JP3362603B2 - Reactor power control device - Google Patents

Description

Detailed Description of the Invention

[0001]

BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to an output control device for a boiling water nuclear power plant, and more particularly to a reactor output control device suitable for increasing the operation efficiency of nuclear power generation.

[0002]

2. Description of the Related Art The power increase at the time of starting a boiling water reactor (BWR) is as follows: start-up → criticality → reactor water temperature and reactor pressure rise → rated pressure reach → generator inclusion → generator output rise → The procedure is to reach the rated electric output. Of these, the process from generator inclusion to reaching the rated electrical output is called generator output control mode, and the steam supply amount to the steam turbine is controlled by adjusting the opening of the turbine steam control valve. Controls the electrical output of a generator coupled to the turbine (hereinafter referred to as the generator output). Further, in this generator output mode, the opening amounts of the turbine steam control valve and the turbine bypass valve are adjusted to control the amount of steam flowing out of the reactor, and the reactor pressure is kept substantially constant.

In the generator output control mode, as a method of controlling the heat output generated in the reactor (hereinafter referred to as the reactor output), a method of operating a control rod and a coolant flow rate in the core (hereinafter referred to as the core) There is a method of controlling the flow rate). The control rod is filled with a substance that easily absorbs thermal neutrons that cause a fission reaction, and the amount of heat generated by the fission reaction can be controlled by adjusting the insertion amount of the control rod into the core. For example, increasing the amount of control rods inserted into the core reduces the reactor power. Moreover, when the core flow rate is reduced, the reactor power is reduced. This is because part of the cooling water in the core evaporates and changes to steam, so when the core flow rate is reduced, the volume ratio of steam to the total coolant (water + steam) in the core (hereinafter referred to as the void ratio). ) Is increased. That is, since steam has a weaker effect of converting fast neutrons generated in the fission reaction into thermal neutrons causing the fission reaction than water, the reactor output decreases as the void fraction increases.

In the generator output control mode, a target generator output time table is planned in accordance with an appropriate output increase rate (a generator output increase amount per unit time). This test
According to the Bull, the reactor power is increased mainly by controlling the control rods in the low power region and mainly controlling the core flow in the high power region. When controlling the control rod, properly select the amount and timing of pulling out the control rod, and when controlling the core flow rate,
The reactor flow rate is controlled by appropriately changing the rotational speed of the recirculation pump to control the reactor power. During this control, the reactor pressure and reactor water level should be kept almost constant.

Conventionally, in the BWR system, the reactor is operated so that the output of the generator is always at the rated value (100%) after the start operation is completed. The reactor output when the generator output is 100% depends on the seawater temperature that cools the steam turbine condenser, and is almost 100% in summer when the seawater temperature is high.
It is about 5% lower in winter when the seawater temperature is low. Therefore,
Especially in the winter, there is a situation in which the reactor is not producing output even though it still has a thermal margin. Since the operating period of the reactor is predetermined, the heat output is rated 1
If it can be operated at 00%, it is the most efficient and economical . Therefore, conventionally, Japanese Patent Laid-Open No. 61-218996
As described in the publication, there is proposed a technique of operating a nuclear reactor so that the thermal output of the nuclear reactor becomes a set value. In this conventional technique, a deviation signal between the reactor heat output and its set value is obtained,
The deviation signal is used as an output change request signal to adjust the speed of the recirculation pump.

[0006]

When the rated point is set to the set value in order to operate at the reactor heat output of 100% as in the prior art described above, the load of the steam turbine and the generator is It may be larger than the rated operation of 100% generator output. Nuclear power generation facilities such as steam turbines and generators are naturally designed to withstand operation at a rating of 100% heat output, and steam turbine load during rated operation at a generator output of 100%, It can sufficiently cope with 100% heat output operation in which these loads are higher than the generator load.

