JPH0727065B2 - Nuclear reactor plant - Google Patents

Description

Description: TECHNICAL FIELD The present invention relates to a nuclear reactor plant, and more particularly to a nuclear reactor plant suitable for application to a nuclear reactor whose core flow rate is controlled by feed water.

[Conventional technology]

At present, in nuclear power plants, reduction of construction cost is a major issue. For example, a new type of power plant equipped with an internal pump is being developed for a boiling water nuclear power plant (hereinafter referred to as a BWR power plant). The new power plant will make the containment vessel compact because it eliminates the need for a recirculation system in an already constructed BWR power plant.

However, it is desired to make the reactor containment vessel more compact. An example in which the reactor containment vessel can be made compact is shown in JP-B-43-23117 and JP-B-49-16920, although not directly mentioned in the respective publications.

The BWR power plant shown in JP-B-43-32117 is
A part of the feed water is supplied into the reactor pressure vessel via the feed water sparger, and the remaining feed water is used as driving water for a jet pump that supplies cooling water to the core.
Here, the feed water introduced to the feed water sparger is used for controlling the water level in the reactor pressure vessel. Further, in this BWR power plant, the cooling water discharged from the feed water sparger and the cooling water separated by the steam-water separator above the core (both cooling water are in a mixed state) are (Installed in the reactor pressure vessel), it is cooled by the feed water used as driving water for the jet pump, and then sucked into the jet pump. The cooling of the suction water of the jet pump by this heat exchanger is intended to prevent the cavitation of the jet pump due to the boiling of the cooling water in the jet pump.

JP-B-49-16920 has a jet pump that uses cooling water discharged from a recirculation pipe as driving water and a jet pump that uses a part of the feed water as driving water in order to adjust the core flow rate. A BWR power plant is described which supplies the remaining feedwater from a feedwater sparger into the reactor pressure vessel. This advertisement gazette also shows that the cooling water sucked by the jet pump from the water supply sparger through the descending annular flow path is cooled as in JP-B-43-23117 (columns 6, 37 to 44). ).

[Problems to be Solved by the Invention]

In each of the conventional examples described above, the heat exchanger is installed in the reactor pressure vessel, and the cooling water sucked by the jet pump in this heat exchanger is cooled by the jet pump driving water that is a part of the feed water. The temperature difference between the cooling water sucked by the jet pump flowing into the heat exchanger and the jet pump driving water is 5 to 60.
The flow rate on the cooling side is about 10 times the flow rate on the cooling side. Therefore, it is necessary to install a large heat exchanger in the reactor pressure vessel, which complicates the structure inside the reactor pressure vessel.

A first object of the present invention is to provide a nuclear reactor plant capable of simplifying the structure of the nuclear reactor.

It is a second object of the present invention to provide a reactor plant and a feed water heating device capable of preventing the occurrence of cavitation in the jet pump and greatly changing the reactor output by controlling the core flow rate.

A third object of the present invention is to provide a nuclear reactor plant capable of suppressing an increase in temperature of feed water sucked by a jet pump.

A fourth object of the present invention is to provide a reactor plant capable of lowering the temperature of the feed water supplied to the feed water sparger with simple equipment.

A fifth object of the present invention is to provide a reactor plant and a reactor feedwater flow rate control device capable of easily controlling the water level.

A sixth object of the present invention is to provide a reactor plant and a reactor power control device that can easily control the core flow rate.

A seventh object of the present invention is to provide a reactor plant and a reactor protection device capable of suppressing a sudden change in water level during abnormal times.

An eighth object of the present invention is to provide a reactor plant and a reactor protection device that can keep the operating state within the allowable range.

A first object of the present invention is to provide a reactor plant and a reactor feedwater temperature control device capable of improving the responsiveness of turbine output.

A tenth object of the present invention is to provide a reactor plant and a general control device capable of stably controlling a plurality of control means in response to a load change request signal while avoiding mutual interference.

[Means for Solving the Problems]

In order to achieve the first object, there is provided water supply means for guiding a part of the water supply to the jet pump as driving water and for guiding the rest of the water supply to the water supply sparger at a lower temperature than the water supplied to the jet pump.

The second object can be achieved by providing a control means for adjusting the temperature difference between the feed water introduced as drive water to the jet pump and the feed water introduced to the feed water sparger.

A third object is to provide a baffle cylinder which is disposed inside the feed water sparger and extends toward the jet pump, and which suppresses the mixture of the high temperature coolant discharged from the core and the feed water discharged from the feed water sparger. Is achieved.

A fourth object is to provide a feed water heater in the first pipe line that guides the feed water to the jet pump as driving water, and to connect the second pipe line that guides the feed water to the feed water sparger to the first pipe line upstream of the water feed heater. It is achieved by mounting. .

A fifth purpose is to determine the water level based on the three factors of the measured water level in the reactor vessel, the first flow rate of feed water supplied into the reactor vessel, and the second flow rate of steam discharged from the reactor. Control the flow rate of the feed water that is lower in temperature than the feed water that is guided as driving water to the jet pump in the reactor vessel and that is led to the feed water sparger in the reactor vessel so that It can be achieved by providing means.

In order to achieve the sixth object, the reactor output control means for outputting a control signal for adjusting the reactor power, and the first conduit for guiding the driving water for guiding a part of the feed water to the jet pump are also heating means. And a flow rate adjusting means for adjusting the feed water flow rate in the first pipeline based on the control signal.

A seventh object is to modify at least one of the first control signal for adjusting the reactor power when the trip signal is input and the second control signal for maintaining the water level in the reactor vessel at a predetermined level. It is achieved by providing means.

The purpose of FIG. 8 is to provide the first pipe provided in the first conduit for guiding a part of the feed water as driving water to the jet pump through the heating means.
Based on the respective feed water temperatures measured by the second thermometer provided in the second pipe that guides the rest of the feed water to the feed water sparger and the reactor output measured by the output detector, Means for determining whether the operating condition has reached the allowable limit, and modifying the control signal for adjusting the reactor power when the operating condition has reached the allowable limit so that the operating condition does not exceed the allowable limit. It can be achieved by including means.

A ninth object is to have means for extracting a predetermined change component from the output of the means for detecting the rotation speed of the turbine, and means for controlling the heating amount of the heating means for heating the feed water based on the extracted change component. It can be achieved by providing.

A tenth object is a means for obtaining a fluctuation cycle and a fluctuation width of the input load change request signal, and a control device which should output the control information signal among a plurality of control devices according to the fluctuation cycle and the fluctuation width. It is achieved by providing means for selecting from.

[Action]

According to the first feature, the temperature of a part of the feed water introduced to the feed water sparger is set lower than the temperature of the rest of the feed water introduced to the jet pump, so that the temperature of the cooling water sucked into the jet pump is lowered. Means do not have to be provided in the reactor.

In the second feature, the temperature difference control means can keep the difference between the temperature of the feed water introduced to the jet pump and the temperature of the feed water introduced to the feed water sparger at a predetermined temperature or higher, so that the occurrence of the cage in the jet pump is prevented. it can.

According to the third feature, by installing the baffle cylinder, it is possible to prevent the high temperature coolant in the reactor vessel from mixing with the low temperature feed water discharged from the feed water sparger, and suppress the temperature rise of the feed water sucked by the jet pump. To be done.

According to the fourth feature, since the feed water introduced to the feed water sparger is shunted on the upstream side of the feed water heater through which the feed water as the driving water led to the jet pump passes, the feed water heater installed in the plant is The temperature of the feed water supplied to the feed water sparger can be lowered with a simple facility for bypassing this.

In the fifth feature, the water level in the reactor vessel can be controlled by controlling the feed water flow rate of the system that supplies water to the feed water sparger, which is one of two systems that supply water to the reactor. Therefore, the water level can be easily controlled.

According to the sixth feature, the reactor output control can be performed by controlling the feed water flow rate of the system that supplies the feed water as the driving water to the jet pump, which is one of the two water supply systems described above. Easy to control.

According to the seventh feature, when the trip signal is generated, at least one of the control signal for adjusting the reactor power and the control signal for adjusting the water level is corrected. Therefore, the control signal corrected according to the abnormal state is used. This makes it possible to control the flow rate of water supply, and to suppress rapid fluctuations in the water level in the reactor vessel during abnormal times.

According to the eighth feature, the temperature of the water supplied to the water sparger,
When the operating condition of the reactor reaches the allowable limit based on the feed water temperature and the reactor power output to the jet pump, the control signal for adjusting the reactor power is modified so that the operating condition does not exceed the allowable limit. The flow rate of the feed water introduced to the jet pump can be adjusted by the modified control signal, and the operating state of the reactor can be maintained within the allowable range.

According to the ninth feature, since the heater of the feedwater heater, that is, the amount of extracted steam is controlled based on the predetermined change component extracted from the measured turbine rotation speed, the amount of steam supplied to the turbine is controlled. It is possible to quickly adjust in a short time.

According to the tenth feature, since an appropriate control device is selected from among a plurality of control devices according to the fluctuation cycle and the fluctuation width of the load change request signal, mutual interference between the control devices can be avoided. .

〔Example〕

First, a BWR power plant which is a preferred embodiment of the present invention
This will be described below with reference to the drawings.

The core 2 is arranged in a cylindrical core shell 3 provided in the reactor pressure vessel 1, and is loaded with a large number of fuel assemblies. A plurality of control rod drive devices 5 in which a plurality of control rods 4 are inserted in the core 3 are individually connected to the control rods 4. A plurality of jet pumps 6 having a throat section 7,
It is arranged in an annular space formed between the reactor pressure vessel 1 and the core shell 3. The throat portion 7 is located above the core 2. The water supply sparger 8 is installed in the reactor pressure vessel 1 above the throat section 7, and has a header and a large number of injection nozzles for discharging the water supply. The injection nozzle. It is installed in Hedda and faces the jet pump 6. The water supply sparger 8 is installed below the position where the water supply pipe 33 is attached to the reactor pressure vessel 1.
This is to ensure that the low temperature feed water ejected from the feed water sparger 8 is sucked into the jet pump 6 while keeping the temperature as low as possible. A cylindrical riser portion 9 is provided on the upper end of the core shroud 3. The diameter of the riser portion 9 is
It is the same as the diameter of the core shell 3. The upper end of the riser portion 9 is located above the installation level of the water supply sparger 8. The water supply sparger 8 is arranged around the riser unit 9. Steam separator 10 is a stand pipe
It is attached to the top of the riser section 9 via 11.

Next, the structure around the turbine will be described. The shafts of the high-pressure turbine 13, the low-pressure turbine 14 and the generator 15 are connected to each other. However, the generator 15 is detachably connected to the low-pressure turbine 14. The high-pressure turbine 13 is connected to the reactor pressure vessel 1 by a main steam pipe 17, and the low-pressure turbine 14 is connected to the high-pressure turbine 13 by a main steam pipe 18. The condenser 16 is connected to a steam outlet (not shown) of the low pressure turbine 14.

A steam stop valve 19 and a steam control valve 20 are provided in the main steam pipe 17. The bypass pipe 21 having the bypass valve 22 has one end connected to the main steam pipe 17 at an upstream side of the steam stop valve 19.
The other end is connected to the condenser 16. The water supply pipe 30
Connected to condenser 16. This water supply pipe 30 has a condenser 16
A condensate pump 23, a condensate demineralizer 24, a plurality of low-pressure feed water heaters 25, and a plurality of high-pressure feed water heaters 26 are provided in this order from the side toward the reactor pressure vessel 1 side. At a branch point 34 on the downstream side of the high-pressure feed water heater 26, the water supply pipe 30 is branched into a water supply pipe 31 (jet pump driving water pipe) and a water supply pipe 33 (supply water sparger supply pipe). A water supply pump 28, a final-stage high-pressure water supply heater 27, and an opening / closing valve 35 are sequentially provided in a water supply pipe 31.

