JPH01499A - nuclear reactor plant - Google Patents

Abstract

(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.

Description

DETAILED DESCRIPTION OF THE INVENTION [Field of Industrial Application] The present invention relates to a nuclear reactor plant, and particularly to a nuclear reactor plant suitable for application to a nuclear reactor in which the core flow rate is controlled by water supply.

[Conventional technology]

Currently, reducing construction costs is a major issue in nuclear power plants. For example, a new type of power plant equipped with an internal pump is being developed for boiling water nuclear power plants (hereinafter referred to as BWR power plants). This new power plant will have a more compact reactor containment vessel because it will eliminate the need for the recirculation system in the already constructed BWRI power plant.

However, it is desired to make the reactor containment vessel more compact. Examples of how the reactor containment vessel can be made more compact are given in Japanese Patent Publication No. 43-23117 and Japanese Patent Publication No. 49-1692, although these publications do not directly mention them.
It is shown in Publication No. 0.

The BWR power plant shown in Japanese Patent Publication No. 43-32117 uses jet pumps to supply part of the feed water into the reactor pressure vessel through a feed water sparger, and the remaining feed water to supply cooling water to the reactor core. It is used as driving water. Here, the water supply led to the water supply sparger is
Used for water level control inside the reactor pressure vessel. Furthermore, in this BWR power plant, the cooling water discharged from the feedwater sparger and the cooling water separated by the steam-water separator above the core (both cooling waters are in a mixed state) are transferred to the heat exchanger. (installed inside the reactor pressure vessel), the water is cooled by water supply used as drive water for the jet pump, and is then sucked into the jet pump. This heat exchanger cools the jet pump suction water.
The purpose is to prevent cavity formation in the jet pump due to boiling of cooling water inside the jet pump.

Japanese Patent Publication No. 49-16920 discloses a jet pump that uses cooling water discharged from recirculation piping as driving water and a jet pump that uses part of the feed water as driving water in order to adjust the core flow rate. , and a BWR51 plant is described which supplies the remaining feed water from the feed water sparger into the reactor pressure vessel.

Similar to Japanese Patent Publication No. 43-23117, this publication also indicates that the cooling water drawn into the jet pump from the water supply sparger through the descending annular flow path is cooled (columns 6.37 to 44). line).

[Problem to be solved by the invention]

In each of the conventional examples described above, a heat exchanger is installed in the reactor pressure vessel, and the cooling water sucked into the jet pump is cooled by the heat exchanger using jet pump drive water, which is part of the water supply. However, the temperature difference between the cooling water sucked into the jet pump flowing into the heat exchanger and the jet pump driving water is 5 to 6.
The temperature is about 0° C., and the flow rate on the side to be cooled is 10 times that on the side to be cooled. Therefore, it is necessary to install a thick heat exchanger inside 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 that can simplify the structure of the nuclear reactor.

A second object of the present invention is to provide a nuclear reactor plant and a feed water heating device that can prevent the occurrence of cavitation in a jet pump and can significantly change the reactor output through core flow rate control.

A third object of the present invention is to provide a nuclear reactor plant that can suppress the temperature rise of feed water sucked into a jet pump.

A fourth object of the present invention is to provide a nuclear reactor plant that can reduce the temperature of feed water supplied to the feed water sparger with simple equipment.

A fifth object of the present invention is to provide a nuclear reactor plant and a reactor feed water flow rate control device that can easily control the water level.

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

A seventh object of the present invention is to provide a nuclear reactor plant and a reactor protection device that can suppress rapid fluctuations in water level during abnormal situations.

An eighth object of the present invention is to provide a nuclear reactor plant and a reactor protection device that can maintain operating conditions within an allowable range.

A first object of the present invention is to provide a nuclear reactor plant and a reactor feed water temperature control device that can improve the responsiveness of turbine output.

A tenth object of the present invention is to provide a nuclear reactor plant and an integrated control device that can stably control a plurality of control means in response to a load change request signal while avoiding mutual interference.

[Means to solve the problem]

In order to achieve the first objective, a water supply means is provided which directs a portion of the water supply to the jet pump as driving water, and leads the remainder of the water supply to the water sparger in a lower temperature state than the water supply that leads 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 to the jet pump as drive water and the feed water introduced to the feed water sparger.

The third purpose is to provide a baffle cylinder that is placed inside the water supply sparger and extends toward the jet pump, and that suppresses mixing of the high temperature coolant discharged from the core and the supply water discharged from the water supply sparger. It is something that can be achieved.

A fourth purpose is to provide a feed water heater in a first pipe line that leads feed water to a jet pump as driving water, and to connect a second pipe line that leads feed water to a feed water sparger to the first pipe line on the upstream side of the feed water heater. This is achieved by installing the .

The fifth purpose is to determine the water level based on three factors: the measured water level in the reactor vessel, the first flow rate of feedwater supplied into the reactor vessel, and the second flow rate of steam discharged from the reactor. Controls the flow rate of feed water that is lower in temperature than the feed water that is led as driving water to the jet pump in the reactor vessel and is fed into the feed water sparger in the reactor vessel so that This can be achieved by providing a means to do so.

In order to achieve the sixth objective, there is provided a reactor power control means for outputting a control signal for adjusting the reactor power, and a first conduit for guiding drive water that leads a part of the water supply to the jet pump and is heated. and a flow rate adjusting means provided in the first conduit having a means for adjusting the water supply flow rate in the first conduit based on the control signal.

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

The eighth purpose is to provide a first thermometer installed in a first pipe line that leads a portion of the feed water to the jet pump as driving water via a heating means, and a second thermometer installed in a second pipe line that leads the remainder of the feed water to the water supply sparger. means for determining whether the operating state of the reactor has reached an allowable limit based on each feed water temperature measured by the second thermometer and the reactor output measured by the output detector; This can be achieved by comprising means for modifying a control signal for adjusting the reactor output when the operating state reaches the permissible limit so that the operating state does not exceed the permissible limit.

A ninth object is to provide means for extracting a predetermined change component from the output of the means for detecting the rotational speed of the turbine, and means for controlling the heating amount of the heating means that heats the water supply based on the extracted change component. This can be achieved by providing

The tenth purpose is to provide a means for determining the fluctuation period and fluctuation width of an input load change request signal, and a means for determining the fluctuation period and fluctuation width of the input load change request signal, and a means for determining the fluctuation period and fluctuation width of the input load change request signal, and a means for determining the fluctuation period and fluctuation width of the input load change request signal, and a means for determining the fluctuation period and fluctuation width of the input load change request signal. This is achieved by providing a means for selecting from.

[Effect]

According to the first feature, the temperature of the part of the feed water led to the feed water sparger is lower than the temperature of the rest of the feed water led to the diene 1 pump, which reduces the temperature of the cooling water sucked into the jet pump. There is no need to provide any means within the reactor to do so.