However, in nuclear power generation where importance is placed on reliability and safety, it is needless to say that it is not preferable to operate the maximum load increase of the steam turbine or generator depending on the seawater temperature. In terms of reliability, it is possible to artificially set the upper limit that is determined by the strength of structural materials such as electric generators and generators. JP-A-61-21 mentioned above
When trying to set this upper limit value in the conventional technology described in Japanese Patent No. 8996, the upper limit value is converted into a heat output value in consideration of the seawater temperature at that time, and the set value of the reactor heat output is converted into this converted value. Since it must be set, the control becomes complicated and there is a risk that the reliability will be hindered.

An object of the present invention is to provide a reactor output control system capable of increasing the operating efficiency of a boiling water nuclear power plant while maintaining high reliability and safety.

[0009]

Means for Solving the Problems In the reactor output control device for controlling the output of the reactor for the above-mentioned purpose, input means for inputting a set value of a generator output and a set value of a reactor output, and the generator output. This is achieved by providing control means for controlling the reactor power to the smaller one of the reactor power corresponding to the set value and the reactor power set value.

The above object is also to provide a reactor power control apparatus for controlling the reactor power to the reactor power upper limit setting value based on a deviation signal between the reactor power and the reactor power upper limit setting value. When the generator output reaches the generator output upper limit set value before the output reaches the reactor output upper limit set value, means for limiting the reactor output to the reactor output corresponding to the generator output upper limit set value is provided. It will be achieved.

Even when the nuclear power plant is set to operate so that the reactor output becomes 100%, when the generator output reaches the upper limit value, the generator output upper limit value is given priority to output. Since it is controlled, safety and reliability are not impaired.

[0012]

BEST MODE FOR CARRYING OUT THE INVENTION An embodiment of the present invention will be described below with reference to the drawings. FIG. 2 is a schematic configuration diagram of a BWR system to which a reactor power control device 60 according to an embodiment of the present invention is applied. A reactor core 2 is provided in the reactor 1,
A plurality of control rods 3 are installed in a distributed manner in the core 2. The control rod drive unit 4 inserts / pulls out the control rod 3 into / from the reactor core 2. The control rod drive unit 4 is controlled by the control rod drive control unit 62 which receives a command from the reactor power control unit 60. . Further, the core 2 has a plurality of neutron flux detectors 7
And a core flow rate detector 8 for detecting the core flow rate is installed on the lower support plate of the core 2.

At the bottom of the nuclear reactor 1, a built-in recirculation pump 5 controlled by a recirculation flow controller 61 is installed. Although only two recirculation pumps 5 are shown in this figure, actually about 10 recirculation pumps 5 are provided.
Are arranged in a ring shape at the bottom of the reactor. The recirculation pump 5 supplies water as a coolant to the core 2 to cool the fuel rods in the core 2. Part of the cooling water becomes steam in the core 2,
It is sent to the steam turbine 14. By changing the number of revolutions of the recirculation pump 5 to change the core flow rate, the reactor power can be adjusted. For example, when the core flow rate increases, the void fraction in the core 2 decreases and the reactor power increases. The recirculation flow rate control device 61 also controls the core flow rate based on a command from the reactor power control device 60.

The steam generated in the reactor 1 is the main steam pipe 6
After being guided to the steam turbine 14, after rotating the turbine blades, the steam is condensed in the condenser 15 and returned to water. A generator 16 is coupled to the steam turbine 14, and electric power is generated from the generator 16. In the main steam pipe 6, a total steam flow rate detector 21 and
A reactor pressure detector 20 and a turbine steam control valve 11a are provided. Part of the steam is the turbine bypass valve 1
It is directly condensed in the condenser 15 without passing through the steam turbine 14 through the turbine bypass pipe 19 provided with 2a. The reactor pressure control device 40 includes a turbine steam control valve controller 1
In 1b, the valve opening of the turbine steam control valve 11a is adjusted to adjust the steam flow rate to obtain a predetermined generator output, and in addition, the turbine bypass valve controller 12b controls the turbine bypass valve 1
It has a function of adjusting the valve opening of 2a to keep the pressure of the reactor 1 constant. The water condensed in the condenser 15 is supplied by the water supply pump 1
Water is supplied to the nuclear reactor 1 through a water supply pipe 18 having a water supply control valve 7 and a water supply control valve 13.