In FIG. 1, the water supply pump 28 arranged downstream of the branch point 34 and also downstream of the high-pressure water heater 27 is
As shown in the figure, it may be arranged upstream of the high-pressure feed water heater 27. As shown in FIG. 2, the feed water pump 28 is replaced by a high pressure feed water heater 27.
By arranging it on the upstream side of the water supply pump 28, the water supply pressure applied to the suction side of the water supply pump 28 is controlled by the water supply pump 29 described later.
It becomes equal to the water supply pressure on the suction side of. This is because the pressure loss due to the high pressure feed water heater 28
This is because it is possible to avoid the influence on the succession side of.

The water supply pipe 31 is introduced into the reactor pressure vessel 1, and its tip is a nozzle 32 that opens above the throat portion 7 of the jet pump 6. The water supply sparger 8 is located above the nozzle 32. The other water supply pipe 33 is connected to the water supply sparger 8. Water supply pump 29, water supply pipe 33
Is installed in.

The low-pressure feed water heater 25 and the high-pressure feed water heaters 26 and 27 each introduce part of the steam generated in the reactor pressure vessel 1 to heat the feed water. That is, the shell inner space of the low-pressure feed water heater 25 is connected to the low-pressure turbine 14 by the extraction pipe 36 having the extraction valve 37. The shell inner space of the high-pressure feed water heater 26 is connected to the high-pressure turbine 13 by an extraction pipe 38, and the shell inner space of the high-pressure feed water heater 27 is connected to the high-pressure turbine 13 by an extraction pipe 40. The extraction valve 39 is connected to the extraction pipe 38,
A bleed valve 41 is provided in the bleed pipe 40. Low pressure feed water heater 25,
Each shell inner space of the high-pressure feed water heaters 26 and 27 is connected to the condenser 16 by a drain pipe 42. Further, the water supply pipe 31 and the water supply pipe 33 have a bypass pipe 43 having an opening / closing valve 44.
Have been contacted by. The bypass pipe 43 has one end connected to the water supply pipe 33 on the downstream side of the water supply pump 29, and the other end connected to the water supply pipe 31 between the water supply pump 28 and the opening / closing valve 35.

The following are installed as detectors.
50 is a water level gauge that detects the reactor water level ( _LR ) in the reactor pressure vessel 1, 51 is a flow rate that detects the feed water flow rate (jet pump drive water flow rate: W _J ) in the water supply pipe 31 that drives the jet pump 6. In total, 52 is the reactor pressure vessel 1 from the feed water sparger 8.
A flow meter for detecting the feed water flow rate (feed water sparger flow rate: W _S ) in the water feed pipe 33 supplied inside, and 53 is a flow meter for detecting the main steam flow rate (W _M ) flowing in the main steam pipe 17. . The water level meter 50 is in the reactor pressure vessel 1, and the flow meter 51 is the water supply pipe 31.
The flowmeter 52 is connected to the water supply pipe 33, and the flowmeter 53 is connected to the main steam pipe.
Mounted individually on 17. Further, 54 is a thermometer attached to the water supply pipe 31 to detect the temperature (T _J ) of the water supply (jet pump drive water) in the water supply pipe 31, 55 is attached to the water supply pipe 33 and the water supply in the water supply pipe 33 ( Water supply sparger water)
Temperature detector (T _S ), 56 is an output detector installed in the core 2 to detect the reactor power (Q _R ), 57 is installed in the main steam pipe 17 and main steam pressure (P S) A pressure gauge for detecting _S ) and 58 are tachometers for detecting the rotational speed ( _NG ) of the turbine.

The state quantities detected by the water level meter 50, the flow meters 51, 52 and 53, the thermometers 54 and 55, and the output detector 56 are transmitted to the water level / output control device 70. The water supply / output control device 70 controls the water supply pumps 28 and 29 and the opening / closing valves 35 and 44. Pressure gauge 57
Each state quantity detected by the tachometer 58 is transmitted to the turbine controller 80. The turbine control device 80 controls the steam stop valve 19, the steam control valve 20, and the bypass valve 22. As another control device, the feed water temperature control device 46 for adjusting the opening degree of the extraction valve 41 based on the output signals of the thermometers 54 and 55, the extraction valves 37, 39 and 41 based on the output signal of the turbine control device 80. An extraction valve control device 90 for controlling the opening degree and a control rod drive device control device 100 for controlling each control rod drive device 5 are provided. Reference numeral 47 is a signal selector for transmitting the former output signal of the output signals of the feed water temperature control device 46 and the extraction valve control device 90 to the extraction valve 41 with priority. Further, there is a general control device 60 as a device that supervises the water level / output control device 70, the turbine control device 80, the extraction valve control device 90, and the control rod drive device control device 100.

The outline of the operation of the BWR power generation plant of the present embodiment having the above configuration is shown below.

The control of the reactor output in this embodiment is performed by moving the control rod 4 into and out of the core and adjusting the core flow rate (flow rate of cooling water supplied to the core 2).

The steam generated in the core 2 rises in the riser section 9 and is introduced into the steam separator 10. The steam separator 10 separates the cooling water entrained in the steam. The separated cooling water flows down into the annular downward flow passage 45 formed between the riser portion 9 and the reactor pressure vessel 1. On the other hand, the steam from which the cooling water has been removed by the steam separator 10 is guided to the high-pressure turbine 13 through the main steam pipe 17, and further to the low-pressure turbine 14 through the main steam pipe 18. During normal operation of the plant, the steam stop valve 19 and the steam control valve 20 are open, and the bypass valve 22 is closed. The steam is used for the high pressure turbine 13 and the low pressure turbine 14.
To rotate. The generator 15 connected to these turbines also rotates at the same time. The steam discharged from the low-pressure turbine 14 to the condenser 16 is condensed in the condenser 16 into water.
This condensed water is supplied again as feed water into the reactor pressure vessel 1 through the feed water pipes 30, 31 and 33. That is, the condensed water in the condenser 16, that is, the feed water is boosted by the condensate pump 23 and purified by the condensate demineralizer 24, and then each of the low-pressure feed water heater 25 and the high-pressure feed water heater 26. It reaches the branch point 34 through the inside of the heat transfer tube. Low-pressure feed water heater 25 and high-pressure feed water heater 26
The steam extracted from the low-pressure turbine 14 and the high-pressure turbine 13 through the extraction pipes 36 and 38 is supplied to the shell inner space. The flow rate of each extraction steam is controlled by the extraction valves 37 and 39. The feed water introduced into the heat transfer pipes of the feed water heaters 25 and 26 is heated by the extraction steam supplied to each shell inner space to be heated. The extracted steam is condensed in the shell inner space by heating the feed water and becomes drain. This drain is returned to the condenser 16 by the drain pipe 42.

Now, a part of the water supply that has reached the branch point 34 passes through the water supply pipe 33 and is pressurized by the water supply pump 29, and then the water supply sparger 8
Is discharged into the annular downward flow passage 45 in the reactor pressure vessel 1. The cooling water discharged from the feed water sparger 8 also contributes to the adjustment of the water level in the reactor pressure vessel 1 as described later.

On the other hand, the rest of the feed water that has reached the branch point 34 is boosted by the feed water pump 28, guided into the heat transfer pipe of the high-pressure feed water heater 27 and raised in temperature, and then discharged from the nozzle 32 into the jet pump 6. . By discharging the water supply from the nozzle 32 into the jet pump 6, the cooling water present in the annular descending passage 45 is sucked into the jet pump 6. The high temperature steam extracted from the high pressure turbine 13 through the extraction pipe 40 is supplied to the shell inner space of the high pressure feed water heater 27. The extraction pipe 40 extracts steam from the high-pressure turbine 13 at a position upstream of the extraction pipe 38. Therefore, the temperature of the steam extracted in the extraction pipe 40 is
The temperature is higher than the temperature extracted by the extraction pipe 38. The extracted steam introduced into the shell inner space of the high-pressure feed water heater 27 heats the feed water flowing in the heat transfer tube and is condensed into drain.
This drain is also guided to the condenser 16 by the drain pipe 42.

The water supply flowing through the water supply pipe 31 contributes as driving water for the jet pump 6. From the jet pump 6, the feed water discharged from the nozzle 32 and the cooling water in the annular downward flow path 45 sucked into the jet pump 6 are discharged in a mixed state. The cooling water discharged from the jet pump 6 is
Guided from below.

The present embodiment described above includes (I) use of two types of feed water having different temperatures, (II) core flow rate control (fine control output control compared to control rods) and water level control by feed water, and (III) abnormal time Protection control in (4) and (IV) control to improve the responsiveness of the generator output. These will be described in detail in the following order.

(I) Utilization of Two Types of Water Supply with Different Temperatures In this embodiment, a part of the water supply divided upstream of the high-pressure water supply heater 27 is not passed through the high-pressure water supply heater 27 but is supplied from the water supply sparger 8 to the reactor pressure vessel. 1 and the rest of the feed water is fed into the reactor pressure vessel 1 (specifically, the jet pump 6) via the high-pressure feed water heater 27. Therefore, the water supply pipe
The temperature of the water supply supplied to the water supply sparger 8 by 33 is
The temperature of the feed water supplied as driving water into the jet pump 6 by the water feed pipe 31 is lower than the temperature of the high-pressure feed water heater 27 because it is not heated. Conversely, the feed water used as the driving water for the jet pump 6 has a higher temperature than the feed water supplied to the feed water sparger 8 as it is heated by the high-pressure feed water heater 27. However, the temperatures of the feed water supplied to the jet pump 6 and the feed water sparger 8 are both lower than the temperature of the cooling water in the reactor pressure vessel 1.
The temperature difference between the supply waters is adjusted to a predetermined value by the opening control of the extraction valve 41 by the supply water temperature control device 46. As shown in FIG. 3, the water temperature controller 46 includes a temperature estimator 46A,
It has adders 46B and 46C, a controller 46D and a function generator 46E. The temperature estimator 46A measures the temperature T _{S of the} water supply (referred to as water supply sparger water) in the water supply pipe 33 measured by the thermometer 55.
Based on the above, the temperature T _JSC of the suction water flow 45A (FIG. 4) sucked by the jet pump 6 is determined. The difference ΔT between the temperature T _J and the temperature T _JSC of the feed water (referred to as jet pump driving water) in the feed water pipe 31 measured by the thermometer 54 is obtained by the adder 46B. Function generator 46E stores the characteristic L ₃ relationship between reactor power Q _R and the set temperature difference [Delta] T _0. Setting the temperature difference [Delta] T ₀ is determined in correspondence with the reactor power Q _R. Characteristic L
Reference numeral ₃ is located below an alarm generation line L _{2 in} FIG. 10 which will be described later, and is set so that the temperature difference between the jet pump driving water and the feed water sparger water becomes a required value. The function generator 46E is the reactor output Q measured by the output detector 56.
_The set temperature difference ΔT ₀ corresponding to _R is output. Function generator 46E
The set temperature difference ΔT ₀ output from and the temperature difference ΔT output from the adder 46B are input to the adder 46C. Adder 4
At 6C, the deviation T _X between the set temperature difference ΔT ₀ and the temperature difference ΔT is calculated.
The controller 46D outputs the opening signal ST ₁ to the extraction valve 41 based on the deviation T _X. The opening signal ST ₁ is transmitted to the signal selector 47. The signal selector 47 gives priority to the opening signal ST ₁ over the opening signal ST ₂ which is the output of the extraction valve control device 90, and the extraction valve 41
When the opening signal ST ₂ is not output, that is, the opening signal ST ₂ is a signal V whose level is 0, which will be described later.
When it is a signal corresponding to ₄ , the opening signal ST ₁ is selected and transmitted to the extraction valve 41. That is, the extraction valve opening controller 91 (FIG. 14) of the extraction valve control device 90 functions (adder of FIG. 14).
Except when the deviation signal u which is the output of 91A is negative), the opening degree of the extraction valve 41 is adjusted by the opening degree signal ST ₁ which is the output of the feed water temperature control device 46. In this way the nozzle 3
Since the feed water sparger water having a temperature lower than the jet pump driving water discharged from 2 by a predetermined temperature difference is supplied from the feed water sparger 8 into the reactor pressure vessel 1, the temperature of the cooling water that descends through the annular descending passage 45. The cooling water having a low temperature is sucked into the jet pump 6 by the water supplied from the nozzle 32. Therefore, it is possible to prevent the occurrence of the cavitation of the jet pump 6. The temperature difference between the above-mentioned two supply waters is controlled so as to satisfy a predetermined value during normal operation. However, if the temperature difference between the two water supplies satisfies a predetermined value, the temperature of the water supply flowing through the water supply pipe 31 may not be significantly increased. What is important in this respect is the enthalpy of the cooling water which is further separated by the steam separator 10 based on the enthalpy of the cooling water at the core inlet required for the core characteristics and flows down into the annular downward flow passage 45, and the water supply pipe 31. The temperature of the water supply in the water supply pipe 31 is determined in consideration of the enthalpy of each water supply in 33 and 33. The water supply temperature in the water supply pipe 31 thus determined is adjusted by controlling the opening degree of the extraction valve 41 so that the temperature of the water supply water in the water supply pipe 33 becomes higher by a predetermined value.