In the second feature, 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 can be maintained at a predetermined temperature or higher by the temperature difference control means, thereby preventing cavitation from occurring within the jet pump. can.

According to the third feature, the installation of the baffle tube prevents the high temperature coolant inside the reactor vessel from mixing with the low temperature feed water discharged from the feed water sparger, and reduces the temperature rise of the feed water sucked into the jet pump. suppressed.

According to the fourth feature, since the feed water led to the feed water sparger is diverted on the upstream side of the feed water heater through which the feed water as driving water guided to the jet pump passes, the feed water heater installed in the plant The temperature of the feed water supplied to the feed water sparger can be lowered by a simple installation that bypasses some of the spargers.

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

According to the sixth feature, the reactor output can be controlled by controlling the water supply flow rate of the system that supplies water as drive water to the jet pump, which is one of the two water supply systems described above. can be done easily.

According to the seventh feature, when the trip signal is generated, at least one of the control signal for reactor power adjustment and the control signal for water level adjustment is modified, so the control signal is modified in response to the abnormal state. This makes it possible to control the water supply flow rate and suppress rapid fluctuations in the water level in the reactor vessel during abnormal situations.

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

According to the ninth feature, since the heater of the feed water 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. can be adjusted quickly in a short period of time.

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

〔Example〕

A BWR power plant which is a preferred embodiment of the present invention will be explained below with reference to FIG.

The reactor core 2 is disposed within a cylindrical core shroud 3 provided within the reactor pressure vessel 1, and is loaded with a large number of fuel assemblies. A plurality of control rod drive devices 5 each having a plurality of II rods 4 inserted into the reactor core 3 are individually connected to the control rods 4 . A plurality of jet pumps 6 having throat portions 7 are arranged in an annular space formed between the reactor pressure vessel 1 and the reactor core shroud 3. Throat part 7 is core 2
It is located higher up. The feed water sparger 8 is installed in the reactor pressure vessel 1 above the throat portion 7, and has a header and a number of injection nozzles that discharge feed water. The injection nozzle is installed in the header and faces towards 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 spouted from the water supply sparger 8 is sucked into the jet pump 6 while keeping the temperature as low as possible. At the top of the core shroud 3,
A cylindrical riser portion 9 is provided. The diameter of the riser section 9 is the same as the diameter of the core shroud 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 will be placed around the riser part 9. The steam heel device 10 is attached to the top of the riser part 9 via a standpipe 11.

Next, the structure around the turbine will be described. High pressure turbine 13. The shafts of the low pressure turbine 14 and the generator 15 are connected to each other. however.

Generator 15 is detachably connected to 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 a steam outlet (not shown) of the low pressure turbine 14.
will be contacted.

A steam stop valve 19 and a steam control valve 20 are provided in the main steam pipe 17. Bypass piping 21 with bypass valve 22
is connected to the main steam pipe 1 with one end upstream of the steam stop valve 19.
7, and the other end is connected to the condenser 16. Water supply piping 30 is connected to condenser 16 . This water supply pipe 30 includes a condensate pump 23. 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. Downstream branch point 3 of high pressure feed water heater 26
4, the water supply pipe 30 is branched into a water supply pipe 31 (jet pump driving water pipe) and a water supply pipe 33 (water supply sparger supply pipe).

Water pump28. A final-stage high-pressure water heater 27 and an on-off valve 35 are sequentially provided in the water supply pipe 31.

In FIG. 1, the feed water pump 28, which is arranged downstream of the branch point 34 and downstream of the high pressure feed water heater 27, is arranged upstream of the high pressure feed water heater 27, as shown in FIG. Good too. By arranging the feed water pump 28 upstream of the high-pressure feed water heater 27 as shown in FIG. is equal to This is because the pressure loss caused by the high-pressure feed water heater 28 can be prevented from affecting the suction side of the water feed pump 28.

The water supply pipe 31 is guided 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 . The water supply pump 29 is
It is installed in the water supply pipe 33.

Low pressure feed water heater 25. The high pressure feed water heaters 26 and 27 are
A portion of the steam generated within the reactor pressure vessel 1 is introduced to heat the feed water. Namely.

The shell inner space of the low pressure feedwater heater 25 is connected to the low pressure turbine 14 by a bleed pipe 36 having a bleed valve 37 . The space inside the shell of the high-pressure feed water heater 26 is an air bleed pipe 38.
The high pressure feed water heater 2 is connected to the high pressure turbine 13 by
The shell inner space of No. 7 is connected to the high pressure turbine 13 by a bleed pipe 40. A bleed valve 39 is provided in the bleed pipe 38 and a bleed valve 41 is provided in the bleed pipe 40. Low pressure water heater 2
5. 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 are connected by a bypass pipe 43 having an on-off valve 44 . 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 on-off valve 35 .

The following detectors are installed.

5o is a water level gauge that detects the reactor water level (LR) in the reactor pressure vessel 1, and 51 is the water supply flow r & (jet pump driving water flow rate: W
52 is a flowmeter that detects the water supply flow rate (water supply sparger flow rate: Ws) in the water supply pipe 33 supplied from the water supply sparger 8 into the reactor pressure vessel 1, and 53 is a main steam pipe. Main steam flow rate (WM) flowing through 17
It is a flow meter that detects The water level gauge 50 is attached to the reactor pressure vessel 1, the flow meter 51 is attached to the water supply pipe 31, the flow meter 52 is attached to the water supply pipe 33, and the flow meter 53 is attached to the main steam pipe 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 driving water) in the water supply pipe 31, and 55 is a thermometer attached to the water supply pipe 31.
3 is a thermometer attached to the reactor core 2 to detect the temperature (Ts) of the feed water (feed water sparger water) in the water supply pipe 33;
A power detector 57 is installed in the main steam pipe 17 to detect the reactor power (Q'R), and a power detector 57 is installed in the main steam pipe 17 to detect the reactor power (Q'R).
s), and 58 is a pressure gauge that detects the rotation speed of the turbine (
This is a tachometer that detects Na).

Water level gauge 50. Flow meters 51, 52 and 53. Each state quantity detected by the thermometers 54 and 55 and the output detector 56 is
The information is transmitted to the water level/output control device 70. The water supply/output control device 7o includes water supply pumps 28 and 29, and an on-off valve 35.
and 44. Each state quantity detected by the pressure gauge 57 and the tachometer 58 is transmitted to the turbine control device 80.

The turbine control device 80 includes a steam stop valve 19 . Controls the steam control valve 20 and bypass valve 22. Another control device is a feed water temperature control device 46 that adjusts the opening degree of the bleed valve 41 based on the output signals of the thermometers 54 and 55. Based on the output signal of the turbine control device 80, the extraction valves 37, 39
and a bleed valve control device 90 that controls the opening degree of each control rod drive device 41, and a control rod drive device control device vi that controls each control rod drive device 5.
100 are provided. 47 is a water supply temperature control device 46
and a signal selector that gives priority to the former output signal among the output signals of the bleed valve control device 90 and transmits it to the bleed valve 41. Furthermore, water level/output control device 70. Turbine control device i!
80. There is an overall control device 60 that controls the bleed valve control device 90 and the control rod drive device control device 100.