In a region where the reactor output is high, there is a possibility that the heat output of the assembly will be locally increased in the core or the flow rate of the assembly will be reduced, whereby effective heat removal cannot be performed. In order to prevent this, a core performance calculation device 64 that predicts the three-dimensional core power distribution and the critical power ratio after the operation to be performed is provided. This core performance calculation device 64 includes a neutron flux detection signal from the neutron flux detector 7, a flow rate detection signal from the core flow rate detector 8, a total steam flow rate detection signal 45, a reactor pressure detection signal 44, and a target. The valve opening detection signal 47 of the bin steam control valve 11a, the valve opening detection signal 48 of the turbine bypass valve 12a, etc. are input.

The core performance calculation device 64 calculates three-dimensional information (detailed output distribution, aggregate flow rate distribution, etc.) in the core in the current state by performing core nuclear thermal-hydraulic calculation based on these detection information.
(Limit power ratio, etc.) and predictive calculation of the limit power ratio when the reactor power is changed depending on the control rod and core flow rate.
The limit power ratio is an index showing the heat removal state of the assembly, and it is necessary that this does not fall below the limit value at all locations in the core. When this condition is satisfied in the prediction calculation, the core performance calculation device 64 outputs the control confirmation signal 90 to the reactor power control device 60.

The reactor output control device 60 includes an input / output device 6
3 is connected so that an operator can input instructions and numerical data, and information from the reactor power control device 60 is displayed.

FIG. 3 shows a reactor pressure control device 4 shown in FIG.
It is a block diagram of 0. The reactor pressure control device 40 comprises a pressure controller 42 and a turbine speed controller 41. Based on the reactor pressure signal 44 and the reactor pressure set value, the pressure controller 42 calculates a total steam flow rate request signal 46 required to make the reactor pressure follow the set value. The total steam flow rate request signal 46 is also used in the reactor power control device 60.
The turbine speed controller 41 calculates a turbine steam flow rate demand signal 50 based on the turbine speed signal 43 and the turbine speed set value. The smaller value of the total steam flow rate request signal 46 and the turbine steam flow rate request signal 50 becomes the turbine steam control valve opening request signal 47, and the total steam flow rate request 46 and this turbine steam control valve open. The difference from the degree request signal 47 becomes the bypass steam control valve opening degree request signal 48.

FIG. 1 is a block diagram of a reactor power control system 60. The reactor output control device 60 is a negative value pass filter 7 that passes only negative values as they are and outputs positive values as zero.
8a and 78b, a proportional element 72 and an integral element 73 that constitute a PI controller, an upper and lower limit limiter 77, switches 81 and 82, and a control rod operation discriminator that calculates a control rod operation signal.
Consisting of constant 84. In this reactor power control device 60,
From the input / output device 63 of FIG. 2, a control mode signal 88, a flow rate control / control rod control selection signal 91, and a heat output control mode.
Mode reactor output set value (upper limit) 85 (hereinafter referred to as reactor output set value) and heat output control mode generator output set value (upper limit) 86 (hereinafter referred to as generator output set value). )
Is input by the operator. In addition to this, the reactor output control device 60 includes a generator output signal 49, a total steam flow rate request signal 46 corresponding to the reactor output, and a reactor core performance calculation device 6
Control confirmation signal that turns ON when it is predicted that the local core heat removal performance after power increase calculated in 4 can be maintained
0 is input.

Next, the operation of the reactor power control system 60 will be described. The heat output control mode is used as the control mode signal 88.
When the signal for selecting the mode is input, the initial value of the integration element 73 is cleared to zero. For example, the upper limit value of the generator load when operating at 100% heat output (for example, 1
The deviation signal 92, which is obtained by subtracting the generator output 49 from the generator output set value 86 for setting (03%), passes through the negative value pass filter 78a, and then the proportional element 72 and the integral element 7
3 into the PI controller. The output of this PI controller passes through the negative value pass filter 78b, and the compensation signal 97
become.

