciter 22, a coupling 23, a main feed water flow rate regulating valve 26 and a main feed water pump 15 are connected onto the extension shaft of the driving shaft of this generator 4. The coupling of a high- pressure condensate pump thereto in place of the main feed water pumps 15 possible as well. As a result, the need for driving mechanisms for the main feed water pump and the high-pressure condensate pump is eliminated. Driving motors or driving turbines, control mechanisms and driving steam pipings are curtailed, by which the construction cost and maintenance cost of the atomic power plant are reduced. The enhancement of the conversion efficiency of the driving energy and the improvement in power generation efficiency are resulted.

Description

Detailed Description of the Invention

[0001]

BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a pump drive of a nuclear power plant for driving a high pressure condensate pump and a feed water pump used for reactor water supply in a boiling water nuclear power plant (hereinafter referred to as a BWR plant). Regarding the device.

[0002]

2. Description of the Related Art An outline of a reactor system, a main steam system and a feed / condensate system of a conventional BWR plant will be described with reference to FIG.
In FIG. 8, a main steam pipe 2 of a main steam system is connected to a reactor 1, the main steam pipe 2 is connected to a main turbine 3 in which a high pressure turbine and a low pressure turbine are directly connected, and the main turbine 3 is a generator 4 Connected to. Main steam flow meter 5 in main steam pipe 2
The reactor 1 is provided with a water level meter 6, and the signals from the main steam flow meter 5 and the water level meter 6 are flow rate adjusters 7.
Is entered.

A main condenser 8 is connected to the main turbine 3, one end of a condensate pipe 9 is connected to the main condenser 8, and the other end of the condensate pipe 9 is a condensate filter 10 and a condensate demineralizer. 11, the high-pressure condensate pump 12 and the low-pressure feed water heater 13 are connected. Low pressure feed water heater
A water supply pipe 14 is connected to 13, and the water supply pipe 14 is a main water supply pump 15,
Main feed water flow adjustment valve 16, feed water flow meter 17, high pressure feed water heater 18
And the reactor 1 are connected.

Here, three high pressure condensate pumps 12 are arranged in parallel, two main water supply pumps 15 are arranged in parallel, and two auxiliary water supply pumps 19 are also arranged in parallel. Two main water supply flow rate adjusting valves 16 are arranged in parallel, and an auxiliary water supply flow rate adjusting valve 20 is also arranged in parallel. Main water supply pump 15, main water supply flow rate adjusting valve 16 and auxiliary water supply flow rate adjusting valve 20
Is electrically connected to the flow rate regulator 17.

The main feed water pump 15 used for supplying water to the reactor of the BWR plant is driven by an electric motor in the old model of BWR-4, and is driven by a turbine in the model of BWR-5 and ABWR. Further, the high-pressure condensate pump 12 is driven by an electric motor in any type. Note that FIG. 8 shows a configuration in which a turbine drive type water supply pump is used as the main water supply pump 15.

The condensate system includes a condensate filter 10, a condensate demineralizer 11, and a high-pressure condensate pump 12 from a main condenser 8 through a condensate pipe 9.
(50% capacity 3 units), low-pressure feed water heater 13 (plural units) are arranged, and water supply pump (50% capacity main water supply pump 15 is 2 units)
Stand) and the auxiliary water supply pump 20 (2 units with 25% capacity) are connected in parallel.

The water supply system subsequent to the condensate system has a flow rate adjusting valve (main water supply flow rate adjusting valve 16 (2 units of 100% capacity), auxiliary water supply flow rate adjusting valve 20 (1 unit of 10% capacity) from the downstream side of the main water supply pump 15. From the feed water flow meter 17 and the high pressure feed water heater 18 to the reactor 1.

The reactor system comprises a reactor water level gauge 6 connected to the reactor 1, and monitors the water level in the reactor 1. The main steam system is a reactor 1 to a main steam pipe 2, a main steam flow meter 5 and a main turbine 3 connected to the main steam pipe 2, and the main steam flow meter 5
The main steam flow rate is monitored by.

The flow controller 7 is a flow signal of the feed water flow meter 17, the reactor water level meter 6 and the main steam flow meter 5 (broken line in the figure).
To calculate the proper water supply flow rate, and
16, output the control signal (broken line in the figure) to the auxiliary water supply flow rate adjusting valve 20 and the main water supply pump 15 for control.