The operation of the BWRqffi plant of this embodiment having the above configuration will be outlined below.

In this embodiment, the reactor output is controlled by moving the control rods 4 in and out of the reactor core and adjusting the core flow rate (cooling water flow rate supplied to the reactor core 2).

Steam generated in the core 2 rises within the riser portion 9 and is guided into the steam separator 10. The steam-water separator 10 separates cooling water entrained in steam. The separated cooling water flows down into the annular downflow 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 in the steam separator 10 passes through the main steam pipe 17 to the high pressure turbine 13. It is further guided to the low pressure turbine 14 via 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 rotates a high pressure turbine 13 and a low pressure turbine 14. A generator 15 connected to these turbines
also rotates at the same time. Steam exhausted from the low pressure turbine 14 to the condenser 16 is condensed into water within the condenser 16. This condensed water is supplied to the water supply pipes 30, 31 and 3 as water supply.
3 and is again supplied into the reactor pressure vessel 1. That is, the condensed water in the condenser 16, that is, the feed water, is pressurized by the condensate pump 23, purified by the condensate demineralizer 24, and then transferred to each of the low-pressure feed water heater 25 and the high-pressure feed water heater 26. It passes through the heat exchanger tube and reaches a branch point 34.

The low pressure turbine 14 is connected to the shell inner space of the low pressure feed water heater 25 and the high pressure feed water heater 26 through bleed pipes 36 and 38.
Steam extracted from the high-pressure turbine 13 and the high-pressure turbine 13 is supplied. The flow rate of each bleed steam is controlled by bleed valves 37 and 39. The feed water introduced into the heat transfer tubes of each of the feed water heaters 25 and 26 is heated by the extracted steam supplied to the inner space of each shell, and its temperature is raised. The extracted steam is condensed within the shell inner space by heating the feed water;
Becomes a drain. This drain is returned to the condenser 16 via drain piping 42.

Now, a part of the water supply that has reached the branch point 34 is transferred to the water supply pipe 33
After being pressurized by the feedwater pump 29 , the water is discharged from the feedwater sparger 8 into the annular downward passage 45 in the reactor pressure vessel 1 . The cooling water discharged from the water supply sparger 8 also contributes to adjusting the water level within the reactor pressure vessel 1, as will be described later.

On the other hand, the remainder of the water supply that has reached the branch point 34 is transferred to the water supply pump 2
The water is pressurized at step 8 , guided into the heat exchanger tube of the high-pressure feed water heater 27 and heated, and then discharged from the nozzle 32 into the jet pump 6 . By discharging the supply water from the nozzle 32 into the jet pump 6 , the cooling water present in the annular downward flow path 45 is sucked into the jet pump 6 . High-temperature steam extracted from the high-pressure turbine 13 through a bleed pipe 40 is supplied to the shell inner space of the high-pressure feed water heater 27 . The bleed pipe 4o bleeds steam from the high pressure turbine 13 at a position upstream of the bleed pipe 38. Therefore, the temperature of the steam extracted in the bleed pipe 40 is higher than the temperature of the steam extracted in the bleed pipe 38.

The extracted steam guided into the shell inner space of the high-pressure feed water heater 27 heats the feed water flowing inside the heat transfer tube, and is condensed to become 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 serves as driving water for the jet pump 6 . From jet pump 6, nozzle 3
The supply water discharged from the jet pump 2 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
It is guided into the reactor core 2 from below.

This embodiment described above has the following features: (1) use of two types of feed water with different temperatures, (■) core flow rate control (finely adjustable output control compared to control rods) and water level control by water feed, and (III) in the event of an abnormality. We are implementing protection control at the plant, and control to improve the responsiveness of the (JV) generator output. These will be explained in detail below.

(1) Use of two types of feed water with different temperatures In this embodiment, a part of the feed water separated upstream of the high pressure feed water heater 27 is routed from the feed water sparger 8 to the reactor pressure vessel without passing through the high pressure feed water heater 27. The rest of the feed water is supplied into the reactor pressure vessel 1 (specifically, the jet pump 6) via the high-pressure feed water heater 27. . Therefore, the temperature of the water supplied to the water supply sparger 8 through the water supply pipe 33 is lower than the temperature of the water supplied as drive water into the jet pump 6 through the water supply pipe 31 by the amount that is not heated by the high-pressure water heater 27. It has become.

Conversely, the feed water used as drive water for the jet pump 6 is heated by the high-pressure feed water heater 27 and has a higher temperature than the feed water supplied to the feed water sparger 8 . However, the temperature of the feed water supplied to the Geno 1 pump 6 and the feed water sparger 8 is lower than the temperature of the cooling water in the reactor pressure vessel 1 . The temperature difference between those water supplies is
The temperature is adjusted to a predetermined value by controlling the opening of the bleed valve 41 by the feed water temperature control device 46. The feed water temperature control device 46 is
As shown in FIG. 3, it has a temperature estimator 46A, an adder 46B and 46C2, a controller 46D, and a function generator 46E. The temperature estimator 46A calculates the temperature TJSC of the suction water flow 45A (FIG. 4) sucked into the jet pump 6 based on the temperature Ts of the water supply (referred to as water supply sparger water) in the water supply pipe 33 measured by the thermometer 55. seek. The difference ΔT between the temperature TJ of the water supply (referred to as jet pump driving water) in the water supply pipe 31 measured by the thermometer 54 and the temperature TJSC is determined by the adder 46B. Function generator 4
6E is the difference ΔT between the reactor output QR and the set temperature.

The characteristic L3 of the relational expression is stored. Set temperature difference ΔT
o is determined corresponding to the reactor output QR.