On the other hand, the value of the total steam flow rate request signal 46 representing the current heat output is subtracted from the reactor power set value 85 (100% in this example), and the reactor power deviation signal 96 is generated. This reactor output deviation signal 96,
The above-mentioned compensation signal 97 is added to form a heat output control mode deviation signal 98. That is, when operating at 100% heat output of the reactor,
When the percentage is exceeded, the deviation signal (which becomes a negative value) corresponding to the exceeded value passes through the PI controller (72, 73) to become the compensation signal 97, which is subtracted from the reactor output deviation signal 96.

The heat output control mode deviation signal 98 thus generated is turned on / off by the switches 81 and 82.
Depending on the state, it is given to the recirculation flow rate control system or the control rod control system. If the control confirmation signal 90 is ON and the flow control / control rod control selection signal 91 indicates that "flow control" is selected, the switch 81 is ON,
The switch 82 is turned off. If the control rod control is selected, the switch 82 is turned on and the switch 81 is turned off.

When the flow rate control is selected by the selection signal 91, the deviation signal 98 is passed through the upper and lower limiter 77 to limit the range, and then as the output change request deviation signal 51 used in the recirculation flow rate control system. Is output. When the control rod control is selected, the deviation signal 98 is input to the control rod operation determiner 84. In the control rod operation determiner 84, when the deviation signal 98 is A <B <0 <C <D, a control rod pull-out signal is output when D ≦ deviation signal 98, and a control rod insertion is input when deviation signal 98 ≦ A. Signal, a control rod stop signal when B ≦ deviation signal 98 ≦ C , a control rod operation signal 52
And outputs it as. This determiner 84 has a hysteresis characteristic, and is stopped or inserted in the section of A <deviation signal 98 <B, C
In the section of <deviation signal 98 <D, a stop or pull-out signal is output.

The reactor power control system 60 functions as follows. When the generator output 49 is smaller than the generator output set value 86, the compensation signal 97 becomes zero by the function of the negative value pass filters 78a and 78b . Therefore, the heat output control mode deviation signal 98 becomes the reactor output deviation 96 itself. If the generator output 49 is always smaller than the generator output set value 86, the reactor output is controlled so that the reactor output set value 85 and the total steam flow rate request signal 46 corresponding to the reactor output match. If 100% is input as the reactor power set value 85, 100% reactor power operation can be realized.

Here, if the generator output 49 becomes larger than the generator output set value 86, the compensation signal 97 becomes a negative value. The absolute value of the compensation signal 97 increases with time unless the deviation signal 92 decreases due to the effect of the integration element 73.
As a result, the control proceeds in the direction in which the total steam flow rate request signal 46 decreases. At this time, the generator output 49 matches the heat output control mode generator output set value 86, and the reactor output becomes smaller than the reactor output set value 85.

In this embodiment, the negative value pass filter is used, but conversely, when a deviation signal obtained by subtracting the generator output set value 86 from the generator output 49 is used, a positive value that makes the negative value zero is used. Even if a structure is adopted in which a compensation signal obtained by performing PI control is subtracted from the reactor output deviation signal 96 by using a value pass filter, the result is exactly the same as the heat output control mode.
A deviation signal 98 is obtained. Further, in the embodiment shown in FIG. 1, the total steam flow rate request signal 46 is used as the signal representing the current reactor output, but other signals may be used as long as they are signals corresponding to the reactor output. Is. Further, in this embodiment, the reactor power set value 85 in the heat output control mode and the generator output set value 8 in the heat output control mode are set.
Although 6 and 6 are input from the input / output device 63, they may be stored in advance in a storage device provided in the reactor power control device 60.

As described above, according to this embodiment,
If the upper limit of the total heat output of the reactor and the upper limit of the electric output of the generator are set, the reactor output corresponding to the generator output upper limit setting value or It is possible to automatically perform the operation that follows the smaller one of the total heat output set value (upper limit value). Therefore, the automatic operation with the rated power of 100% reactor power can be safely realized. As a result, the operating efficiency of the plant can be improved.