Next, the features and operations of the main equipment installed in the nuclear power plant shown in FIG. 8 will be described. [Main water supply pump] The main water supply pump 15 is a pump used when the plant is operated at a rated output or a high output for a long time, and has the following two drive systems. Currently, turbine driven water supply pumps are the mainstream.

Features of the electric motor driven water supply pump: Used in the old model of BWR-4.・ Drive system: Induction motor drive. -Number of equipment: 50% of rated capacity 3 pumps (2 pumps operating under rated output, 1 standby) will be installed in parallel. -It can be operated without being affected by the amount of steam generated when the reactor is started and stopped. -It is driven by an induction motor and runs at a constant speed.・ The water supply flow rate is controlled by the main water supply flow rate adjustment valve. -Because it is driven by an electric motor, its structure is simple, robust, and highly reliable. -The drive unit does not need to be warmed up, and quick startup is possible. -The plant efficiency is deteriorated because the generated electricity is consumed.

Features of turbine drive type water supply pump ・ BWR-4 is used in plants after the new model.・ Drive system: Turbine drive.・ Number of equipment: Two pumps with 50% capacity of the rated capacity (a separate pump equivalent to 50% is required for a trip during operation) will be installed in parallel.・ Operation is not possible when the amount of steam generated is small, such as when the reactor is started or stopped (it requires an auxiliary water supply pump). -Variable speed operation is possible because it is driven by a turbine driven by steam generated in the reactor. The feed water flow rate is controlled by the main feed water flow rate adjusting valve 16 or the turbine speed. Since it is driven by a turbine and operates at a variable speed, the structure is complicated and the amount of maintenance work is large.・ It is necessary to warm up the turbine when it goes into standby mode. If it is not warmed up, quick start is not possible. -Since it does not consume generated electricity but uses steam, there are few factors that deteriorate plant efficiency compared to the electric motor drive system.

[Auxiliary Water Supply Pump] The auxiliary water supply pump 19 is a pump that is used when the amount of steam generated is small, such as when the reactor is started and when the turbine drive system water supply pump cannot be used, and has the following features. are doing.

Drive system: Induction motor drive.・ Number of equipment: 25% of rated capacity 2 pumps or 50%
One capacity pump. -Use when the amount of steam generated is small, such as when the reactor is starting up or shutting down, or during a transition period when the turbine-driven feedwater pump trips and is rapidly started from the standby state for continuous plant operation. As a general rule, do not run for a long time (when the turbine-driven water feed pump trips, return to the standby state as soon as the tripped pump is restored). -It is driven by an induction motor and operates at almost the rated speed. The feed water flow rate is controlled by the main feed water flow rate adjustment valve 16 during high-power operation, and is controlled by the auxiliary feed water flow rate adjustment valve 20 when the amount of steam generation is small, such as when starting up and shutting down the reactor. -Because it is driven by an electric motor, its structure is simple, robust, and highly reliable. -The drive unit does not need to be warmed up, and quick startup is possible. -The plant efficiency is deteriorated because the generated electricity is consumed.

[Main Water Supply Flow Rate Control Valve] The water supply flow rate is controlled so as to keep the operation water level constant based on the operating water level of the reactor 1, the main steam flow rate flowing through the main steam pipe 2 and the water supply flow rate flowing through the water supply pipe 14. Therefore, the main water supply flow rate adjusting valve 16 is installed. The main feed water flow rate adjusting valve 16 takes in signals from the feed water flow meter 17, the reactor water level gauge 6 and the main steam flow meter 5 to calculate an appropriate feed water flow rate and issues a signal for controlling the opening degree of the main feed water flow rate adjusting valve 16. It is controlled by the regulator 7.

The drive system is a compressed air drive, and the number of equipment is 50% and capacity is 3. -While the plant is in operation, two main feed water flow rate adjusting valves 16 are used, but if one malfunctions, it will be isolated immediately and one that will be in standby will be in service immediately. -If a turbine driven water feed pump is used, the feed water flow control is turbine driven and is programmed to control the speed of the water feed pump. In this case, the two main water supply flow rate adjusting valves 16 are fully open. However, when the feed water flow rate control by the turbine drive type feed water pump does not operate properly, the turbine feed type feed water pump is put into the run-out state and the main feed water flow rate adjusting valve 16 takes over the control.

[Auxiliary Water Supply Flow Rate Adjusting Valve] The auxiliary water supply flow rate adjusting valve has a low opening degree because the main water supply flow rate adjusting valve 16 causes erosion because the main water supply flow rate adjusting valve 16 is too small at the time when the water supply flow rate is low, such as when the reactor is started and stopped. It is a feed water flow rate adjustment valve used exclusively for flow rate control and has the following features. The drive system is compressed air drive, the number of equipment is 10% capacity, and one is used in a transient state such as when the plant is started and stopped, or at low load operation.