Characteristic [53 is the alarm generation line L2 in FIG. 10, which will be described later.
It is located below the jet pump and is set so that the temperature difference between the jet pump drive water and the water supply sparger water is the required value. Function generator 46E outputs a set temperature difference ΔTO corresponding to reactor power QR measured by output detector 56. Set temperature difference Δ output from function generator 46E
TO and the temperature difference ΔT output from the adder 46B are input to the adder 46C. Adder 46C is set temperature difference Δ
The deviation TX between To and the temperature difference ΔT is determined. Controller 46
D outputs an opening signal STl for the bleed valve 41 based on the deviation Tx. The opening degree signal STt is sent to the signal selector 47.
can be conveyed to. The signal selector 47 is connected to the bleed valve control device 90
The opening signal STt is given priority to the bleed valve 41 over the opening signal STx, which is the output of the opening signal ST.
When the opening signal STZ is not output, that is, when the opening signal STZ corresponds to a signal V4 at level 0, which will be described later, the opening signal ST1 is selected and transmitted to the bleed valve 41. That is, the bleed valve opening controller 91 of the bleed valve control device 90 (
14) is functioning (when the deviation signal U, which is the output of the adder 91A in FIG. 14, is negative), the opening degree of the bleed valve 41 is the output of the feed water temperature control bag 5!46. It is adjusted by the opening signal S'r1. In this way, the feedwater sparger 8-ja water having a temperature lower by a predetermined temperature difference than the jet pump drive water discharged from the nozzle 32 is supplied from the feedwater sparger 8 into the reactor pressure vessel 1, so that the water is lowered in an annular manner. The temperature of the cooling water descending through the flow path 45 decreases, and as a result, the low-temperature cooling water is sucked into the jet pump 6 by the water supply jetted from the nozzle 32. Therefore, cavitation of the jet pump 6 can be prevented from occurring. The temperature difference between the two water supplies mentioned above is controlled so as to satisfy a predetermined value during one normal operation. However, as long as the temperature difference between both water supplies satisfies a predetermined value, the temperature of the water supply flowing through the water supply pipe 31 may not be increased significantly. What is important in this regard is the enthalpy of the cooling water that is further separated in the steam separator 10 and flows down to the annular downflow passage 45 based on the enthalpy of the cooling water at the core inlet required by the core characteristics, and the enthalpy of the cooling water that flows into the annular downflow passage 45 and the water supply piping 31.
The temperature of the water supply in the water supply pipe 31 is determined by taking into consideration the enthalpy of each water supply in the water supply pipe 31 and 33. The bleed valve 41 is set so that the thus determined temperature of the water supply in the water supply pipe 31 is higher than the temperature of the water supply in the water supply pipe 33 by a predetermined value.
It is adjusted by controlling the opening degree of.

As described above, as in this embodiment, the water supply pipes 31 and 3
By creating a temperature difference in the feed water flowing through the reactor pressure vessel 1 (by lowering the temperature of the feed water in the water supply pipe 33), there is no need to provide a heat exchanger inside the reactor pressure vessel 1 as in the conventional example. Since the internal structure can be significantly simplified, installation of the reactor core structure into the reactor pressure vessel 1 becomes significantly easier. Since there is no need to provide a heat exchanger within the reactor pressure vessel 1, one nuclear reactor can be downsized. Furthermore, maintenance and inspection work for the heat exchanger in the reactor pressure vessel 1, which is highly activated, which is required in the conventional example, is eliminated. In addition, in this embodiment, the temperature of the feed water in the water supply pipe 31 and the temperature inside the water supply pipe 33 are determined by the implementation and non-performance of heating by the high-pressure feed water heater 27, which is located outside the reactor pressure vessel 1 and is necessary for heating the feed water. The temperature of the cooling water sucked into the jet pump 6 (the cooling water in the annular downward flow path 45) can be significantly lowered than in the conventional example.

Therefore, this embodiment has a jet pump 6 that is different from the conventional example.
This significantly increases the range in which cavitation can be prevented, and enables significant changes in reactor output through core flow control. In this embodiment, load follow-up operation can be easily performed, and load follow-up operation can be performed to a large extent by controlling the core flow rate.

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 flow path.
The cooling effect of the cooling water in the annular descending passage by the jet pump driving water using the heat exchanger installed in the reactor pressure vessel is also small, and the temperature of the cooling water sucked into the jet pump is less likely to decrease.

Therefore, in the conventional example, the range in which cavitation can be prevented by the jet pump is narrower than in the present embodiment, and it is not possible to cope with the occurrence of cavitation when the reactor output is significantly changed during load following operation. Furthermore, water supply piping 33
is branched upstream of the high-pressure feed water heater 27, which is a necessary device for the water supply system, so a cooling device is required to make the temperature of the water supply in the water supply pipe 33 lower than the temperature in the water supply pipe 31. Moreover, it is not necessary to install a new heater to heat the water supply in the water supply pipe 31. In this embodiment, there is no need to provide a recirculation system with recirculation system piping or an internal pump with a complicated structure, which was conventionally installed in the containment vessel surrounding the reactor pressure vessel 1, and the water supply pump 28 and 29 is installed outside the containment vessel, the containment vessel can be made smaller, and the structure inside the containment vessel can also be simplified. Since a recirculation system and an internal pump are no longer required and maintenance and inspection thereof are no longer necessary, the time required for maintenance and inspection of the nuclear reactor plant is shortened.

In this embodiment, the water supply pipe 33 is branched upstream of the high-pressure water heater 27 at the final stage, but BWs with different absolute values of rated output
For the R power generation plant, the water supply pipe 33 may be branched from the water supply pipe 30 on the upstream side of the feed water heater in two or three stages upstream from the high-pressure feed water heater 27 in the final stage, if necessary. As a result, the temperature of the water supplied in the water supply pipe 33 can be significantly lowered than the temperature of the water supplied in the water supply pipe 31 compared to the above embodiment. Some of the feedwater heaters required for nuclear reactor plants, especially the final stage high-pressure feedwater heater, are bypassed and a portion of the feedwater is guided to the feedwater sparger 8, so it can be guided to the feedwater sparger 8 with simple equipment. The temperature of the feed water can be lowered than that of the feed water supplied to the jet pump 6 as driving water.

In order to improve the thermal efficiency of a nuclear reactor plant, it is desirable to set the opening of the bleed valve 41 so that it is close to a fully open state, maintain this state, and not perform significant opening control. For this reason, the bleed air pipe 40 is adjusted so that the temperature inside the water supply pipe 31 at the outlet of the feed water heater 27 is higher than the temperature inside the water supply pipe 33 by the set temperature difference ΔTo according to the reactor output QR.
It is desirable to set the connection position of the inlet and the amount of extracted steam of the extraction piping 40.

In this example, the use of two types of water supply with different temperatures is as follows:
This was brought about by the following study results.

According to conventional core thermal design, the core flow rate We driven by the recirculation system is approximately seven times the total feed water flow, jiWFw (equal to the main steam flow rate VMS during steady-state operation).

Therefore, based on the conventional core design, even if all the water supply is directly directed to the jet pump 6 as driving water, the jet pump 6 needs an M ratio of approximately 6.0 as determined by the following equation. becomes.

However, in reality, in order to control the reactor water level, it is necessary to divert a part of the total feed water flow to the feed water sparger 8 at the branch point 34, and the reactor water level (also referred to as the reactor water level) must be controlled by other variables. This is because they need to be controlled independently. Assume 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 water supply sparger flow rate is Ws, the jet pump driving water flow rate is W,+, and the reactor core thermal design is the same, the following equation holds true.

Wc=7 WFW=(M+1)・-WFW 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 rated output.

Basically, the following four methods can be considered to increase the M ratio.