FIG. 4 is a block diagram of a reactor power control system 60 according to the second embodiment of the present invention. It is composed of a controller of a generator output control mode for automatically controlling until reaching a value (100%) and a controller of a heat output control mode according to the features of this embodiment. Figure 1
The reactor power control device described in detail in 1. is not suitable for power control that greatly changes the current reactor power. On the other hand, since the reactor output control system 60 shown in FIG. 4 also has a controller of the generator output control mode having a wide output control range, it is possible to control the output in a wide range. As a result,
The reactor output control device 60 can support both the rated operation of heat output and the rated operation of generator output. That is, the control mode is entered by the operator from the input-output device 63 - by de signal 88, one of the generator output constant operation and the reactor thermal power constant operation can select.

FIG. 4 shows a state in which the generator output control mode is selected by the switch. When the generator output control mode is selected, the switch 79 is connected to the lower line, the switch 83 is connected to the left line, and the switch 80 is turned on. When the heat output control mode is selected, the switch 79 is connected to the upper line, the switch 83 is connected to the right line, and the switch 80 is turned off.

In the structure of the heat output control mode, the negative value pass filter 78b in FIG. 1 is replaced with the upper and lower limit limiter 76, but basically both are through passes, so the operation does not change at all. Therefore, the operation in the generator output control mode will be described below.

In the generator output control mode, the reactor output control device 60 is supplied with the generator output time change rate 87 input from the input / output device 63, and a flow control / control rod control selection signal 91. The generator output signal 49, the total steam flow rate request signal 46 that is the output of the reactor pressure control device 40, and the control confirmation signal 90 that is the output of the core performance calculation device 64 are input.

The generator output target setter 70 creates a target generator output time table from the break point information and the generator output time change rate 87 which are input in advance. Target generator output and actual generator output 4
The deviation signal 93 from 9 is for the purpose of improving the stability of control.
After passing through a dead zone 71 that makes the output zero near the zero input, it is input to the PI controller having a proportional element 72 and an integral element 73.

On the other hand, for the purpose of speeding up the control response, the PI corresponding to the reactor output target value which has a quicker response than the generator output.
The output bias is calculated by the following method. First, the advance compensation circuit 74 calculates a generator output target value at a time advanced by a time difference (about 10 seconds) between the reactor output and the generator output. Next, the PI output bias setter 75 outputs a PI output bias corresponding to the reactor output with respect to the advanced generator output target value. The relationship between the generator output and the reactor output does not have to be accurate, and the generator output (%) = PI output bias (%) may be set. PI output bias and PI
The signal added with the controller output is passed through the upper and lower limiter 76, and then the total steam flow rate request signal 46 corresponding to the reactor output is subtracted to generate the generator output control mode deviation signal 9
Set to 5. The subsequent handling of the generator output control mode deviation signal 95 is the same as the heat output control mode deviation signal 98.

Reactor power control device 60 according to the present embodiment
Controls using the reactor output, which has a faster response than the generator output, so the control is stabilized. Further, even if the relation between the generator output and the reactor output is inaccurate, the output change request deviation 51 becomes zero when the generator output target value and the generator output 49 match. It is also excellent in the ability to change the reactor power over a wide range.

The generator output control mode is used for constant generator output operation. When performing a constant heat output operation, first the generator output control mode is used to raise the generator output to the set value. Then, the heat output control mode
Switch to the mode and increase the heat output to the set value. The control logic of the heat output control mode has the function of not only increasing the reactor output but also decreasing it, and when the reactor output exceeds the upper limit value in the generator output control mode, the heat output When switching to the control mode, the generator output can be reduced.

In this embodiment, there is an effect that it is possible to select an operation in which either the 100% reactor output or the 100% generator output is the rated point. Further, since the generator output control mode controller and the heat output control mode controller are partially overlapped, there is an effect of reducing the number of parts.

FIG. 5 is a block diagram of a reactor power control system according to the third embodiment of the present invention. This embodiment is shown in FIG.
Similar to the above embodiment, it is possible to support the rated operation of the reactor output and the rated operation of the generator output. The structure is based on the controller of the generator output control mode shown in FIG. 4, but a generator output target adder 94 is added. The generator output target adder 94 has a control mode signal 88.
Is always in the generator output control mode, the operation of the reactor output control device 60 is the same as that of the embodiment of FIG.