[High-Pressure Condensate Pump] The high-pressure condensate pump 12 is a pump used when the plant is operated at a rated output or a high output for a long time, and has the following features.

The drive system is an induction motor drive, and the number of facilities is 50% of the rated capacity. 3 pumps (2 operated under rated output,
It is one stand-by). It can be operated without being affected by the amount of steam generated, such as when the reactor is started up and shut down, and is driven by an induction motor to run at almost constant speed.

・ The condensate flow rate is determined by the main water flow rate adjusting valve 16 of the water supply system.
Is controlled by -Because it is driven by an electric motor, its structure is simple, robust, and highly reliable. -The drive unit does not need to be warmed up, and quick startup is possible. -The plant efficiency is deteriorated because the generated electricity is consumed.

[0021]

Generally, the thermal efficiency of BWR is about 33 to 35%, which is considerably lower than that of the latest thermal power generation. In BWR-5, in order to improve the efficiency at the power transmission end of the power plant, the steam generated in the nuclear reactor is used to drive the main water supply pump without using the generated electricity to improve the power generation efficiency.

Comparing the electric motor driven and turbine driven feed water pumps, the pumps are the same in structure,
The drive mechanism is different. The electric motor drive system has a simple structure, is robust, and is easy to control. On the other hand, the turbine drive system has a complicated turbine control mechanism and needs to be warmed up when in a standby state, which is complicated and fragile.

Further, the cost of the apparatus is higher in the turbine drive system. However, the turbine drive system is adopted with the intention of suppressing the motor drive system even if there are disadvantages in the structure, method of use, and device cost in order to improve power generation efficiency.
Unlike high-pressure condensate pumps, high-pressure condensate pumps have always been introduced with an electric motor drive system, but they have the same features as electric motor-driven water supply pumps.

These techniques are quite completed and have few technical problems. However, the construction cost of a nuclear power plant is extremely high, and socializing the construction of the nuclear power plant raises issues of rationalization and reduction of the construction cost.

The present invention has been made to solve the above problems, and facilitates the control of the feed water pump and the high-pressure condensate pump and reduces the construction cost and maintenance cost by eliminating the drive turbine and the associated steam piping. An object of the present invention is to provide a pump drive device for a nuclear power plant that can improve the reliability of plant operation and the power generation efficiency.

[0026]

According to a first aspect of the present invention, a main turbine, a generator and an exciter are directly connected to each other, a high pressure condensate pump is provided on an extension axis of a drive shaft on the generator side,
Alternatively, the drive shaft of the main water supply pump is connected. This can eliminate the need for a drive source for the high-pressure condensate pump or the main feed water pump.

A second aspect of the present invention is characterized in that a speed increaser is interposed between the exciter and the high-pressure condensate pump or the main feed water pump. As a result, the number of rotations can be increased and the pumps can be downsized.

A third aspect of the present invention is characterized in that a clutch is interposed between the exciter and the high-pressure condensate pump or the main feed water pump. This facilitates disconnection or connection of the pumps from the drive shaft.

A fourth aspect of the present invention is characterized in that a transmission joint is interposed between the exciter and the high-pressure condensate pump or the main feed water pump. This makes it easy to change the rotation speed of each pump.

According to a fifth aspect of the present invention, a plurality of the high pressure condensate pumps or main feed water pumps are arranged in parallel, and the plurality of high pressure condensate pumps or main feed water pumps are arranged in parallel in a single coupling. And the coupling is connected to the exciter. As a result, it is possible to separate into two axes and form two series each having a capacity of 50% or more.

A sixth aspect of the present invention is characterized in that a speed increaser, a transmission joint, a clutch and a coupling are connected in series between the high pressure condensate pump or the main feed water pump and the exciter. And Thereby, the effects of claims 1 to 4 can be combined.

According to a seventh aspect of the present invention, a coupling is connected to the exciter, and a clutch, a transmission joint, a speed increaser, a main feed water pump, and a high-pressure condensate connected in series to both shafts of the coupling. It is characterized in that the pump groups are connected in parallel. This makes it possible to combine the effects of claims 5 and 6.