(1) Increase the pressure of the driving water of the jet pump to increase the flow rate of the driving water flowing through the jet pump throat.

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

(3) Lower the temperature of the suction water flow sucked into the jet pump.

(4) Use a multistage jet pump.

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

Suction water flow (flow of cooling water in the annular descending flow path 45) 45A is sucked into the throat portion 7 by the jet pump driving water flow 31A, and after these water flows are mixed, the jet pump is transferred to the jet pump via the differential user 6A of the jet pump 6. 6 to exit 6B. FIG. 4 further shows changes in the pressure Ps of the suction water flow 45A and the pressure PD of the jet pump driven water flow at this time along the flow direction.

The pressure of both water streams becomes the minimum pressure PM at the throat portion 7, and then the pressure of the water stream increases due to the effect of the diffuser 6A, and the discharge pressure I] at the outlet 6B.

is obtained. By the way, in order to increase the M ratio, if the above-mentioned method (1) is adopted and the driving water flow 31A with a significantly high pressure po, or in other words with a significantly high flow velocity, is used, the suction water flow 45A becomes lower than the saturation pressure at the throat portion 7. The temperature decreases, and bubbles are generated (called cavitation).
If cavitation occurs, the efficiency of the jet pump 6 will be significantly reduced, and equipment may be damaged. Therefore, it is important to prevent cavitation from occurring and to increase the M ratio.

The method of increasing the M ratio without causing cavitation in the jet pump 6 is because cavitation is caused by boiling that occurs when the pressure PM of the throat part 7 becomes lower than the saturation pressure of the suction water flow 45A. The purpose is to make the temperature of the water stream 45A sufficiently low so that it does not boil under the pressure PM. That is, the above (
This is the adoption of method 3). A conventional example based on this idea is the aforementioned Japanese Patent Publication No. 43-23117 entitled ``Nuclear Reactor Apparatus.'' In this conventional example, as a means for lowering the temperature of the suction water flow, the reactor pressure vessel 1 is connected to the water supply pipe 31 shown in FIG.
A group of heat transfer tubes of a heat exchanger are connected within the pipe, and heat exchange is performed between the jet pump driving water and the suction water flow supplied through the water supply pipe. The temperature difference between this conventional jet pump drive water and suction water flow is small,
Furthermore, there was a practical problem because the length and size of the heat exchanger did not allow for sufficient space. In addition, this conventional example.

Method (4) is also used.

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

In this embodiment, the method (2) is also adopted, and the reactor configuration is such that the discharge pressure Pa of the jet pump 6 is reduced. The discharge pressure Po is mainly controlled by the core 2. Core exit chamber (
plenum), steam/water separator 10 and standpipe 11
It needs to be larger than the pressure loss (static pressure + dynamic pressure) based on For this reason, a chamber in which the core outlet chamber is extended above the core 2 (for example, a chamber extended to the vicinity of the water supply sparger 8), that is, a riser portion 9 is provided. Risers are also called chimneys. As a result, a large amount of two-phase flow exists above the core 2, and the natural circulation force based on the buoyancy of the bubbles increases. Since the cooling water is driven by this natural circulation force, the required discharge pressure of the jet pump 6 can be reduced compared to the case where the riser portion 9 is not provided. The discharge pressure Pa in FIG. 3 is the pressure P of the jet pump driving water flow 3LA.

depends on the size of. If the discharge pressure Po is sufficiently small, the pressure P of the jet pump 6 is too large.

It is possible to obtain a large M ratio even if the jet pump is not driven by water.

(■) 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/output control device 7.
It is done by 0. The water level/output control bag [170 is a water level controller 71. It is composed of a furnace discharge master controller 72 and a plant state determination section 73.

The configuration of the water level controller 71 is shown in FIG. The water level controller 71 includes a regulator 71A, a switch 71B, and adders 71C, 71D, 71E, and 71F. The water level controller 71 contains the reactor water level LR measured by the water level gauge 50.
, the jet pump driving water flow rate WJ measured by the flowmeter 51, the feedwater sparger flow Ws measured by the flowmeter 52, the main steam flow rate WM measured by the flowmeter 53, and the output from the central control device 60. A three-element/-element control switching signal Sθ^ is input. Switch 71B is.

If the input three-element/-element control switching signal S9^ indicates three-element control, it is closed, and if the three-element/-element control switching signal So^ indicates one-element control, it is closed. be done. The three-element/-element control switching signal S9^ instructs one-element control until the reactor output (approximately 10% output) is reached, at which the turbines 13 and 14 are combined.

The adder 71c inputs the input reactor water level LR and the reactor water level set value LR.
Find the deviation from O. The adder 71E adds the jet pump driving water flow rate W,+ and the water supply sparger flow rate Ws. Adder 71F determines the deviation between the output signal of adder 71E and main steam flow rate WM. When the switch 71B is closed based on the three-element/-element control switching signal S9^ (instructing three-element control), the deviation signal output from the adder 71F is input to the adder 71D. switch 7
1B is opened based on the three-element/-element control switching signal s9^ (-element control instruction), the adder 71
The deviation signal output from the adder 71D is not input to the adder 71D. When the switch 71B is closed, the adder 71D (
(when the reactor output exceeds 10%), adders 71C and 7
Input each output signal of 1F and add each signal. When switch 71B is open (when reactor output is 10% or less).

Adder 71D outputs the output signal of adder 71C as is. The regulator 71A outputs the feedwater sparger flow rate request signal Wso so that the reactor water level reaches the reactor water level set value LRO based on the output signal of the adder 71D. This water supply sparger flow rate request signal W s o becomes the output of the water level controller 71 and is input to the plant state determiner 73 .

The furnace discharge master controller 72 has a configuration shown in FIG. That is, the furnace output master controller 72 has a regulator 72A and a switch 72B that switches between fixed terminals A and B. The furnace output master controller 72 receives a load change request signal εLoAD and a manual load change request signal εN output from the overall control device 60.
and manual/automatic switching signal Ssa are input.

These load demand signals are the difference between the actual reactor power and the target reactor power (or the difference between the actual and target electrical output of generator 15).

The load change request signal εLOAD is input to the fixed terminal A. A manual load change request signal ε is input to the fixed terminal B. Switch 72I3 is 1 manual/automatic switching signal S
Connected to fixed terminal B when ea indicates manual operation. The regulator 72A outputs a load change request signal ε. ^D or εH is input, and the jet pump driving water flow rate request signal W J O is output so that each load change request signal becomes zero. This request signal WJO is sent to the plant state determiner 7.
3 is input.

When the BWR power generation plant is operating normally (not in an abnormal state), the plant state determiner 73 shown in FIG.
O and jet pump driving water flow rate request signal W J O
The respective values are output as they are as the water supply sparger flow rate request signal WSP and the jet pump driving water flow rate request signal WJD. The detailed configuration and functions of the plant state determiner 73 will be explained in the next section (III).