As described above, by providing a temperature difference in the feed water flowing in the feed water pipes 31 and 33 as in the present embodiment (the feed water temperature in the feed water pipe 33 is low), the reactor pressure vessel as in the conventional example is obtained. It is not necessary to provide a heat exchanger in the reactor pressure vessel 1
The internal structure can be significantly simplified. Therefore, the work of mounting the core structure in the reactor pressure vessel 1 is significantly facilitated. Since it is not necessary to provide a heat exchanger in the reactor pressure vessel 1, the reactor can be downsized. Furthermore, the maintenance and inspection work of the heat exchanger in the reactor pressure vessel 1 activated to a high level which is required in the conventional example is eliminated. In addition, in this embodiment,
The difference between the temperature of the water supply in the water supply pipe 31 and the temperature of the water supply in the water supply pipe 33 due to the fact that the high-pressure water supply heater 27 necessary for heating the water supply to the outside of the reactor pressure vessel 1 is or is not executed. Can be increased, and the temperature of the cooling water sucked into the jet pump 6 (cooling water in the annular descending flow path 45) can be significantly reduced as compared with the conventional example.

Therefore, the present embodiment is different from the conventional example in the jet pump 6.
The range in which the occurrence of cavitation can be prevented significantly increases, and the reactor power can be significantly changed by controlling the core flow rate. In this embodiment as described above, the load following operation can be easily performed, and the load following operation can be largely performed by the core flow rate control. By the way, in the conventional example, there is a limit to the setting of the difference between the temperature of the jet pump driving water and the cooling water temperature of the annular descending passage, and the annular temperature of the jet pump driving water using the heat exchanger installed in the reactor pressure vessel is limited. The cooling effect of the cooling water in the descending passage is also small, and the temperature of the cooling water sucked by the jet pump is not significantly reduced. Therefore, in the conventional example,
The range in which the jet pump can prevent the cavitation is narrower than that of the present embodiment, and it is not possible to cope with the occurrence of the cavitation when the reactor output is significantly changed in the load following operation. Furthermore, since the water supply pipe 33 is branched on the upstream side of the high-pressure water supply heater 27, which is a device required for the water supply system, the temperature of the water supply in the water supply pipe 33 is made lower than that in the water supply pipe 31. There is no need for a cooling device, and there is no need to install a new heater for heating the water supply in the water supply pipe 31. In the present embodiment, it is not necessary to provide a recirculation system having a recirculation system pipe or an internal pump having a complicated structure, which is conventionally installed in a containment vessel surrounding the reactor pressure vessel 1, and the water supply pump 28 and Since the 29 is installed outside the storage container, the storage container can be downsized and the internal structure of the storage container can be simplified. Since the recirculation system and the internal pump are not required, the maintenance and inspection of these are not necessary, so that the maintenance and inspection time of the reactor plant is shortened.

In the present embodiment, the water supply pipe 33 is branched upstream of the final-stage high-pressure feed water heater 27, but for the BWR power plant having different absolute values of the rated output, the final-stage high-pressure feed water heater 27 is used as necessary. The water supply pipe 33 may be branched from the water supply pipe 30 on the upstream side of the two-stage or three-stage upstream side water supply heater. As a result, the temperature of the water supply in the water supply pipe 33 can be made significantly lower than the temperature of the water supply in the water supply pipe 31 as compared with the above-described embodiment. Some of the feedwater heaters needed for a reactor plant,
In particular, since the high-pressure feed water heater at the final stage is bypassed and a part of the feed water is guided to the feed water sparger 8, the feed water to be fed to the feed water sparger 8 can be supplied to the jet pump 6 as drive water by a simple facility. The temperature can be lowered.

In order to improve the thermal efficiency of the reactor plant, the extraction valve
It is desirable to set the opening degree so that 41 is close to the fully opened state, and maintain this state to prevent large opening degree control.
Therefore, the reactor power Q _R of the bleed pipe 40 of the inlet so that the temperature in the water supply pipe 31 in the feed water heater 27 outlet becomes higher by setting the temperature difference [Delta] T ₀ than the temperature in the water supply pipe 33 in accordance with the It is desirable to set the connection position and the extraction steam amount of the extraction pipe 40.

The use of two types of water supply with different temperatures in this embodiment is
This is brought about by the following examination results.

According to the conventional core nuclear heat design, the core flow rate W _C driven by the recirculation system is the total feed water flow rate W _FW (main steam flow rate W during steady operation).
(Equal to _MS ) about 7 times. Therefore, based on the conventional core design, even if all the feed water is directly directed to the jet pump 6 as driving water, the jet pump 6 needs to have an M ratio of about 6.0 determined by the following equation. .

However, in practice, a part of the total feed water flow rate needs to be diverted to the feed water sparger 8 at the branch point 34 in order to control the reactor water level. This is because it is necessary to control the reactor water level (also called the reactor water level) independently of other variables. It is assumed that 1/3 of the total water supply is distributed to the water supply sparger 8 and the remaining 2/3 is distributed to the jet pump 6. Assuming that the feed water sparger flow rate is W _S , the jet pump drive water flow rate is W _J , and the core nuclear heat design is the same, the following equation holds.

Therefore, the required M ratio is 9.5. By the way, the M ratio of a BWR jet pump with a recirculation system is around 2.5 at the rated output.

To increase the M ratio, the following four methods are basically considered.

(1) The pressure of the driving water for the jet pump is increased to increase the flow velocity of the driving water flowing through the jet pump funnel.

(2) Reduce the required discharge pressure of the jet pump.

(3) Decrease the temperature of the suction water flow sucked by the jet pump.

(4) Use a multi-stage jet pump.

Here, the characteristics of the jet pump are shown in FIG.

Due to the jet pump driving water flow 31A, the suction water flow (the cooling water flow in the annular descending flow path 45) 45A is turned into the throat section 7.
After being sucked in and mixing the water streams, they are guided to the outlet 6B of the jet pump 6 through the drain user 6A of the jet pump 6. FIG. 4 further shows the pressure P _S of the suction water flow 45A and the pressure P _S of the jet pump driving water flow at this time.
The change in _D is shown along the flow direction.

At the throat section 7, the pressure of both water flows becomes the minimum pressure P _M ,
After that, the pressure of the water flow rises due to the effect of Diff User 6A,
A discharge pressure P _O is obtained at the outlet 6B. By the way, in order to increase the M ratio, if the measure (1) is adopted and a remarkably large pressure P _D , in other words, a driving water flow 31A having a remarkably high flow velocity is used, the saturation water flow 45A is saturated at the throat portion 7. Lower than that, and bubbles are generated (called a cavitation). When the cavitation occurs, the efficiency of the jet pump 6 is significantly reduced, and the equipment may be damaged. Therefore, it is important to prevent cavitation and increase the M ratio.

The method of increasing the M ratio without causing the cavitation in the jet pump 6 is because the generation of the cavitation is caused by boiling caused by the pressure P _M of the throat section 7 being lower than the saturation pressure of the suction water flow 45A. The temperature of water stream 45A should be low enough so that it does not boil at pressure P _M. That is, the above method (3) is adopted. A conventional example based on this idea is the above-mentioned Japanese Patent Publication No. 43-23117 “Reactor Apparatus”. In this conventional example, as a means for lowering the temperature of the suction water flow, a heat transfer tube group of a heat exchanger in the reactor pressure vessel 1 is connected to the water supply pipe 31 shown in FIG. 4, and a jet pump driven by this water supply pipe is driven. It allows heat exchange between the water and the water stream. There is a practical problem because the temperature difference between the conventional jet pump driving water and the suction water flow is small, and the heat exchanger cannot have a sufficient length and size. This conventional example also uses the method (4).

Therefore, as a result of various studies on practical methods, it was concluded that "the temperature of the feed water supplied from the feed water sparger 8 should be sufficiently lower than the temperature of the feed water used as the jet pump driving water".

In the present embodiment, the method (2) is also adopted, and the reactor configuration is such that the discharge pressure P _O of the jet pump 6 becomes small. The discharge pressure P _O needs to be larger than the pressure loss (static pressure + dynamic pressure) mainly due to the core 2, the core outlet chamber (plenum), the steam separator 10 and the stand pipe 11. For this reason, a chamber in which the core outlet chamber is extended above the core 2 for a long time (for example, a chamber extended to the vicinity of the feed water sparger 8), that is, a riser portion 9 is provided. The riser is also called a chimney. As a result, there are many two-phase flows above the core 2, and the natural circulation force based on the buoyancy of bubbles increases. Since the cooling water is driven by this natural circulation force, the discharge pressure required by the jet pump 6 can be reduced as compared with the case where the riser portion 9 is not provided. Discharge pressure in Fig. 3
P _O depends on the magnitude of the pressure P _O of the jet pump driving water stream 31A. If the discharge pressure P _O is sufficiently small, the jet pump 6 can take a large M ratio without being driven by the jet pump driving water having a too large pressure P _O.

(II) Core flow rate control and water level control by water supply The core flow rate and water level control in this embodiment is performed by the water level / power control device 70. Water level / output control device 70
As shown in FIG. 5, it is composed of a water level controller 71, a reactor output master controller 72 and a plant state judging section 73.

The structure of the water level controller 71 is shown in FIG. The water level controller 71 includes a controller 71A, a switch 71B, an adder 71C, 71D, 71E.
And 71F. The water level controller 71 includes the reactor water level L _R measured by the water level meter 50, the jet pump drive water flow rate W _J measured by the flow meter 51, the feed water sparger flow rate W _S measured by the flow meter 52, and the flow rate. Main steam flow rate W _M measured by total 53
And the three-element / one-element control switching signal S _9A output from the integrated control device 60 is input. Switch 71B is is closed when the three elements / an element control switching signal S _9A input is instructed three element control, three elements / an element control switching signal S _9A
Is opened when the one-element control is instructed. The three-element / one-element control switching signal S _9A indicates the one-element control because the reactor output (about 10%
Output).

The adder 71c calculates the deviation between the input reactor water level L _R and the reactor water level set value L _RO . The adder 71E is a jet pump drive water flow rate W
Add _J and feed water sparger flow rate W _S. The adder 71F is
Find the deviation between the output signal of the adder 71E and the main steam flow rate W _M. When the switch 71B is closed based on the three-element / one-element control switching signal _S9A (three-element control instruction), the deviation signal output from the adder 71F is input to the adder 71D. When the switch 71B is opened based on the three-element / one-element control switching signal _S9A (one-element control instruction), the deviation signal output from the adder 71 is not input to the adder 71D. The adder 71D inputs each output signal of the adders 71C and 71F when the switch 71B is closed (when the reactor output exceeds 10%), and adds the respective signals. Switch 71B
When is open (when the reactor output is 10% or less), the adder 71D outputs the output signal of the adder 71C as it is. Based on the output signal of the adder 71D, the controller 71A adjusts the reactor water level to the reactor water level set value L _RO by the feed water sparger flow rate request signal W
Output _SO . This feed water sparger flow rate request signal W
_SO becomes the output of the water level controller 71, and the plant state determiner
Entered in 73.