That is, by installing the high-pressure condensate pump or the main feed water pump on the shaft extending the drive shaft of the main turbine / generator, the drive device for the pump can be eliminated. Further, by providing a speed increasing gear, the number of rotations can be increased, and the respective pumps can be downsized. By providing a clutch, the pump can be disconnected or connected to the drive shaft. The speed of rotation of the pump can be changed by connecting the transmission joint to the controller.

Further, when the drive shafts of the main turbine and the generator are separated into two shafts on the extended shaft, and two series each having a capacity of 50% or more are provided, one pump trips for some reason. By activating the other pump, the required water supply flow rate can be secured.

[0035]

BEST MODE FOR CARRYING OUT THE INVENTION A first embodiment of a pump drive device for a nuclear power plant according to the present invention will be described with reference to FIG. In FIG. 1, the same parts as those in FIG. 8 are designated by the same reference numerals, and the description of the overlapping parts will be omitted.

In FIG. 1, the main turbine 3 comprises one high-pressure turbine 3a and three low-pressure turbines 3b of the first to third stages connected in series. The third-stage low-pressure turbine 3b is connected to the generator 4. Exciter 22, coupling via connecting shaft 21 on the extension axis of the drive shaft of generator 4.
23, the main water supply flow rate adjusting valve 16 and the main water supply pump 15 are connected in series.

In this way, the generator 4 and the exciter 22 are connected to the main turbine 3 in which the high-pressure turbine 3a and the first to third-stage low-pressure turbines 3b are directly connected, and the main feed water flow rate adjusting valve 16 is connected via the coupling 23. By connecting the main water supply pump 15 and the feed water pump drive device, an electric motor or a water supply pump drive turbine becomes unnecessary.

Further, in the present embodiment, the main water supply pump
Instead of 15, the high-pressure condensate pump 12 shown in FIG. 8 can be connected. Also in this case, the electric motor, which is the driving device of the high-pressure condensate pump 12, can be eliminated.

The main turbine 3 and the generator 4 are operated at a rotation speed corresponding to the system frequency. This rotational speed is very stable with almost no change. The generator 4 as the load of the main turbine 3 is larger than the main feed water pump 15 and the high-pressure condensate pump 12 by two orders of magnitude, so even if there is a change in the feed water flow rate, the main turbine 3 has a small load change. The rotational speed of the main turbine 3 directly connected to the water supply pump 15 and the high-pressure condensate pump hardly changes. Therefore, according to the present embodiment, the main water supply pump 15 and the high-pressure condensate pump 12 can be operated extremely stably without any drive device.

The main feed water flow rate adjusting valve 16 is used for adjusting the feed water flow rate with this configuration because the pump is a constant flow type use method. The flow rate control by the main feed water flow rate adjusting valve 16 has a sufficient track record and is technically established. The main water supply pump 15 and the generator 4 or the exciter 22 are preferably coupled by a gear coupling in consideration of the thermal expansion of the main water supply pump 15.

If the main turbine 3 trips for some reason, the main feed pump 15 and the high-pressure condensate pump will also stop, but it is necessary to have the auxiliary feed pump 19 in the water supply system and the third high-pressure condensate pump. By holding it, it can be automatically started and water supply to the reactor 1 can be secured. However, the simplest method for driving the main feed water pump 15 and the high-pressure condensate pump 12 is to reduce the probability of failure, but conversely, the main turbine 3 must be stopped due to the failure of the main feed water pump 15 or the high-pressure condensate pump 12. This is also a configuration that cannot be obtained, and it is necessary to combine this configuration as a basic configuration to enhance the reliability of the plant.

Next, a second embodiment of the present invention will be described with reference to FIG. The present embodiment is different from the first embodiment in that a speed increaser 24 is provided between the exciter 22 and the main feed water pump 15 and is connected by a connecting shaft 21. The other parts are the same as those in the first embodiment, and the description thereof is omitted.

The rotation speed of the main water supply pump 15 of the direct coupling type is 1500 rpm in the 50 hertz area and in the 60 hertz area.
It will be 1800 rpm. This rotation speed is not high at all, and the pump itself becomes large. The main water supply pump 15 can be downsized by installing a speed increaser 24 on the direct coupling shaft 21 and increasing the speed.

Next, a third embodiment of the present invention will be described with reference to FIG. The present embodiment is different from the first embodiment in that a clutch 25 is provided between the exciter 22 and the main feed water pump 15 and is connected by a connecting shaft 21. The other parts are the same as those in the first embodiment, and the description thereof is omitted.