The water supply sparger flow rate request signal Wsp is the water supply sparger flow rate request signal Wsp.
is input. The feed water pump 29 changes its rotation speed according to the feed water sparger flow rate request signal Wsp, and adjusts the reactor water level LR.
The flow rate of the feed water flowing through the water supply piping 33 is adjusted so that the reactor water level becomes the set value LRO.

As a result, regardless of the reactor output, the reactor water level LR
can be maintained at a predetermined level.

The jet pump driving water flow rate request signal W J o is input to the water supply pump 28 . The feed water pump 28 changes its rotational speed according to the jet pump drive water flow rate request signal WJD, and adjusts the flow rate of the feed water flowing through the water supply pipe 31 so that the reactor output QR becomes a predetermined reactor output. Control of the flow rate of the feed water in the water supply pipe 31 is similar to a recirculation system having a conventional recirculation pipe, in which the core flow rate discharged from the jet pump is adjusted, leading to control of the reactor output. Fine control of the reactor output based on changes in the core flow rate due to the water supply in the water supply pipe 31 of this embodiment is achieved by
This is carried out in the power control region based on the core flow rate (high power region exceeding the power at which PCMI is started) as shown in Publication No. 11038. Output control in the region below the output that starts PCMr is performed by the control rod 4 as in Japanese Patent Publication No. 57-11038.

Changing the reactor output by controlling the flow rate of the driving water of the jet pump is similar to this embodiment and the conventional B with a recirculation system.
Same as WR power plant.

However, conventional plant recirculation systems use a jet pump driven water stream that has approximately the same temperature as the jet pump suction water stream. On the other hand, in this embodiment, the influence W of the temperature change of the jet pump driving water flow 31A (M ratio is 10
(about 1/10), the temperature of the core flow rate also changes slightly, which further changes the core void reactivity. Therefore, the change characteristics of the reactor output in this example are slightly different from those in the case where a conventional recirculation system is used, as shown in FIG. The change characteristics of the former will be at a higher level than those of the latter.

In this embodiment, the water level in the reactor pressure vessel 1 is controlled by controlling the rotation speed of one of the water supply pumps based on the output signal of the water level controller 71 and adjusting the water supply flow rate in the water supply pipe 33. Since the rotation speed of the water supply pump 28 is not controlled at this time, the water level can be easily controlled. Further, the reactor output can be easily controlled because the rotation speed of one of the feed water pumps 28 may be controlled based on the output signal of the reactor output master controller 72.

(01) Protection control in abnormal situations In a BWR power plant with a conventional recirculation system, the total feed water flow ffiWFw was used to control the reactor water level. However, in this embodiment, most of the water supply (2.WFI/
3) is used for controlling the reactor power discharged into the jet pump 6, and the remaining feed water (WFw/3) is used for controlling the reactor water level. Therefore, the reactor water level is 51
! ! Capacity is reduced compared to BWR power plants with conventional recirculation systems. Even in this case, no problem occurs during normal operation. If the plant status of the BWR power plant undergoes a significant and sudden change, or if it is abnormal,
Reduction in reactor water level. Significant fluctuations may occur. The possibility of such a phenomenon occurring needs to be avoided. Therefore, this embodiment takes two measures against this problem.

The first is to increase the capacity of the water supply pumps 28 and 29. In this embodiment, the minimum required capacities of the water supply pumps 28 and 29 are 2WFW/3 and WF!, as described above.
/3. The larger the capacity of these pumps, the wider the control range of the reactor output and the control range of the reactor water level. For this reason, the pump capacity of the water supply pump 29 is set to 300.
%, the pump capacity of the water supply pump 28 is increased to 105%, and the pump capacity of the condensate pump 23 is increased to 1.7 times that of the conventional one. Thereby, even if a sudden drop in the reactor water level LR occurs, the water supply sparger flow rate Ws can be increased over time.

The second is protection by the plant state determiner 73.

The configuration of the plant state determiner 73 will be explained based on FIG. 8. The plant state determiner 73 includes flow rate request signal regulators 73A and 73B, a limiter 73C, and a state determiner 73.
D, temperature estimator 73E.

It has an operating state determiner 73F and an adder 73G.

The plant state determiner 73 receives trip signals SWt, B
A plant state quantity Xp measured by a detector installed in the WR power generation plant, and a water supply temperature TJ in the water supply pipe 31 measured by a thermometer 54.

Supply water temperature T in the water supply pipe 33 measured by the thermometer 55
s, and the reactor power Q measured by the power detector 56
R, and the above-mentioned sparger flow rate request signal Wso and jet pump drive water flow rate request signal WJD are input.

After inputting the trip signal SWT, the state determiner 73D determines whether the plant state quantity Xp affected by the trip signal SWt has deviated from a predetermined regulation level. When the l-rip signal SWT is not input and when the plant-like MmXP is within the specified level even if the trip signal SW↑ is input, the state determiner 73D sends an open signal to the on-off valve 35 as a valve switching signal 89C, and outputs an open signal to the on-off valve 35. A close signal is output to 44. When it is determined that the plant state iXp deviates from a predetermined regulation level, the state determiner 73D sends a change instruction signal Ss of the flow rate request signal according to the trip signal Swr to at least one of the flow rate request signal regulators 73A and 73B.
The on-off valve 35 .
44. Depending on the trip signal SWt, there is no need to switch between opening and closing the on-off valve 35°44. The flow rate request signal regulator 73A inputs the change instruction signal SS, modifies the sparger flow rate request signal Wso according to the signal Ss, and outputs it to the water supply pump 29 as a sparger flow rate request signal Wsp. The flow rate request signal regulator 73B inputs the aforementioned change instruction signals S, +, modifies the jet pump driving water flow rate request signal WJO' output from the limiter 73C according to the signal SJ, and adjusts the jet pump driving water flow rate request signal WJO' output from the limiter 73C. It is output to the water supply pump 28 as a driving water flow rate request signal WJD. When the determination result signal LM output from the operating state determiner 73F is zero (when the first rotation state is normal), the limiter 73C outputs a jet pump driving water flow rate request signal W.
JO is directly output to the flow rate request signal regulator 731'3 as a jet pump driving water flow rate request signal WJO'.

Flow rate request signal regulators 73A and 73B, status determiner 73
The action of D will be explained with respect to a specific trip signal SWT, for example, the "main steam isolation valve closed" signal.