The furnace output master controller 72 has the configuration shown in FIG. That is, the furnace output master controller 72
Has a switch 72B that switches between a regulator 72A and fixed terminals A and B. Furnace power master controller 7
The load change request signal ε _LOAD , the manual load change request signal ε _M, and the manual / automatic switching signal S _9B output from the integrated control device 60 are input to the unit 2.

These load demand signals are the difference between the actual reactor power output and the target reactor power output (or the difference between the actual electric power output of the generator 15 and the target electric power output). Load change request signal ε _LOAD
Is input to the fixed terminal A. A manual load change request signal ε _M is input to the fixed terminal B. Switch 72B is
It is connected to the fixed terminal B when the manual / automatic switching signal S _9B indicates manual. The controller 72A inputs the load change request signal ε _LOAD or ε _M and outputs the jet pump drive water flow rate request signal W _JO so that each load change request signal becomes zero. This request signal W _JO is the plant state determiner 73
Entered in.

The plant state determiner 73 shown in FIG. 8 is used when the BWR power plant is operating normally (not in an abnormal state).
The output values of the supplied feed water sparger flow rate request signal W _JO and the jet pump drive water flow rate request signal W _JO are output as they are as the feed water sparger flow rate request signal W _SP and the jet pump drive water flow rate request signal W _JD . The detailed configuration and function of the plant state determiner 73 will be described in (III) in the next section.

The water supply sparger flow rate request signal W _SP is input to the water supply pump 29. The feed water pump 29 changes the rotation speed according to the feed water sparger flow rate request signal W _SP , and adjusts the flow rate of feed water flowing through the feed water pipe 33 so that the reactor water level L _R becomes the reactor water level set value L _RO . This makes it possible to secure the reactor water level L _R at a predetermined level regardless of the reactor output.

Jet pump drive water flow rate request signal W _JD is the water supply pump 2
Entered in 8. Water supply pump 28 varies the rotational speed according to Jietsutoponpu driving water flow rate demand signal W _JD, reactor power Q _R adjusts the feedwater flow rate flowing through the water supply pipe 31 to a predetermined reactor power. The control of the flow rate of the feed water in the feed water pipe 31 is to adjust the core flow rate discharged from the jet pump similarly to the conventional recirculation system having the recirculation pipe, which leads to the control of the reactor output. The control of the fine reactor power based on the change in the core flow rate due to the water supply in the water supply pipe 31 of the present embodiment is performed in the power control range by the core flow rate shown in Japanese Patent Publication No. High output area). The output control in the area below the output for starting PCMI is performed by the control rod 4 as in Japanese Patent Publication No. 57-11038.

Changing the reactor power by controlling the driving water flow rate of the jet pump is the same as that of the conventional BW having the present embodiment and the recirculation system.
Same as R power plant. However, conventional plant recirculation systems use a jet pump driven water stream that has about the same temperature as the jet pump's saxion water stream. On the other hand, in the present embodiment, the temperature of the core flow rate slightly changes under the influence of the temperature change of the jet pump driving water flow 31A (about 1/10 when the M ratio is 10), which is further reduced. Change the core void reactivity. Therefore, the change characteristic of the reactor output in this embodiment is slightly different from the case of using the conventional recirculation system as shown in FIG. The change characteristic of the former is higher than that of the latter.

In this embodiment, the water level control in the reactor pressure vessel 1 is performed by controlling the rotation speed of one of the water feed pumps based on the output signal of the water level controller 71 to adjust the feed water flow rate in the water feed pipe 33. At that time, since the rotation speed of the water supply pump 28 is not controlled, the water level can be easily controlled. Further, the control of the reactor output, since it is sufficient to control the rotation speed of one feed water pump 28 based on the output signal of the reactor output master controller 72,
It's easy to do.

(III) Protection control in the event of an abnormality In a conventional BWR power plant with a recirculation system, the reactor water level was controlled using the total feedwater flow rate W _FW . However, in the present embodiment, most of the water supply (2 · W _FW / 3) is used for controlling the reactor power discharged into the jet pump 6, and the remaining water supply (W _FW / 3) is the reactor water level. Used for control. Therefore, the capacity of adjusting the reactor water level becomes smaller than that of the conventional BWR power plant with a recirculation system. Even with this, no problem occurs during normal operation. BWR
When the plant state of the power plant is accompanied by a large and abrupt change and when it is abnormal, the reactor water level may decrease significantly. The possibility of occurrence of such a phenomenon needs to be avoided. Therefore, the present embodiment takes two measures against this.

The first is to increase the capacity of the water supply pumps 28 and 29. The minimum required capacity of the water supply pumps 28 and 29 is 2 W _FW / 3 and W _FW / 3 in this embodiment, as described above. The larger these pump capacities, the wider the control range of the reactor power and the control range of the reactor water level. Therefore, the pump capacity of the water supply pump 29 is 300%, the pump capacity of the water supply pump 28 is 105%, and the pump capacity of the condensate pump 23 is the same as the conventional one.
1.7 times. As a result, even if the reactor water level L _R suddenly drops, the feed water sparger flow rate W _S can be temporarily increased.

The second is protection by the plant state determiner 73. The configuration of the plant state determiner 73 will be described based on FIG. The plant state determiner 73 is a flow rate request signal controller 73A.
And 73B, limiter 73C, state determiner 73D, temperature estimator 73E,
It has an operating condition determiner 73F and an adder 73G. Plant state determining unit 73, Toritsupu signal SW _T, BWR measured by provided the detector power plant the plant state quantity X _P,
Feed water temperature T _J in the feed water pipe 31 measured by the thermometer 54, feed water temperature T _S in the feed water pipe 33 measured by the thermometer 55, and reactor output Q measured by the output detector 56 Further, _R , the aforementioned sparger flow rate request signal W _SO and the jet pump drive water flow rate request signal W _JD are input.

State judging unit 73D, after inputting the Toritsupu signal SW _T, determines the plant state quantity X _P affected by the Toritsupu signal SW _T is whether deviates from the predetermined specified level. When time and Toritsupu signal SW _T where plant state quantity X _P be input is at the specified level in you do not enter a Toritsupu signal SW _T, the state determination unit 73D is open signal to the opening and closing valve 35 as a valve switching signal S _9C, A closing signal is output to the on-off valve 44. When the plant state quantity X _P is determined to deviate from the predetermined specified level, the state determination unit 73D is a flow demand signal conditioner 73A and flow demand signal corresponding to Toritsupu signal SW _T to at least one of 73B-changing indicator At least one of the signals S _S and S _J is output, and the valve switching signal S _9C that closes the on-off valve 35 and opens the on-off valve 44 according to the trip signal SW _T is sent to the on-off valves 35 and 44. Output. Depending on the trip signal SW _T , it is not necessary to switch the opening / closing of the on-off valves 35 and 44. The flow rate request signal controller 73A is
Input the change instruction signal S _S , modify the sparger flow rate request signal W _SO according to the signal S _S, and
Output to the water supply pump 29 as _SP . Flow rate demand signal controller
73B modifies the Jietsutoponpu driving water flow demand signal W _JO 'output from Rimitsuta 73C in response to the signal S _J to input change instruction signal S _J described above, the water supply as Jietsutoponpu driving water flow rate demand signal W _JD Output to pump 28. The limiter 73C, when the judgment result signal LM output from the driving condition judging device 73F is zero (when the driving condition is normal),
The jet pump drive water flow rate request signal W _JO is output as it is to the flow rate request signal controller 73B as a jet pump drive water flow rate request signal W _JO ′.

The operation of the flow rate request signal adjusters 73A and 73B and the state determiner 73D will be described with reference to a specific trip signal SW _T , for example, a “main steam isolation valve close” signal. The "main steam isolation valve closed" signal causes the reactor to be scrammed by the rapid insertion of the control rod 4 into the core 2. The state determiner 43D inputs a "main steam isolation valve closed" signal and then, when the reactor water level L _R drops to a predetermined specified level, a change instruction signal S _{S of} "increase of feed water sparger flow rate request signal W _SO ". , "Jet pump drive water flow rate request signal
A change instruction signal S _{J for} “holding W _JO ′” and a valve switching signal S _9C for closing the opening / closing valve 35 and opening the opening / closing valve 44 are output. When the trip signal SW _T is the “main steam isolation valve closed” signal, the change instruction signals S _S and S _J and the valve switching signal S _9C are output. The on-off valve 35 is closed by the valve switching signal S _9C ,
The on-off valve 44 is opened. The flow rate request signal controller 73A determines the feed water sparger flow rate request signal W _SO based on the change instruction signal S _S.
Output the feed water sparger flow rate request signal W _SP with increased. The flow rate demand signal controller 73B outputs the jet pump drive water flow rate demand signal W _JO ′ as the jet pump drive water flow rate demand signal W _JD based on the change instruction signal S _J. These signals do not change the rotation speed of the water supply pump 28, but increase the rotation speed of the water supply pump 29. Water pump 28
The feed water discharged from the water is supplied from the feed water sparger 8 into the reactor pressure vessel 1 through the feed water pipe 31, the bypass pipe 43 and the feed water pipe 33. Although the flow rate of the feed water supplied from the feed water sparger 8 increases, the water level L _R in the reactor pressure vessel 1 is increased by the function of the water supply / output control device 70, particularly the water level controller 71.
Is maintained at a predetermined prescribed level. The valve switching signal S
_It is the nozzle that closes the on-off valve 35 and opens the on-off valve 44 at _9C .
Jet pump 6 based on the action of water supply discharged from 32
This is to prevent a large amount of core flow rate from being supplied into the core 2 of the nuclear reactor that has been scrammed by driving.

When the turbine metropolitan flop occurs, the state determination unit 73D does not output a valve switching signal S _9C, water Supajiya flow demand signal W _SO
And the change instruction signals S _S and S _J for decreasing the jet pump drive water flow rate request signal W _JO ′ to a predetermined level.

With the above configuration, it is possible to prevent the reactor water level L _R from changing rapidly during various trips.

The state determiner 73D has a memory that stores the change instruction signals S _S and S _J and the valve switching signal S _9C for various trip signals SW _T. This memory may be installed separately from the state determiner 73D. The state determiner 73D retrieves each signal from the memory corresponding to the input trip signal SW _T.

The plant state determiner 73 is the flow rate request signal adjuster 73 described above.
A first protection part consisting of A and 73B and a state determiner 73D that corrects each flow rate request signal at the time of trip, and a second protection part that limits the jet pump drive water flow rate request signal when the operating state described later deviates from the permissible range. Have Next, the second protection section will be described in detail.

Similar to the temperature estimator 46A, the temperature estimator 73E determines the temperature T _JSC of the suction water flow 45A that is sucked into the jet pump 6 based on the temperature T _S of the feed water sparger water. The temperature difference ΔT between the temperature T _J of the jet pump driving water and the temperature T _JSC is the adder
Required at 73G. The operating condition determiner 73F is the reactor output.
Q Type _R and the temperature difference [Delta] T, determines whether the current determined based on these values the operating condition is within the allowable range. Operating condition determining unit 73F is the reactor shown in FIG. 10 outputs Q _R
And a characteristic based on the temperature difference ΔT are stored. In FIG. 10, the area above the line L ₁ is the prohibited area. line
L ₂ is an alarm generation line, and the area below the alarm generation line L ₂ is the operation allowable area. Determined in One Manzanillo the reactor power Q _R and the temperature difference ΔT position, in the case of operation allowable range, the operation state of the BWR power plant is normal. When the position is in the area above the alarm generation line L ₂ , the operating state of the BWR power plant is in an abnormal state.
The operating condition determiner 73F outputs a determination result signal LM having a level of zero when the operating condition is normal, and outputs a determination result signal LM having a level of "1" when the operating condition is abnormal. . Measured reactor power when the operating condition is abnormal
Q _R and the temperature difference by the ΔT connexion determined point X is alarm line
It is when entering the area above L ₂ . When the point X contacts the alarm generation line L ₂ from below, the operating condition determiner 73
F outputs an alarm, and this alarm is displayed on a display device (not shown). The judgment result signal LM is a limiter
Input to 73C. The limiter 73C has the control characteristics shown in FIG. The solid line shows the characteristic when the judgment result signal LM is "0", and the broken line shows the characteristic when the judgment result signal LM is "1". Therefore, the limiter 73C uses the jet pump drive water flow rate request signal W _JO ′ indicated by the broken line to input the jet pump drive water flow rate request signal W _JO input when the operating state is abnormal.
Limited to value. As a result, point X becomes the alarm generation line L ₂
Held in the upper position. Therefore, the jet pump drive water flow rate that causes the occurrence of cavitation in the jet pump 6 is not adjusted.