In the heat output control mode, the difference between the reactor power set value 85 and the total steam flow rate request signal 46 corresponding to the reactor power is generated as the reactor power deviation signal 96,
This reactor output deviation signal 96 and generator output set value 86
Then, the generator output control mode deviation signal 95 output from the limiter 76 is input to the generator output target adder 94,
The output of the adder 94 and the generator output time change rate 87 are input to the generator output target setter 70. Generator output 4
The deviation signal 93 is generated by subtracting the output of the setter 70 from 9.

Next, the function of the generator output target adder 94 will be described. When the reactor output deviation signal 96 is a positive value, that is, the reactor output set value 85 is larger than the total steam flow rate request signal 46, and the generator output control mode deviation signal 95 is a value near zero, the generator output is Although the target was reached for the time being, it indicates that the reactor power is lower than the set value. Therefore,
The generator output target adder 94 calculates the increment to increase the generator output by a fixed amount (eg 0.5%),
The generator output target setter 70 is commanded to add this increment to the output. However, if it is determined that the addition result is larger than the generator output set value 86, the increase command is not issued.

The advantage of this embodiment is that the configuration is simpler than that of the embodiment of FIG. Both rated operations can be supported only by adding the generator output target adder 94 to the controller of the generator output control mode.

According to each of the above-described embodiments of the present invention, when the generator output is larger than the upper limit value, the deviation signal of both is input to the proportional-integral circuit, and the deviation between the reactor output target value and the reactor output is input. The signal obtained by subtracting the output signal of the proportional-plus-integral circuit from the signal is used as the reactor output deviation signal as the core flow rate control or control rod control signal.Therefore, the seawater temperature changes in summer and winter and the reactor output and power generation Even if the relationship with the reactor output is unknown, the total heat output of the reactor and the electrical output of the generator can be monitored to prevent both from exceeding the set value (upper limit value).

Further, a generator output control mode controller for controlling the reactor output until the generator output target value of 100% or less is reached, and the reactor output is further increased from the target generator output. Since a heat output control mode controller is provided to control the reactor output so as to match the smaller of the reactor output corresponding to the set value (upper limit value) and the generator output set value (upper limit value), It is possible to realize a control device that can set the output of the reactor at either the generator output set value or the reactor output set value.

Further, the automatic output control device which realizes the operation method in which the rated power is 100% of the reactor output is a generator output control mode controller, which reaches 100% of the generator output when the generators are connected. The reactor output is controlled to 100 %, and after reaching 100 % generator output, the reactor output corresponding to the reactor output upper limit value and the generator output upper limit value is used by using the heat output control mode controller. The reactor power can be controlled to match the lesser of the powers. Therefore, according to these embodiments, it is possible to improve the operating efficiency of the nuclear reactor while maintaining high reliability and safety.

[0044]

According to the present invention, by setting the upper limit value of the electrical output of both the generator setting the upper limit of the total heat output of the reactor, the upper limit of which is operator becomes Limiting Even if not instructed, the reactor output can be controlled to the smaller one of the reactor output corresponding to the generator output upper limit and the reactor output upper limit, and 100% of the reactor output is set as the rated point. the automatic operation of (thermal power 100% operation), it is possible to achieve safe and reliable. As a result, the operating efficiency of the plant can be improved.

[Brief description of drawings]

FIG. 1 is a configuration diagram of a reactor power control device according to a first embodiment of the present invention.

FIG. 2 is a diagram showing a configuration example of a nuclear reactor including a nuclear reactor power control device according to an embodiment of the present invention.

FIG. 3 is a configuration diagram of the reactor pressure control device shown in FIG.

FIG. 4 is a configuration diagram of a reactor power control device according to a second embodiment of the present invention.

FIG. 5 is a configuration diagram of a reactor power control device according to a third embodiment of the present invention.