The reactor is scrammed by rapidly inserting the control rods 4 into the reactor core 2 in response to the "main steam isolation valve closed" signal. After inputting the "main steam isolation valve closed" signal, the status determiner 43D inputs a change instruction signal Ss of "increase in water supply sparger flow rate request signal Wso" and a "jet Pump drive water flow rate request signal WJO' change instruction signal SJ and on-off valve 35 are closed and on-off valve 44
A valve switching signal S90 is output to open the valve. When the trip signal SWT is a "main steam isolation valve closed" signal, change instruction signals Ss and SJ and valve switching signal S9c are output. The valve switching signal Sec closes the on-off valve 35 and opens the on-off valve 44. The flow rate request signal regulator 73A increases the water supply sparger flow rate request signal Wso by increasing the water supply sparger flow rate request signal Wso based on the change instruction signal Ss.
Output SP. The flow rate request signal regulator 73B outputs the jet pump driving water flow rate request signal WJc)' as the jet pump driving water flow rate request signal WJD based on the change instruction signal SJ. 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. The water discharged from the water supply pump 28 is transferred to the water supply pipe 31. Bypass piping 43 and water supply piping 3
3 and is supplied into the reactor pressure vessel 1 from the water supply sparger 8. Although the water supply flow rate supplied from the water supply sparger 8 increases, the water supply/output control device 70. In particular, the water level controller 71 maintains the reactor water level LR in the reactor pressure vessel 1 at a predetermined level. In addition, the valve switching signal s9c
The reason for closing the on-off valve 35 and opening the on-off valve 44 is to close the on-off valve 35 and open the on-off valve 44 because a large amount of the core 2 of the reactor is scrammed by the drive of the Jets I-pump 6 based on the action of the feed water discharged from the nozzle 32. This is to prevent the flow rate from being supplied.

When a turbine trip occurs, the state determiner 73D does not output the valve switching signal Sec, and outputs the water supply sparger flow rate request signal Wso and the jet pump driving water flow rate request signal WJ.
Change instruction signal Ss to reduce O' to a predetermined level
and output SJ.

With the above configuration, it is possible to prevent the reactor water level LR from fluctuating rapidly during various types of trips.

The state determiner 73D has a memory that stores change instruction signals Ss and SJ and a valve switching signal Sec for various trip signals 5ljr. This memory may be installed separately from the state determiner 73D. Status determiner 73
D searches the memory for each signal corresponding to the input trip signal SWt.

The plant condition determiner 73 includes a first protection section that corrects each flow rate request signal at the time of trip, which is composed of the aforementioned flow rate request signal regulators 73A and 73B and a condition determiner 73D, and a first protection section that corrects each flow rate request signal at the time of tripping, and a first protection section that corrects each flow rate request signal when the operation condition described below deviates from an allowable range. It has a second protection part that limits the jet pump driving water flow rate request signal. Next, the second protection section will be explained in detail.

Like the temperature estimator 46A, the temperature estimator 73E determines the temperature TJSC of the suction water flow 45A sucked into the jet pump 6 based on the temperature Ts of the supplied sparger water. Jet pump driving water temperature TJ and temperature TJSC
The temperature difference ΔT between the two and the same is calculated by the adder 73G. The operating state determiner 73F inputs the reactor output QR and the temperature difference ΔT, and determines whether the current operating state determined based on these values is within an allowable range. Operating state determiner 73
F stores characteristics based on the reactor output QR and the temperature difference ΔT shown in FIG. In FIG. 10, the area above line Ll is a driving prohibited area. Line L2 is an alarm generation line, and the area below the alarm generation line Lz is an operation permissible area.

The position determined by the reactor output QR and the temperature difference ΔT is
If the operating state is within the allowable operating range, the operating state of the BWR power plant is normal. That position is alarm generation line L2
If it is in the upper region, the operating state of the BWR power plant is in an abnormal state. The operating state determiner 73F outputs a judgment result signal LM whose level is "0" when the operating state is normal, and outputs a judgment result signal LM whose level is "1" when the operating state is abnormal. do. When the operating state is abnormal, this is when a point X determined by the actually measured reactor output QR and temperature difference ΔT enters a region above the alarm generation line Lx. Alarm generation line LZ from point X
If it touches from below, the driving state determiner 73F outputs an alarm, and this alarm is displayed on a display device (not shown).

The determination result signal LM is input to the limiter 73G.

Limiter 73C has control characteristics shown in FIG. The solid line is the characteristic when the judgment result signal LM is "0",
The broken line indicates the characteristic when the determination result signal LM is "1". Therefore, the limiter 73C converts the jet pump driving water flow rate request signal WJO input when the operating state is abnormal to the jet pump driving water flow rate request signal WJQ shown by the broken line.
'Limited to value. Thereby, it is held at a point or at a position on the alarm generation line Lz. Therefore, jet pump 6
The jet pump drive water flow rate is not adjusted to such a level that cavitation occurs within the jet pump.

(IV) Control for Improving Responsiveness of Generator Output This control is performed by the turbine control device 80 and the bleed valve control device 90. The detailed configuration of these control devices is shown in FIG.

The turbine control device 80 is a pressure controller 80A.

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

The electrical output of the generator ff1Ia16 is determined by the true amount of steam flowing through the high pressure turbine 13 and the low pressure turbine 14. This amount of steam is adjusted by a steam control valve 20. There are two modes for controlling the opening degree of the steam control valve 20. The first mode is the steam pressure Ps (
(measured by a pressure gauge 57 provided in the main steam pipe 17) to a value close to the set pressure pso (reactor pressure constant control). That is, the measured pressure Ps, the set pressure Pso, and the initial pressure that is the output of the initial pressure regulator 80D are input to the adder 80G, and the initial pressure and the deviation signal between the measured pressure Pa and the set pressure Pso are input to the pressure controller 80A. is input. The pressure controller 80A outputs a signal v1 based on the deviation signal. The signal Vl is a low value priority gate 80C2.
It is output to adders 801 and 80H. The low value priority gate 80C selects a low level signal from the signal v1 and the signal Vz and outputs it to the controller 80F. Normally, one communication v1 is small and the signal Vz is selected. The controller 80F controls the opening degree of the steam control valve 20 based on the output signal of the low value priority gate 80C. Controller 80E
controls the opening degree of the bypass valve 22 based on the signal vl 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 output increases, the steam pressure increases, the steam control valve 20 opens in response to the signal Vz, the flow rate of steam supplied to the turbine increases, and the output of the generator 5 increases. The second mode is for responding to requests from the power system, changes in the rotational speed of the generator 15, and the like. The speed controller 80B determines the deviation value between the rotational speed R of the generator 15 (turbine) measured by the tachometer 58 and the target value Li5t.

A signal Vz corresponding to this deviation value is output. In addition, the speed controller 80B detects a short-period, small-width output change component that requires quick dissolution from the signal Vz (with a period of less than a few tens of seconds and a change width of 5
%) to create a load change request signal εL and output it to the bleed valve controller 90A. The aforementioned signal (2) is input to the low value priority gate 80C and the adder 80J. When the low value priority gate 80G selects the signal Vz instead of the signal v1, the controller 80F controls the opening degree of the steam control valve 20 based on the signal V2. The adder 80J is
The sum signal of the signal Vz and the bias signal is output to the adder 80H. The adder 80H sends a deviation signal (jet pump driving water flow rate change request signal εQ) between the signal v1 and the output signal of the adder 80J to the initial pressure regulator 80D and the bleed valve control device 9.
0 to the adder 90E. The jet pump driving water flow rate change request signal ff1Q is a reactor output change request signal.