(IV) Control for improving responsiveness of generator output This control is performed by the turbine control device 80 and the extraction valve control device 90.
It is carried out by. Detailed configuration of these control devices
Shown in the figure.

The turbine controller 80 includes a pressure controller 80A, a speed controller 80B,
It has a low value priority gate 80C, an initial pressure regulator 80D, controllers 80E and 80F, and adders 80G to 80J. The extraction valve control device 90 includes an extraction valve controller 90A, an extraction amount distributor 90B, a jet pump drive water flow rate compensation controller 90C, and adders 90D and 90E.

The electrical output of the generator 16 depends on the true amount of steam flowing through the high pressure turbine 13 and the low pressure turbine 14. This amount of steam is
It is adjusted by the steam control valve 20. There are two modes for controlling the opening degree of the steam control valve 20. The first mode is to control the steam pressure P _S of the reactor pressure vessel 1 (measured by the pressure gauge 57 provided in the main steam pipe 17) to a value close to the set pressure P _SO (atom). Furnace pressure constant control). That is,
The measured pressure P _S , the set pressure P _SO, and the initial pressure output from the initial pressure regulator 80D are input to the adder 80G, and the deviation signal between the initial pressure and the measured pressure P _S and the set pressure P _SO is input to the pressure controller. Input to 80A. The pressure controller 80A outputs a signal V ₁ based on the deviation signal. Signal V ₁ is low priority gate 80C, adder
Output to 80I and 80H. The low priority gate 80C has the signal V
_The signal of the lower level between ₁ and the signal V ₂ is selected and output to the controller 80F. Communication V ₁ is usually small and signal V ₁
Is selected. Controller 80F is a low price priority gate 80C
The opening degree of the steam control valve 20 is controlled based on the output signal of the.
The controller 80E controls the opening degree of the bypass valve 22 based on the signal V ₁ obtained by the adder 80I, the output signal of the low value priority gate 80C and the deviation signal of the bias signal. For example, when the reactor power increases, the steam pressure increases, the steam control valve 20 opens at the signal V ₁ , the steam flow rate supplied to the turbine increases, and the output of the generator 5 increases. The second mode is for responding to a request from the power system side and a change in the rotation speed of the generator 15. The speed controller 80B obtains a deviation value between the rotation speed R _{M of} the generator 15 (turbine) measured by the tachometer 58 and the target value L _set, and outputs a signal V ₂ corresponding to this deviation value. Further, the speed controller 80B extracts a short cycle and small output change component (change range within 5% within a period of several tens of seconds) that requires quick response from the signal V ₂ and extracts the load change request signal ε _L. To output to the extraction valve controller 90A. The aforementioned signal V ₂ is input to the low value priority gate 80C and the adder 80J. When the signal V ₂ is selected by the low value priority gate 80C instead of the signal V ₁ , the controller 80F controls the opening degree of the steam control valve 20 based on the signal V ₂ . The adder 80J outputs the addition signal of the signal V ₂ and the bias signal to the adder 80H. 80H adder
Is the deviation signal between the signal V ₁ and the output signal of the adder 80J (jet pump drive water flow rate change request signal ε _Q )
Output to 80D and the adder 90E of the bleeding valve control device 90. The jet pump drive water flow rate change request signal ε _Q is a reactor output change request signal.

The above two modes are selected by the low priority gate 80C. A bias value of 10% in terms of reactor power conversion is added to the signal V ₂ by the speed controller 80B so that the first mode is selected during normal operation of the BWR power plant. However, the rotation speed R
_When the fluctuation of _M is large and the signal V ₂ changes greatly, the steam control valve 2
0 is adjusted by the signal V ₂ . In order to make the generator output respond faster, the initial pressure regulator 80D turns on the steam control valve 20 before the effect of the response (quite slow) of the water level / output control device 70 that controls the flow rate of the jet pump drive water appears. It is an attempt to move auxiliary.

In this embodiment, the bleed valves 37, 39 are output by the output signal of the bleed valve controller 90A.
And 41 and corrects the jet pump drive water flow rate change request signal ε _Q output from the turbine control device 80 by the output signal thereof, and the load change request signal ε _LOAD obtained by the correction is passed through the overall control device 60. Water level / output control device
This is output to the furnace output master controller 72 of 70.

The bleeding valve controller 90A that receives the load change request signal ε _L is
Based on the signal ε _L , a closing degree signal (reverse of the opening signal) ε _V of the extraction valve is obtained, and this signal is output to the extraction amount distributor 90B and the jet pump drive water flow rate compensation controller 90C. The extraction amount distributor 90B uses the extraction signals 37 and 3 based on the closing degree signal ε _V.
Each opening of 9 is designated, and the opening of the bleeding valve 41 is designated based on the temperature difference ΔT output from the feed water temperature control device 46. The opening difference of the extraction valve 41 by the extraction distributor 90B is controlled by the temperature difference ΔT.
Occurs when the alarm line L ₂ shown in FIG. 10 is crossed. The jet pump drive water flow rate compensation controller 90C outputs a jet pump drive water flow rate compensation signal ε _FW proportional to the input extraction valve closing degree signal ε _V for the purpose of compensating for the decrease in the reactor inlet feed water temperature. This signal ε _FW is input to the adder 90E. The adder 90E corrects by adding the compensation signal ε _FW to the jet pump drive water flow rate change request signal ε _Q , and the load change request signal ε _LOAD obtained by the correction is added to the integrated control device 60.
Output to. The water level / water supply control device 70 inputs the load change request signal ε _LOAD from the overall control device 60 as described above, and adjusts the rotation speed of the water supply pump 28 based on this request signal. As a result, the core flow rate is changed.

The structures of the extraction valve controller 90A and the extraction amount distributor 90B will be described below. The bleeding valve controller 90A is specifically configured as shown in FIG. 13, and includes a switch 90A ₁ and a controller 90A ₂ . Switch 90A ₁ is normally closed and when no exerted the function of the present embodiment is opened manually, for example. The controller 90A ₂ is a proportional / integral type controller. The bleed air quantity distributor 90B includes bleed valve opening controllers 91 and 9 as shown in FIG.
2 and a function generator 93. The function generator 93 is connected to the output detector 56 and the adder 91A. The bleeding valve opening controller 91 controls the opening of the bleeding valve 41 and includes adders 91A and 91D, a function generator 91B and a PI controller 91C.
Is equipped with. The adder 91A is also connected to the feed water temperature control device 46 and the function generator 91B. The PI controller 91C is connected to the function generator 91B. The adder 91D is a PI controller
It is connected to the output end of 91C and the input end of the signal selector 47.
Extraction valve opening controller 92 for adjusting the opening of the extraction valves 37 and 39
Has regulators 92A and 92B connected to summer 90D. The regulator 92A is connected to the bleeding valve 37, and the regulator 92B is connected to the bleeding valve 39.

The response of each part according to this embodiment is as follows. First, an increase in the load on the power system causes a decrease in the rotation speed of the generator 15 (turbine) (detected by the tachometer 58). This is detected by the speed controller 80B as a load change request signal ε _L (zero in normal times, positive value side in this case). The bleeding air controller 90A, which receives the load change request signal ε _L , uses a proportional / integral type regulator (proportional gain K _P , integral gain K _I ) 90A ₂ to indicate how close the bleeding valve should be closed ε. _{Find V.} This closure signal ε
_V is transmitted to the jet pump driving water flow rate compensation controller 90C and the adder 90D. The function of the latter controller 90C has been described above and will not be described.

The deviation signal V ₃ obtained by the adder 90D is the extraction amount distributor 90B.
Is input to the adjusters 92A and 92B of the bleed valve opening controller 92. Controller 92A outputs the opening signal ST ₃ corresponding to the deviation signal V ₃ to bleed valve 37. The extraction valve 37 is adjusted to the corresponding opening based on the opening signal ST ₃ . The controller 92B outputs an opening degree signal ST ₄ corresponding to the deviation signal V ₃ to the bleed valve 39. The extraction valve 39 is adjusted to the corresponding opening based on the opening signal ST ₄ . The bleed valve opening controller 92 uses the bleed valve 37 and the bleed valve 37 to quickly respond to the output change of the generator 16 (the change width is within 5% within a period of several tens of seconds) based on the output of the tachometer 58. Control the opening of 39. Therefore, it is possible to deal with the output fluctuation of the generator 16 having a small change width in a short cycle in a short time. That is, the above-mentioned opening signals ST ₃ and ST ₄
By rapidly reducing the openings of the extraction valves 37 and 39 to reduce the amount of extracted steam, the rotational speeds of the turbines 13 and 14 are increased and ε _L is rapidly returned to zero.

Temperature difference ΔT obtained by the adder 46B of the water temperature controller 46
Is input to the adder 91A of the extraction valve opening controller 91. The function generator 93 is the reactor output measured by the output detector 56.
Determining the temperature difference [Delta] T ₁ based on the Q _R. Function generator 93 stores a relational expression showing the relationship between the temperature difference [Delta] T ₁ and reactor power Q _R (which corresponds to the formula alarm line L _2). The temperature difference ΔT ₁ obtained by the function generator 93 is input to the adder 91A. The adder 91A calculates the deviation signal u (= ΔT ₁ −ΔT). The function generator 91B outputs the signal V _{4 of} level 0 when the deviation signal u is 0 or more, and outputs the negative signal V ₄ corresponding to the case where the deviation signal u is negative. PI controller 91
C outputs a control signal based on the signal V ₄ . Adder 91D
Calculates the opening signal ST ₂ based on this control signal and outputs the opening signal ST ₂ to the signal selector 47. The signal selector 47 selects one of the input opening signals ST ₁ and ST ₂ as described above, and transmits the selected opening signal to the extraction valve 41. The opening degree of the bleeding valve 41 is adjusted based on the opening degree signal selected by the signal selector 47. Bleed valve 41 based on opening signal ST ₂
In operation allowable range lower rapidly than alarm line L ₂ even when the temperature difference ΔT corresponding to O connexion any reactor power Q _R to reduce the degree of opening of the had exceeded the alarm line L ₂ It is possible to shift to the operation of. The bleed valve opening controller 91 is a kind of protection device for shifting the operation of the reactor to a safe state when the operation is performed in a region above the alarm generation line L ₂ .

The response characteristic of the control based on the function of the bleed valve opening controller 92 is
It is shown on the time axis of the short time scale in Figure 15. The influence of the increase / decrease in the amount of extracted steam extends to the turbine inlet side and the reactor pressure vessel side, and various variables have their own delay and amplitude in the system output request Q _L (reflected in the load change request signal ε _L ). Follow along with it. Therefore, it has a load following characteristic having extremely good characteristics as a whole.

However, it is assumed that a state in which the load change request signal ε _L sways to the positive value side occurs for a relatively long time (several minutes or more) (load request of the power system, change of load set point, etc.). Caused by). At this time as well, the turbine output immediately responds by the control of the extracted steam described above. However, since the bleed valve is held in a state where it is fully closed to a certain extent,
The amount of extraction steam supplied to the feed water heaters 25, 26, and 28 decreases, and the feed water temperature starts to gradually decrease.