When the main water supply pump 15 trips, the main turbine 3 may have to be stopped unless the tripped main water supply pump 15 is isolated.
As a measure to further improve the reliability of the nuclear power plant, a clutch 25 is provided on the connecting shaft 21 of the main water supply pump 15, and when the main water supply pump 15 trips, it can be separated and isolated so that the nuclear power plant can be separated. The reliability can be further improved. It is desirable that the clutch 25 has a function of connecting and disconnecting by remote control.

Next, a fourth embodiment of the present invention will be described with reference to FIG. The present embodiment is different from the first embodiment in that a transmission joint 26 is provided between the exciter 22 and the main water feed pump 15 and is connected by a connecting shaft 21. The other parts are the same as those in the first embodiment, and the description thereof is omitted.

When the main water supply pump 15 is rotated via the gearbox 24 or the clutch 25 shown in FIG. 2 or 3,
The main feed water pump 15 is a constant rotation pump, and the feed water flow rate control is performed by the flow rate adjusting valve, but by using the transmission joint 26 as a coupling, the feed water flow rate control can be performed by the rotation speed control of the pump. . In this case, the transmission joint is connected to the control unit (not shown).

Next, a fifth embodiment of the present invention will be described with reference to FIG. In the present embodiment, two main water supply pumps 15 are arranged in parallel in the first embodiment, these main water supply pumps 15 are connected in parallel to the connecting shaft 21 of the coupling 23, and the coupling 23 is connected to the exciter 22. It is connected to.

Directly connecting the shaft 21 to the coupling 21 after the exciter 22
Main water supply pump with 50% capacity each separated by two shafts
When installing 15 and installing the auxiliary water supply pump 19 with 50% capacity separately, even if one main water supply pump 15 trips for some reason, the auxiliary water supply pump will automatically start and the water supply flow rate Can be provided, and the reliability of the nuclear power plant is improved.

Next, a sixth embodiment of the present invention will be described with reference to FIG. This embodiment is different from the first embodiment in that a coupling 23, a clutch 25, a transmission joint 26, and a speed increaser 24 are connected in series between the exciter 22 and the main feed pump 15 as four types of joints. And then intervened. The other parts are the same as those in the first embodiment, and the description thereof is omitted. When driving the main feed pump 15 and the high-pressure condensate pump 12 by a combination incorporating the above four types of joints,
It can be combined as shown below.

Symbols: Main feed pump 15 is RFP, high-pressure condensate pump 12 is HPCP, coupling 23 is CP, gearbox 24 is SB, clutch 25 is CT, transmission coupling 26 is FC, excitation machine 22 wo EX door to door, (1) EX + CP + RFP (2) EX + CP + SB + RFP (3) EX + CP + CT + RFP (4) EX + CP + FC + RFP (5) EX + CP + SB + CT + RFP (6) EX + CP + SB + FC + RFP (7) EX + CP + CT + FC + RFP (8) EX + CP + SB + CT + FC + RFP (9) EX + CP + HPCP (10) EX + CP + SB + HPCP (11 ) EX + CP + CT + HPCP (12) EX + CP + FC + HPCP (13) EX + CP + SB + CT + HPCP (14) EX + CP + SB + FC + HPCP (15) EX + CP + CT + FC + HPCP (16) EX + CP + S It can be combined in 16 ways of B + CT + FC + HPCP.

Next, a seventh embodiment of the present invention will be described with reference to FIG. In the present embodiment, the fifth and sixth embodiments are combined and the high-pressure condensate pump 12 is connected coaxially with the water supply pump 15. The other parts are the same as those in the first embodiment, and the description thereof is omitted.

Not only is the main feed water pump 15 driven by the drive shafts of the main turbine 3 and the generator 4, but also the high pressure condensate pump 12 is coaxially coupled to the main feed water pump 15, so The number of driving devices can be reduced.

As in the case of the main feed water pump 15, three 50% high-pressure condensate pumps 12 are installed, two of which are driven by the drive shafts of the main turbine 3 and the generator 4, and the remaining 1 The pedestal is driven by an electric motor as in conventional equipment, and the main turbine 3 and generator 4 are used.
When one of the high-pressure condensate pumps 12 that is driven by the drive shaft of the Improve the reliability of.

[0055] water supply pump two high-pressure condensate water pump wo combine example Toshite (1) EX + CP + RFP + HPCP (2) EX + CP + SB + RFP + HPCP (3) EX + CP + CT + RFP + HPCP (4) EX + CP + FC + RFP + HPCP (5) EX + CP + SB + CT + RFP + HPCP (6) EX + CP + SB + FC + RFP + HPCP (7) EX + CP + CT + FC + RFP + HPCP (8) EX + CP + SB + CT + FC + RFP + HPCP field 8 as two Can be combined.