[Explanation of symbols]

DESCRIPTION OF SYMBOLS 1 ... Reactor, 2 ... Core, 3 ... Control rod, 4 ... Control rod drive part, 5 ... Built-in type recirculation pump, 6 ... Main steam piping, 7 ... Neutron flux detector, 8 ... Core flow detector, 11a ... Turbin steam control valve, 11b ... Turbine steam control valve controller, 12
a ... Turbin bypass valve, 12b ... Turbin bypass valve regulator, 13 ... Water supply control valve, 14 ... Steam turbine, 15
... condenser, 16 ... generator, 17 ... water supply pump, 18 ... water supply pipe, 19 ... turbine bypass pipe, 20 ... reactor pressure detector, 21 ... total steam flow detector, 40 ... reactor pressure control Device, 41 ... Turbin speed controller, 42 ... Pressure controller, 43 ... Turbine speed signal, 44 ... Reactor pressure signal,
45 ... total steam flow rate signal, 46 ... total steam flow rate request signal, 4
7 ... Turbin steam control valve opening request signal, 48 ... Turbin bypass valve opening request signal, 49 ... Generator output, 50 ... Turbin flow rate request signal, 51 ... Output deviation request signal, 52 ...
Control rod operation signal, 60 ... Reactor output control device, 61 ... Recirculation flow rate control device, 62 ... Control rod drive control device, 63 ...
Input / output device, 64 ... Core performance calculation device, 70 ... Generator output target setting device, 71 ... Dead band, 72 ... Proportional element, 73 ...
Integral element, 74 ... Lead compensation circuit, 75 ... PI output bias setter, 76, 77 ... Upper and lower limit limiters, 78a, 78
b ... Negative value pass filter, 79 to 83 ... Switch, 84 ...
Control rod operation determiner, 85 ... Heat output control mode Reactor output set value, 86 ... Heat output control mode Generator output set value, 8
7 ... Generator output time change rate, 88 ... Control mode signal, 8
9 ... Generator output target adder, 90 ... Control confirmation signal, 91
... Flow control / control rod control selection signals, 92, 93 ... Generator output deviation signal, 94 ... Generator output target adder, 95 ... Generator output control mode deviation signal, 96 ... Reactor output deviation signal, 97 … Compensation signal.

─────────────────────────────────────────────────── ─── Continuation of the front page (72) Yoshiyuki Miyamoto, Inventor, 3-1-1, Sachimachi, Hitachi City, Ibaraki Hitachi Ltd., Hitachi Factory (72) Inventor, Yukihisa Fukasawa, 3-chome, Sachimachi, Hitachi City, Ibaraki Prefecture No. 1 Hitachi Ltd., Hitachi Factory (72) Inventor Kazuhiko Ishii 52-1 Omika-cho, Hitachi-shi, Ibaraki Hitachi Ltd. Omika Factory (56) Reference JP-A-6-27278 (JP, A) ) JP 61-90094 (JP, A) JP 2-24598 (JP, A) (58) Fields investigated (Int.Cl. ⁷ , DB name) G21D 3/00 G21D 3/12 G21C 7 / 08

Claims (3)

(57) [Claims] 1. A reactor output control device for controlling the output of a nuclear reactor, wherein a proportional-integral means for taking in a deviation signal of the generator output and performing a proportional-integral process only when the generator output is larger than a heat-output control mode generator output set value. And heat output control mode Equivalent to reactor power set value and reactor power
Determined from the deviation signal between a signal to the signal obtained by subtracting the output signal of the proportional integrating means as heat output control mode error signal
Therefore, an output control means for outputting a control signal of the recirculation flow rate control system or the control rod control system based on the heat output control mode deviation signal is provided. 2. The flow control selection signal according to claim 1,
When input, the output control means controls the heat output.
The mode deviation signal passes through a limiter that limits its upper and lower limits.
The output signal as a control signal for the recirculation flow control system.
A reactor power control device characterized by the following. 3. The control rod control selection signal according to claim 1.
Is input, the output control means causes the thermal output control
Pull out the control rod based on the magnitude of the control mode deviation signal
Signal, control rod insertion signal, control rod stop signal, control rod control
Reactor exit characterized by being output as a system control signal
Force control device.