In the present embodiment, in order to compensate for this drop in the feed water temperature, as described above, the load change request signal ε _LOAD obtained by correcting with the signal ε _FW proportional to the extraction valve closing degree signal ε _V is used as the central control unit. It is transmitted to the reactor power master controller 72 of the water level / power control device 70 via 60. That is, as shown in FIG. 13, since the bleed valve controller 90A includes the integral term KI / S (KI is an integral gain), the signal ε _V is the integrated value of the signal ε _L , in other words, the cut bleed air. The integrated amount of steam is shown. Therefore, if the jet pump drive water flow rate (core flow rate) is increased by an amount commensurate with this integral amount, the increase in turbine output will gradually contribute to the reactor output, and the cut amount of extracted steam will eventually Since it becomes zero, the water temperature does not drop significantly. More specifically, as the jet pump driving water flow rate increases (the speed is given by the water level / power control device 70), the reactor power increases,
The turbine controller 80 opens the steam control valve CV in an attempt to keep the reactor pressure constant, and the turbine (generator 15) rotational speed tries to increase more than the target value.
_L is begins to fall gradually negative signal epsilon _V Te summer, toward the direction of the fully open the bleed valve 37 and 39. In the present embodiment, the increase in the output of the generator 15 when the load of the power system is increased or when the load setting is increased in the load following operation is first covered by the cut of the extracted steam amount, and then the reactor output. Will be covered by the increase in. When the reactor output increases, the opening degrees of the extraction valves 37 and 39 return to the original 100% opening degree, so the feed water temperature does not continue to drop. In particular, since the recirculation flow rate change request signal ε _Q is corrected based on the signal ε _FW , it is possible to suppress the decrease in the feed water temperature in a short time and mitigate the thermal shock to the structure of the reactor pressure vessel.

The response of each variable at this time is shown by the solid line on the long-time scale in FIG.

As for the effect when the water supply temperature decreases and the water supply temperature increases and decreases repeatedly in a considerable period, firstly, there is a case where the thermal cyclic stress of the structural material such as the water supply nozzle may be a problem. To be In this embodiment, the thermal shock to the internal structure generated at this time can be suppressed, and the thermal fatigue generated in this structure can be significantly reduced. Secondly, it is conceivable that the thermal behavior in the core 2 changes greatly. That is, when the reactor power is increased by the same amount, the boiling start point moves slightly when the core flow rate increases, whereas the boiling start point moves significantly when the feedwater temperature decreases. Along with this, the power distribution in the axial direction also increases almost averagely when the core flow rate increases, whereas the local change is large when the feedwater temperature decreases and the power output before the reactor power change is changed. The distortion becomes large with respect to the distribution. Therefore, the fluctuation of the feed water temperature is accompanied by the movement of the hot spot, and the fluctuation of the position where the hot spot occurs is repeated. In the present embodiment, such a problem can be solved.

Further, in the present embodiment, by providing the bleed valve control device 90 described above, it is possible to change the output in a small width and in a short cycle (usually referred to as AFC operation or governor-free operation mode), and furthermore, it is large and relatively uncomfortable. Since the flow control of the jet pump driving water that is the water supply for controlling the output change (controlled by the water level / output control device 70) is also used, it has a wide output change function.

Bleed valve opening controller 92 and function generator 93 in this embodiment
May be removed from the extraction amount distributor 90B and installed in the feed water temperature controller 46 together with the signal selector 47.

According to this embodiment, the rapid response of the turbine output to the load change is improved.

(V) Overall Control Device Finally, a specific configuration of the overall control device 60 will be described. The integrated control device 60 includes a water level / output control device 70, a turbine control device 80, an extraction valve control device 90, and a control rod drive device 100.
And controls signals with these control devices.

The integrated control device 60 has a load change request signal evaluation unit 60A and a control device selection unit 60B. The integrated control device 60 also inputs information about the plant state of the entire plant including the control device. The load change request signal evaluation unit 60A uses the load change request signal ε _LOAD output from the extraction valve control device 90.
To analyze and evaluate. That is, the load change request signal ε
_LOAD is evaluated with respect to the change width ΔQ and the rate of change with time (or period, frequency component).

The control device selection unit 60B includes a control device selection unit 60C and a controller 60.
With D-60G. The control device selector 60C determines which signal should be sent to which control device with priority.
For example, in the cycle of several seconds to several minutes, an output change component having a fluctuation width of several% is input to the turbine control device 80, and an output change component smaller than the above-described period and narrower is input to the bleeding valve control device 90, in a cycle of several minutes or more. Output level change components larger than a few percent are supplied to the water level / output control unit 70, and compensation for output change components that are very loose and drift-like are supplied to the control rod drive unit control unit 100. Output. Also adjuster 60D-60G
Information is exchanged with each other, and the control device selection unit 60B
Is adjusted so that the whole is stable and there is no mutual interference. For example, non-interference control based on the multivariable controller theory is implemented.

Another embodiment of the present invention will be described below.

First, in the other first embodiment, the temperature of the jet pump driving water and the temperature of the feed water sparge water are measured so that the cavitation does not occur during the operation of the jet pump driven by the water supply, and these are set to the target values. Is a method of controlling. The configuration in this case will be described with reference to FIG.
The extraction steam supplied to the feed water heaters 25, 26 and 27 is extracted based on the set jet pump drive water and feed water sparger water temperatures (T _J and T _S ) input to the extraction control device 90. And 40 by controlling bleed valves 37, 38 and 41, respectively. That is, the bleed valve controller 90 operates the bleed valves 37 and 39 to control the temperature of the feed water sparger water, and considers the opening degrees of the bleed valves 37 and 39 to control the temperature of the jet pump driving water. Therefore, it is necessary to adjust the opening degree of the extraction valve 41. Since the temperature of the water supply (water supply flowing in the water supply pipes 31 and 33) of both has a large delay time and a long dead time, the bleed valve control device 90 used in the present embodiment is preferably programmed control.

Another embodiment of the present invention is shown in FIG. In the reactor plant of this embodiment, the water supply pumps 28 and 29 functioning as the water supply flow rate adjusting means in the water supply pipes 31 and 33 in the embodiment shown in FIG. 1 are replaced with flow rate adjusting valves 61 and 62. Yes,
The water supply pump 63 is installed in the water supply pipe 30 between the high-pressure water supply heater 26 and the branch point 34. The other structure of this embodiment is the same as that of the embodiment shown in FIG. The flow rate control valve 61 is provided in the water supply pipe 31 between the high-pressure water supply heater 27 and the branch point 34. The flow rate control valve 62 is provided in the water supply pipe 33.
The opening degree of the flow rate control valve 61 is controlled by the jet pump drive water flow rate request signal W _JD . The opening of the flow control valve 62 is
It is controlled based on the feed water sparger water flow rate request signal W _SP .

Such an embodiment can obtain the same effect as the nuclear reactor plant shown in FIG.

FIG. 18 shows another embodiment of the present invention. This embodiment is the first
A baffle tube 12 is added to the configuration of the illustrated embodiment. The baffle tube 12 includes a riser section 9 and a water supply sparger 8
It is placed between and.

The baffle tube 12 is arranged concentrically with the riser section 9,
Its lower end extends to the vicinity of the upper end of the jet pump 6. A large number of small holes are provided in the upper part of the baffle tube 12.

A large amount of high-temperature cooling water separated by the steam separator 10 is discharged to the outside of the steam separator 10 and mixed with the cooling water in the upper part of the reactor pressure vessel 1. The temperature of this cooling water rises due to the mixing of a large amount of high temperature cooling water. The baffle cylinder 12
The high-temperature cooling water is prevented from being mixed with the low-temperature water supply discharged from the water supply sparger 8 throughout. Since the baffle cylinder 12 is provided with small holes, only a part of the high temperature cooling water is mixed with the low temperature feed water. High-temperature cooling water exists inside the baffle tube 12. Therefore, the cooling water outside the baffle tube 12 is
It is sucked into the jet pump 6 while keeping the low temperature.

The nuclear reactor plant of this embodiment has the same effects as the embodiment shown in FIG. Further, due to the effect of installing the baffle cylinder 12, the temperature of the cooling water sucked into the jet pump 6 becomes lower than that of the embodiment shown in FIG.

FIG. 19 shows a reactor plant according to another embodiment of the present invention shown in FIGS. 19 and 20. These figures show the structure in the vicinity of the jet pump in the reactor pressure vessel 1 of the present embodiment. In this embodiment, the jet pumps are arranged in two stages in series. The other construction is the same as that of the embodiment of FIG. 1, and two jet pumps 6B and 6C are arranged in parallel. The jet pump 6A is arranged above the jet pumps 6B and 6C. At the upper end of the jet pump 6A, the nozzle 32
Is inserted. Two nozzles 64A and 64 are provided at the lower end of the jet pump 6A, that is, on the cooling water discharge side. These nozzles 64A and 64B are inserted into the upper ends of the jet pumps 6B and 6C. When the M ratio of the jet pump 6A is M ₁ and the M ratio of the jet pumps 6B and 6C is M ₂ , the M ratio of the entire two-stage jet pump is given by (M ₁ + M ₂ × (M ₁ +1)).

The lower end of the baffle cylinder 12 provided inside the water supply sparger 8 reaches near the upper end of the jet pump 6A. 12
A is a small hole provided in the baffle tube 12.

The jet pump driving water (supplied by the water supply pipe 31) ejected from the nozzle 32 causes the jet pump 6A to move to the baffle cylinder 12
Suck mainly the cold cooling water outside of the. The cooling water sucked into the jet pump 6A is ejected from the nozzles 64A and 64B and becomes the driving water for the jet pumps 6B and 6C. In this embodiment, the M ratio can be increased without causing cavitation in the jet pump. Moreover, the range in which the occurrence of cavitation can be prevented is large.

A reactor plant according to another embodiment of the present invention will be described with reference to FIG. The same components as those in the embodiment of FIG. 1 are designated by the same reference numerals. In this embodiment, the feed water temperature control device 46, the water level / output control device 70 and the bleed valve control device 90 of the embodiment of FIG. 1 are replaced by a feed water temperature control device 49, a water level / output control device 75 and a bleed valve control device 94. Instead, the signal selector 47 is removed.
Further, a thermometer 59 for measuring the temperature T _SA of the cooling water (saturated water)
Is installed in the reactor pressure vessel 1 (for example, in the riser unit 9). A pressure gauge 62 for measuring the reactor pressure P _R is attached to the reactor pressure vessel 1. The measurement signals of the thermometer 59 and the pressure gauge 62 are input to the water level / output control device 75.

The water temperature controller 49 will be described with reference to FIG. The water temperature controller 49 includes a temperature estimator 46A, adders 46B, 49C, 49E and 4
9G, function generators 49A and 49B, target temperature difference setter 49D and PI
It has a D controller 49F. In the function generators 49A and 49B, each input end is connected to the output detector 56, and each output end is an adder 49.
Connected to C. The adder 49C is connected to the target temperature difference setter 49D. The input end of the adder 49E is the target temperature difference setter 4
9D and adder 46B are connected, and the output terminal is connected to PID controller 49E. The PID controller 49F is connected to the extraction valve 41 via the adder 49G. Function generator 49A is equivalent to the characteristics of the reactor power Q _R and the temperature difference [Delta] T ₂ characteristics showing the relationship between L _U2 (24 alarms are stored in the operation state determination unit 76A shown in FIG generation line L _U2 ) Is remembered. Function generator 49B are reactor power Q _R and the temperature difference [Delta] T ₃ lower alarm line is also priority than characteristics showing the relationship L _D2 (which is stored in the operation state determination unit 76A alarm line L _U2 and L It corresponds to the characteristics of _D2 ). The region between the upper limit alarm generation line L _U2 and the lower limit alarm generation line L _D2 stored in the operating condition determiner 76A is the operation allowable region.