[0056]

By connecting the main feed water pump and the high-pressure condensate pump to the main turbine / generator shaft, the drive unit (electric motor or feed water pump drive turbine) can be deleted, and the construction cost and maintenance of the nuclear power plant can be improved. The cost can be reduced.

If the main feed pump is turbine driven, the turbine, controller and steam lines can be eliminated. Further, when the main water supply pump and the high-pressure condensate pump are driven by an electric motor, the electric motor can be deleted. further,
The power generation efficiency is improved by using the main steam as the drive source.

The drive device reduction targets are the main feed water pump and the high-pressure condensate pump, but depending on the layout of the installation site, it is possible to target only the main feed water pump. Eliminating the driving electric motor means changing the driving energy from electricity to steam, increasing the energy conversion efficiency, and improving the power generation efficiency.

[Brief description of drawings]

FIG. 1 is a block diagram showing a first embodiment of a pump drive device for a nuclear power plant according to the present invention.

FIG. 2 is a block diagram showing a main part of a second embodiment of a pump drive device for a nuclear power plant according to the present invention.

FIG. 3 is a block diagram showing a main part of a third embodiment of a pump drive system for a nuclear power plant according to the present invention.

FIG. 4 is a block diagram showing a main part of a fourth embodiment of a pump drive device for a nuclear power plant according to the present invention.

FIG. 5 is a block diagram showing a main part of a fifth embodiment of a pump drive device for a nuclear power plant according to the present invention.

FIG. 6 is a block diagram showing a main part of a sixth embodiment of a pump drive device for a nuclear power plant according to the present invention.

FIG. 7 is a block diagram showing a main part of a seventh embodiment of a pump drive system for a nuclear power plant according to the present invention.

FIG. 8 is a system diagram showing an outline of a reactor system, a feed / condensate system, and a steam system of a conventional BWR nuclear power plant.

[Explanation of symbols]

DESCRIPTION OF SYMBOLS 1 ... Reactor, 2 ... Main steam pipe, 3 ... Main turbine, 4 ... Generator, 5 ... Main steam flow meter, 6 ... Reactor water level gauge, 7 ... Flow controller, 8 ... Main condenser, 9 ... Condensate pipe, 10 ... Condensate filter,
11 ... Condensate demineralizer, 12 ... High-pressure condensate pump, 13 ... Low-pressure feed water heater, 14 ... Water feed pipe, 15 ... Main feed water pump, 16 ... Main feed water flow control valve, 17 ... Feed water flow meter, 18 ... High pressure Water heater, 19 ...
Auxiliary water supply pump, 20 ... Auxiliary water supply flow rate control valve, 21 ... Connecting shaft, 22 ... Exciter, 23 ... Coupling, 24 ... Speed increaser, 25 ...
Clutch, 26 ... Transmission joint.

Claims (7)

[Claims] 1. A high-pressure condensate pump or a drive shaft of a main feed water pump is connected to an extension axis of the drive shaft of the main turbine, the generator and the exciter, which is directly connected to the main turbine, the generator and the exciter. Pump drive device for nuclear power plant. 2. The pump drive system for a nuclear power plant according to claim 1, wherein a speed increaser is interposed between the exciter and the high-pressure condensate pump or the main feed water pump. 3. The pump drive system for a nuclear power plant according to claim 1, wherein a clutch is interposed between the exciter and the high-pressure condensate pump or the main feed water pump. 4. A pump drive system for a nuclear power plant according to claim 1, wherein a transmission joint is interposed between the exciter and the high-pressure condensate pump or the main feed water pump. 5. A plurality of high-pressure condensate pumps or main feed water pumps are arranged in parallel, and the plurality of high-pressure condensate pumps or main feed water pumps are connected in parallel to a single coupling. A pump drive device for a nuclear power plant according to claim 1, wherein the pump drive device is connected to the exciter. 6. A speed increaser, a transmission joint, a clutch and a coupling are connected in series between the high pressure condensate pump or the main feed water pump and the exciter. Drive unit for nuclear power plant in Japan. 7. A clutch, a transmission joint, a speed increaser, a main feed water pump, and a high-pressure condensate pump group, which are connected in series to both shafts of the coupling, are connected in parallel to the exciter. The pump drive device for a nuclear power plant according to claim 1, wherein