Function generator 49A outputs the temperature difference [Delta] T ₂ corresponding to the inputted reactor power Q _R. Function generator 49B outputs a temperature difference [Delta] T ₃ corresponding to the inputted reactor power Q _R. Adder 49C
Outputs a temperature difference ΔT ₄ obtained by adding the temperature difference ΔT ₂ and the temperature difference ΔT ₃ . The target temperature difference setter 49D calculates the target temperature difference ΔT ^* based on the input temperature difference ΔT ₄ . In this embodiment, the target temperature difference ΔT ^* is 0.5 times the temperature difference ΔT ₄ , that is, the average value of the temperature difference ΔT ₂ and the temperature difference ΔT ₃ . Adder
49E calculates the deviation between the temperature difference ΔT obtained by the adder 46B and the target temperature difference ΔT ^* . Based on this deviation, the PID controller 49F outputs a control signal so that the temperature of the jet pump driving water is higher than the temperature of the feed water sparger water by a predetermined temperature. The adder 49G outputs an opening degree signal ST ₅ based on this control signal. The opening of the bleed valve 41 is adjusted based on the opening signal ST ₅ .

Since this embodiment has the water supply heater 27 and the water supply pipes 31 and 33, it can perform the control mode of the item (I) which can obtain the same function as the embodiment of FIG. The water supply temperature control device 49 controls the difference between the temperature of the water supply flowing in the water supply pipe 31 and the temperature of the water supply water flowing in the water supply pipe 33 to a predetermined temperature.

The water level / output control device 75 that implements the control mode of the above (II) will be described. Figure 23 shows the water level / output control device.
75 configurations are shown. The water level / output control device 75 has a water level controller 71 and a reactor output master controller 72 provided in the water level / output control device 70, and a plant state determination device 76 in addition to these. Water level / output control device
The water level controller 71, the reactor output master controller 72, and the plant state determiner 76 of 75 are configured such that the water level controller 71 of the water level / output control device 70 and the reactor output master controller 72 are used when the control mode of the section (II) is performed. And the same operation as that performed by the plant state determiner 73.

In the present embodiment, the plant state determiner 76 has the protective function performed by the plant state determiner 73 in the control mode (III) in the embodiment of FIG. FIG. 24 shows the detailed configuration of the plant state determiner 76. Like the plant state determiner 70, the plant state determiner 76 includes flow rate request signal adjusters 73A and 73B, a limiter 73C state determiner 73D, a temperature estimator 73E, and an adder 73G. The plant state determiner 76 has an operating state determiner 76A, thermal shock determiners 76B and 76C, and an OR circuit 76D in addition to the above configuration.
The thermal shock determiner 76B includes thermometers 54 and 59 and an output detector 56.
It is connected to the. Thermal shock determiner 76C is a thermometer 55 and 5
9 and the output detector 56. Operating status judge 7
6A is connected to the adder 73G and the output detector 56. The output terminals of the operating condition determiner 76A and the thermal shock determiners 76B and 76C are connected to the limiter 73C via an OR circuit 76D.
The thermal shock determiner 76B inputs the jet pump driving water temperature T _J measured by the thermometer 54 and the saturated water temperature T _SA measured by the thermometer 59, and makes a judgment by the following equation. Thermal shock detector 7
6B outputs “0” when T _SA −T _J <ΔT _J (Q _R ) ... (1) (1) is satisfied, and outputs “1” when Formula (1) is not satisfied. ΔT _J can prevent the occurrence of thermal shock and thermal fatigue caused by supplying the jet pump driving water into the reactor pressure vessel 1. Jietsutoponpu indicates allowable maximum change rate of the driving water temperature is decreased to the function of reactor power Q _R. The thermal shock determiner 76C has a feed water sparger water temperature T _S and a saturated water temperature T _SA measured by the thermometer 55.
Is input and the judgment is made according to the following formula. Thermal shock detector 76C
Outputs “0” when the expression (2) is satisfied, and outputs “1” when the expression does not satisfy T _SA −T _S <ΔT _S (Q _R ) ... (2). [Delta] T _S the water supply Supajiya water shows a maximum allowable rate of change of the feed water Supajiya water temperature generation can prevent thermal shock and thermal fatigue caused Te cowpea to be supplied to the reactor pressure vessel 1, a function of reactor power Q _R It has become.

The operating state determiner 76A stores the characteristics of the alarm generation line L _U2 indicating the upper limit of the temperature difference ΔT and the alarm generation line L _D2 indicating the lower limit of the temperature difference ΔT. Temperature difference ΔT determined in these alarm line L _U2 and L _D2 is a function of reactor power Q _R. The alarm generation line L _U2 corresponds to the alarm generation line L ₂ in FIG. Alarm generation line L
_D2 is set below the alarm generation line L _U2 and is set to prevent cavitation in the jet pump 6. The line L _U1 shown in FIG. 24 corresponds to the line L ₁ (FIG. 10). Line L
_D1 indicates a limit temperature difference in which the cavitation does not occur in the jet pump 6 below the alarm generation line L _D2 . The region above the line L _U1 and the region below the line L _D1 are the nuclear reactor operation prohibition regions. The region between the alarm generation line L _U2 and the alarm generation line L _D2 is the operation allowable region. Operating condition determining unit 76A includes an adder receiving the output temperature difference ΔT from 73G, the temperature difference ΔT alarm generation line reflects the reactor power Q _R at that time
It is determined whether or not it exists in the area between L _U2 and the alarm generation line L _D2 . The operating condition determiner 76A outputs "0" when it is determined to be "existing" and outputs "1" when it is determined to be "not present".

The OR circuit 76D inputs the outputs of the thermal shock determiners 76B and 76C and the operating state determiner 76A and outputs a determination result signal LM of "1" or "0" to the limiter 73C.

The protection function of the plant state determiner 76 described above is the function of the second protection unit shown in the control mode of item (III) of the embodiment of FIG. The function of the first protection unit in the plant state determination unit 76 of this embodiment is achieved by the flow rate request signal adjusters 73A and 73B, the limiter 73C and the state determination unit 73D as in the case of the first protection unit in the embodiment of FIG. it can. The first protection unit and the second protection unit of the plant state determination unit 76 have the same effects as the effects obtained by the first protection unit and the second protection unit of the plant state determination unit 73. Further, this embodiment is a thermal shock detector.
Since it is equipped with 76B and 76C, it is possible to prevent thermal shock and thermal fatigue due to changes in the feed water temperature. Furthermore, the operating condition determiner 76A
However, it is determined whether the temperature difference ΔT is in a region above or below the alarm generation line L _{D2, and the} limiter 73C is operated by the determination result signal LM based on this determination. Therefore, it is possible to prevent the occurrence of cavitation.

The control mode of item (IV) executed in the embodiment of FIG.
This is performed by the extraction valve control device 94 of this embodiment. As shown in FIG. 25, the extraction valve control device 94 includes an extraction valve controller 90A, a jet pump drive water flow rate compensation controller 90C, an adder 90D and an adder 90D.
It is provided with 90E and an extraction amount distributor 95. Bleed amount distributor 9
The components other than 5 are provided in the extraction valve control device 90. As shown in FIG. 26, the extraction amount distributor 95 has an extraction valve controller 96 and an extraction valve opening corrector 97. The extraction valve controller 96 includes regulators 92A and 92B, correction amount distributors 96A and 96B, and adders 96C and 96D. Adder 96C
Has an input end connected to the regulator 92A and the correction amount distributor 96A, and an output end connected to the extraction valve 37. The adder 96D has an input end connected to the controller 92B and the correction amount distributor 96B and an output end connected to the bleed valve.
39 connected respectively. Bleed valve opening corrector 97, the dead zone is connected the feed water temperature target setter 97A for inputting the reactor power Q _R, the feed water temperature target setter 97A and the adder 97B is connected to a thermometer 55, the adder 97B It has a PID controller 97D connected to the device 97C and the dead band device 97C to perform proportional and integral calculations. The output terminal of the PID controller 97D is the correction amount distributors 96A and 96B.
It is connected to the.

Water temperature target setter 97A obtains the control target value T _S ^* feedwater Supajiya water temperature T _S on the basis of the input reactor power Q _R. The adder 97B calculates the deviation (T _S −T _S ^* ) between the feed water sparger water temperature T _S and the control target value T _S ^* . Dead band 97C
Has a dead zone of width δ from 0 to the + side and the − side, and gives a positive signal when the deviation (T _S −T _S ^* ) becomes larger than δ, and makes it larger than −δ. Sometimes it outputs a negative signal. PID controller 97 based on the output signal of dead band device 97C
D outputs the correction signal SA. The correction signal SA is input to the correction amount distributors 96A and 96B. Controller 92A and 93B are opening signal ST ₃ and ST ₄ on the basis of the deviation signal V ₃ as described above
Is output. The correction amount distributor 96A calculates α · SA. α is a distribution coefficient and takes a value of 0 ≦ α <1. The correction amount distributor 96B calculates (1−α) · SA. The adder 96C is
The opening signal ST ₆ by adding the alpha · SA output from the correction amount distributor 96A to the opening signal ST _3, the bleed valve opening degree signal ST ₆ 37
Output to. The extraction valve 37 is adjusted to an opening degree corresponding to the opening degree signal ST ₆ . The adder 96D adds (1-α) · SA output from the correction amount distributor 96B to the opening signal ST ₃ to form an opening signal ST _7, and outputs this opening signal ST ₇ to the bleeding valve 37. To do. The extraction valve 37 is adjusted to an opening degree corresponding to the opening degree signal ST ₇ .
The bleed valves 37 and 39 controlled in this way prevent the cavitation of the jet pump 6 and secure the core inlet enthalpy, and the comparatively sensitive fluctuation component and load change request contained in the load change request signal ε _L. Signal ε _L
Will operate with both the small-width and short-cycle fluctuation components included in.

In this embodiment as well, the same effect as that obtained by the control mode in the section (IV) of FIG. 1 can be obtained. In this embodiment, since the bleed valve opening compensator 97 is provided, the accuracy of the opening control of the bleed valves 37 and 39 is improved as compared with the embodiment of FIG.

This embodiment also has an integrated controller 60 having the same functions as the embodiment of FIG. Therefore, the effects brought about by the central control device 60 shown in FIG. 16 can also be obtained in this embodiment.

〔The invention's effect〕

According to the first aspect of the present invention, it is not necessary to provide a means for lowering the temperature of the cooling water sucked in the jet pump in the reactor, so that the structure of the reactor can be simplified.

According to the second feature of the present invention, it is possible to prevent the generation of gear vat in the jet pump, so that it is possible to drastically change the reactor output by controlling the core flow rate.

According to the third aspect of the present invention, since the temperature rise of the feed water sucked by the jet pump can be suppressed by the action of the baffle cylinder, the range in which the cavitation in the jet pump can be prevented is increased.

According to the fourth feature, since the feed water heater necessary for the nuclear reactor plant is bypassed and a part of the feed water is supplied to the feed water sparger, the temperature of the feed water supplied to the feed water sparger can be lowered with a simple facility. it can.

According to the fifth feature, since the water level is controlled by controlling the feed water flow rate of the system that supplies the water to the feed water sparger, which is one of the two systems that guides the water into the reactor, the water level control is simplified. it can.

According to the sixth feature, the reactor output can be controlled by adjusting the feed water flow rate supplied to the jet pump, so that the reactor output control can be simplified.

According to the seventh feature, it is possible to prevent a rapid change in the reactor water level during abnormal times.

According to the eighth feature, it is possible to prevent the operating state of the reactor from deviating from the allowable range.

According to the ninth feature, it is possible to improve the rapid response of the turbine output in response to the load change.

According to the tenth feature, mutual interference between control devices can be avoided.

[Brief description of drawings]

FIG. 1 is a block diagram of a BWR power generation plant which is a preferred embodiment of the present invention, and FIG. 2 is a block diagram showing another arrangement example of the feed water pump 28 and the high-pressure feed water heater 27 of FIG. 3 is a configuration diagram of the feed water temperature control device of FIG. 1, FIG. 4 is a characteristic diagram showing the axial pressure distribution of the jet pump, and FIG. 5 is a detailed configuration diagram of the water level / output control device of FIG. 6 is a detailed block diagram of the water level controller of FIG. 5, FIG. 7 is a detailed block diagram of the reactor power master controller of FIG. 5, and FIG. 8 is a detailed block diagram of the plant state determiner of FIG. Fig. 9 is a characteristic diagram showing the relationship between the jet pump drive water flow rate and the reactor output, Fig. 10 is a characteristic diagram showing the relationship between the reactor output and the temperature difference ΔT, and Fig. 11 is the operating characteristics of the limiter in Fig. 8. Fig. 12 is a detailed configuration diagram of the turbine control device and the extraction valve control device of Fig. 1, Fig. 13
Figure is the detailed configuration diagram of the bleed valve controller of Figure 12, Figure 14 is the configuration of Figure 12
FIG. 15 is a configuration diagram of the extraction amount distributor of FIG. 15, FIG. 15 is a response characteristic diagram of a BWR power plant based on the operation of the extraction valve control device of FIG. 12,
FIG. 16 is a detailed configuration diagram of the integrated control device of FIG. 1, and FIG.
FIG. 19 is a block diagram of another embodiment of the present invention, FIG. 20 is a sectional view taken along line YY of FIG. 19, and FIG. 21 is another embodiment of the present invention BW.
R power plant configuration diagram, FIG. 22 is a configuration diagram of the feed water temperature control device of FIG. 21, FIG. 23 is a configuration diagram of the water level / output control device of FIG. 21, and FIG. 24 is a plant state of FIG. FIG. 25 is a block diagram of the determiner, FIG. 25 is a block diagram of the extraction valve control device of FIG. 21, and FIG. 26 is a block diagram of the extraction amount distributor of FIG. 1 ... Reactor pressure vessel, 2 ... Reactor core, 4 ... Control rod, 6 ... Jet pump, 8 ... Water supply sparger, 12 ... Baffle tube, 13
… High-pressure turbine, 14… Low-pressure turbine, 15… Generator, 17…
Main steam pipe, 20 ... Steam control valve, 25 ... Low-pressure feed water heater, 26,2
7 ... High-pressure feed water heater, 28,29 ... Water feed pump, 30,31,33 ... Water supply pipe, 60 ... General control device, 70 ... Water level / output control device,
71 ... Water level controller, 72 ... Reactor output master controller, 73
... Plant condition determiner, 73A, 73B ... Flow rate request signal conditioner, 73C ... Limiter, 73D ... State determiner, 73F ... Operating condition determiner, 80 ... Turbine controller, 80A ... Pressure controller, 80B
... Speed controller, 80C ... Low value priority gate, 90 ... Bleak valve controller, 90A ... Bleak valve controller, 90B ... Bleed air amount distributor, 90C ... Jet pump drive water flow rate compensation controller, 100 ... Control rod drive device control apparatus.

─────────────────────────────────────────────────── ─── Continuation of front page (51) Int.Cl. ⁶ Identification code Internal reference number FI Technical display location G21D 3/00 M 9117-2G 3/04 GDB H 9117-2G 3/08 GDB A 9117-2G B 9117-2G (56) Reference JP 55-66796 (JP, A) JP 45-17937 (JP, B2) JP 43-23117 (JP, B2) JP 49-16920 (JP, B2)

Claims (20)

[Claims] 1. A reactor vessel containing a reactor core, a jet pump arranged in the reactor vessel to supply a coolant to the reactor core, a water supply sparger installed in the reactor vessel, and a water supply system. A reactor plant comprising: a part of the driving water which is guided to the jet pump, and the remaining part of the feed water which is guided to the jet pump at a temperature lower than that of the feed water and which is guided to the feed water sparger. 2. The nuclear reactor plant according to claim 1, further comprising control means for adjusting a temperature difference between feed water introduced as drive water to the jet pump and feed water introduced to the feed water sparger. 3. A baffle cylinder which is disposed inside the water supply sparger and extends toward the jet pump, and which suppresses the mixture of the high temperature coolant discharged from the core and the water supply discharged from the water supply sparger. The nuclear reactor plant according to claim 1, which is provided. 4. A coolant channel for guiding a coolant, a means for guiding the coolant in the coolant channel as driving water to a jet pump in a nuclear reactor vessel, and the cooling in the coolant channel. And a means for guiding the material to the water supply sparger in the reactor vessel as water supply at a temperature lower than that of the coolant supplied to the jet. 5. A reactor vessel containing a reactor core, a jet pump arranged in the reactor vessel to supply a coolant to the reactor core, a water supply sparger installed in the reactor vessel, and a water supply system. A first conduit for guiding a part of the driving water to the jet pump, a second conduit for guiding the rest of the water supply to the water supply sparger, and a temperature of the water supply provided in the first conduit for guiding the jet pump. And a heating means for increasing the temperature of the feed water to the feed water sparger. 6. The nuclear reactor plant according to claim 5, further comprising means for controlling a heating amount of said heating means. 7. A reactor vessel containing a reactor core, a jet pump arranged in the reactor vessel to supply a coolant to the reactor core, a water supply sparger installed in the reactor vessel, and a water supply system. A first conduit for driving water to the jet pump; a second conduit connected to the first conduit for guiding the water supply to the water supply sparger; and a jet pump provided in the first conduit. An atom attached to the first pipe upstream of the feed water heater, the feed water heater increasing the temperature of the feed water introduced to the feed water sparger. Furnace plant. 8. The feed water heater according to claim 7, further comprising another feed water heater which is connected to the joint between the first pipe and the second pipe and is located upstream of the joint. Nuclear reactor plant. 9. The nuclear reactor plant according to claim 7, further comprising means for controlling a temperature difference between the feed water discharged from the feed water heater and the feed water flowing in the second pipeline. 10. The nuclear reactor plant according to claim 9, wherein the control means is means for controlling the amount of the heating medium supplied to the feed water heater. 11. The nuclear reactor plant according to claim 7, further comprising means for guiding the steam generated in the reactor vessel to the feed water heater as a heating medium. 12. A first conduit for guiding a part of feed water as driving water to a jet pump arranged in a reactor vessel for supplying a coolant to a core, and a first conduit for guiding the rest of the feed water to the water supply sparger. Two pipes, heating means provided in the first pipe for increasing the temperature of the feed water guided to the jet pump to be higher than the temperature of the feed water guided to the water feed sparger; A first flow meter for measuring the flow rate of steam discharged from the furnace vessel, a second flow meter for measuring the flow rate of feed water introduced through the first pipeline, and a flow rate of feed water introduced through the second pipeline. A third flow meter, a water level meter for measuring the liquid level of the coolant in the reactor vessel, a vapor flow rate measured by the first flow meter, and a second flow meter
And water level control means for outputting a control signal for maintaining the water level in the reactor vessel at a predetermined level based on each feed water flow rate measured by the third flow meter and the water level measured by the water level meter. And a flow rate adjusting means that is provided in the second pipeline and that regulates a feed water flow rate in the second pipeline based on the control signal. 13. A first conduit for guiding a part of feed water as driving water to a jet pump arranged in a reactor vessel for supplying a coolant to a core, and a first conduit for guiding the rest of the feed water to the water supply sparger. 2 pipes, heating means provided in the 1st pipe for making the temperature of the feed water introduced to the jet pump higher than the temperature of the feed water introduced to the feed water sparger, and outputting a control signal for adjusting the reactor output A nuclear reactor plant comprising: a reactor output control means for controlling the flow rate; and a flow rate adjusting means provided in the first pipeline for adjusting a feed water flow rate in the first pipeline based on the control signal. 14. A first line for guiding a part of feed water as driving water to a jet pump arranged in a reactor vessel for supplying a coolant to a core, and a first pipe for guiding the rest of the feed water to the water sparger. Two pipes, heating means provided in the first pipe for making the temperature of the feed water introduced to the jet pump higher than the temperature of the feed water introduced to the water feed sparger, and a first control signal for adjusting the reactor output. And a water level control means for outputting a second control signal for maintaining the water level in the reactor vessel at a predetermined level, and the first control provided in the first conduit. A first flow rate adjusting means for adjusting a water supply flow rate in the first pipeline based on a signal; and a water supply flow rate in the second pipeline based on the second control signal, which is provided in the second pipeline. The second flow rate adjusting means for adjusting and the trip signal Reactor plant and means for modifying at least one of the first and second control signal when it is force. 15. A first conduit for guiding a part of feed water as driving water to a jet pump arranged in a reactor vessel for supplying a coolant to a core, and a first conduit for guiding the rest of the feed water to the water supply sparger. 2 pipes, heating means provided in the 1st pipe for making the temperature of the feed water introduced to the jet pump higher than the temperature of the feed water introduced to the feed water sparger, and outputting a control signal for adjusting the reactor output Reactor power control means, a first thermometer provided in the first conduit, and the second thermometer
A second thermometer provided in the pipe, an output detector provided in the core, each feed water temperature measured by the first and second thermometers, and atoms measured by the output detector Based on the reactor power, it is determined whether the operating condition of the reactor has reached the allowable limit, and when the operating condition reaches the allowable limit, the control signal is set so that the operating condition does not exceed the allowable limit. Reactor plant with means for modifying. 16. A reactor vessel containing a reactor core, a jet pump arranged in the reactor vessel to supply a coolant to the reactor core, a water supply sparger installed in the reactor vessel, and a water supply system. A first conduit leading to the jet pump, a second conduit connected to the first conduit and guiding the water supply to the water supply sparger, and upstream from a connection point between the first conduit and the second conduit. From the reactor vessel, a first feed water heater provided on the side of the first pipeline, a second feed water heater provided on the portion of the first pipeline on the downstream side of the connection point, A turbine driven by the discharged steam,
A flow control valve is provided to guide the steam to the first feed water heater, a means for detecting the rotation speed of the turbine, and a predetermined change width or less from the output of the rotation speed detection means. Means for extracting the following change components,
Means for controlling the opening of the flow rate control valve based on the extracted change component. 17. Another bleeding line provided with another flow rate control valve for guiding the steam to the second feed water heater, a first temperature detecting means provided in the first line, and the first temperature detecting unit. Second temperature detecting means provided in the two pipes, and based on the difference between the water supply temperature measured by the first temperature detecting means and the water supply temperature measured by the second temperature detecting means The nuclear reactor plant according to claim 16, further comprising means for controlling an opening degree of the flow rate control valve. 18. A heating means for heating a part of feed water used as driving water for a jet pump in a nuclear reactor vessel, and a temperature of remaining feed water supplied to a feed water sparger in the nuclear reactor vessel. 1 temperature detecting means, second temperature detecting means for measuring the temperature of a part of the feed water discharged from the heating means, and discharge from the heating means based on output signals of the first and second temperature detecting means And a means for controlling the heating amount of the heating means so that the temperature of the supplied water becomes higher than the temperature of the remaining supplied water. 19. Another heating means for heating a part of the water supply supplied to the heating means and the remaining water supply supplied to the water supply sparger, and driven by steam discharged from the reactor vessel Means for detecting the rotation speed of the turbine, means for extracting a predetermined change component from the output of the rotation speed detection means, and means for controlling the heating amount of the other heating means based on the change component. The water supply heating controller according to claim 18, which is provided. 20. A reactor vessel having a built-in core, a coolant channel for guiding a coolant, and means for guiding the coolant in the coolant channel as feed water to a water supply sparger installed in the reactor vessel. And a drive for supplying the coolant in the coolant flow path as drive water to a jet pump provided in the reactor vessel at a temperature higher than that of the coolant supplied to the water supply sparger as supply water. A water supply unit, a turbine that is connected to the reactor vessel by a main steam pipe having a first valve that controls a steam flow rate, and is driven by steam guided by the main steam pipe, and is connected to the main steam pipe And means for bypassing steam supplied to the turbine having a second valve, heating means provided in the coolant passage, and reactor output for outputting a first control signal for adjusting reactor power Control means, front A means for adjusting the flow rate of the driving water provided on the driving water supply means based on the first control signal, a turbine control means for controlling the opening degrees of the first and second valves, and a heating means for heating the heating means. A load change request signal for inputting the heating amount control means for adjusting the amount, the control rod insertion amount control means for adjusting the insertion degree of the control rod inserted in the core, and the control means for outputting the control information signal. Reactor plant comprising: the reactor output control means, the turbine control means, the heating amount control means, and the control rod insertion amount control means according to the fluctuation cycle and fluctuation range of the above.