The aforementioned two modes are selected by low value priority gate 80G. During normal operation of the BWR power plant, a bias value of 10% in terms of reactor output is added to the signal v2 by the speed controller 80B so that the first mode is selected. but,
When the rotational speed R+ fluctuates greatly and the signal Vz changes greatly, the steam control valve 20 is adjusted by the signal v2. The initial pressure regulator 80D is used to make the generator output respond quickly.

The purpose is to supplementally operate the steam control valve 20 before the effect of the (quite slow) response of the water level/output control device 70 that controls the flow rate of the jet pump drive water appears.

In this embodiment, the bleed valve 3 is controlled by the output signal of the bleed valve controller 90A.
7, 39, and 41, corrects the jet pump drive water flow rate change request signal εQ output from the turbine control device 80 using the output signal, and controls the load change request signal ILOAD obtained by the correction. 60 to the furnace output master controller 72 of the water level/output control device 70.

The bleed valve controller 90A that receives the load change request signal εL determines the bleed valve closing signal (inverse of the opening signal) εV based on the signal EL, and uses this signal to drive the bleed air amount distributor 90B and the jet pump. It is output to the water flow rate compensation controller 90C. The bleed air amount distributor 90B specifies the opening degrees of the bleed valves 37 and 39 based on the closing degree signal εV, and controls the feed water temperature control device 4.
The opening degree of the bleed valve 41 is designated based on the temperature difference ΔT outputted from 6. The opening degree of the bleed valve 41 is controlled by the bleed air distributor 90B when the temperature difference ΔT exceeds the alarm generation line Lz shown in FIG. The jet pump drive water flow rate compensation controller 90C outputs a jet pump drive water flow rate compensation signal εFW that is proportional to the input bleed valve closing signal εV for the purpose of compensating for a decrease in the reactor inlet feed water temperature.

This signal fFW is input to adder 90E. Adder 90E receives jet pump driving water flow rate change request signal εQ
is corrected by adding a compensation signal εFW, and the load change request signal εLOAD obtained by the correction is output to the overall control device 60. The water level/water supply control device 70 receives the load change request signal εLOAD from the general control device 60 as described above, and adjusts the rotation speed of the water supply pump 28 based on this request signal. This changes the core flow rate.

The configurations of the bleed air valve controller 90A and the bleed air amount distributor 90B will be described below. Specifically, the bleed valve controller 90A
The configuration is shown in FIG. 3, and the switches 90A1. and a regulator 90A2. The switch 90Az is normally open, and is opened manually, for example, when the function of this embodiment is not activated. The regulator 90A2 is a proportional/integral type regulator. The bleed air amount distributor 90B has bleed valve opening controllers 91 and 92 and a function generator 93, as shown in FIG. The function generator 93 is connected to the output detector 56
and the adder 91A.

The bleed valve opening degree controller 91 controls the opening degree of the bleed valve 41, and includes adders 91A and 91D, and a function generator 9.
1B and a PI controller 91G. Adder 91A
is also connected to the feed water temperature control device 46 and the function generator 91B. The PI controller 91G is a function generator 91B.
has been contacted. The adder 91D is a PI controller 91G.
is connected to the output terminal of the signal selector 47 and the input terminal of the signal selector 47. A bleed valve opening controller 9 that adjusts the openings of the bleed valves 37 and 39
2 are regulators 92A and 92 connected to adder 90D.
It has B. The regulator 92A is connected to the bleed valve 37, and the regulator 92B is connected to the bleed valve 39.

The responses of each part according to this embodiment are as follows. First, an increase in the load on the power system causes a decrease in the rotational 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 (zero in normal times, positive value side in this case). The bleed air controller 90A, which receives the load change request signal εL, uses a proportional/integral type regulator (proportional gain Kp, + integral gain) 90Az to obtain a closing signal EV indicating how far the bleed valve should be closed.

This closure signal εV 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, so a description thereof will be omitted.

The deviation signal Va obtained by the adder 90D is transmitted to the bleed air amount distributor 90B, and is sent to the regulator 9 of the bleed valve opening controller 92.
2A and 92B. The regulator 92A outputs an opening signal STa corresponding to the deviation signal 8 to the bleed valve 37. The bleed valve 37 is adjusted to a corresponding opening based on the opening signal STs. The regulator 92B outputs an opening signal ST& corresponding to the deviation signal v8 to the bleed valve 39. Bleed valve 39
is adjusted to a corresponding opening degree based on the opening degree signal ST4. The bleed valve opening controller 92 controls the bleed valve 37 and the bleed valve opening controller 92 in order to respond quickly to changes in the output of the generator 16 (change width is within 5% with a period of several tens of seconds) based on the output of the tachometer 58. Controls the opening degree of 39. Therefore, it is possible to deal with output fluctuations of the generator 16, which have a small variation in a short period, in a short period of time. That is, by rapidly decreasing the opening degrees of the bleed valves 37 and 39 based on the opening degree signals STs and STa described above to reduce the amount of bleed steam, the rotational speeds of the turbines 13 and 14 are increased and [L is reduced to zero. return.

The temperature difference ΔT obtained by the adder 46B of the feed water temperature control device 46 is input to the adder 91A of the bleed valve opening controller 91. The function generator 93 determines the temperature difference ΔT1 based on the reactor power QR measured by the power detector 56. The function generator 93 stores a relational expression (corresponding to the expression of the alarm generation line L2) indicating the relationship between the temperature difference ΔT1 and the reactor output QR. The temperature difference T1 obtained by the function generator 93 is input to the adder 91A. Adder 91A
calculates the deviation signal u (=ΔTs−ΔT). The function generator 91B outputs a signal v4 at level 0 when the deviation signal U is 0 or more, and outputs a corresponding negative signal v4 when the deviation signal U is negative. The PI controller 91C outputs a control signal based on the signal v4. Adder 91
D determines the opening signal STx based on this control signal and outputs the opening signal STz to the signal selector 47. The signal selector 47 selects either of the input opening degree signals ST1 and Sr1 as described above, and transmits the selected opening degree signal to the bleed valve 41. The opening of the bleed valve 41 is adjusted based on the opening signal selected by the signal selector 47. By reducing the opening of the bleed valve 41 based on the opening signal STz, even if the temperature difference ΔT corresponding to any reactor output QR exceeds the alarm generation line L2, the temperature difference ΔT is immediately lower than the alarm generation line L2. It is possible to shift to operation within the permissible operation range. The bleed valve opening controller 91 is a type of protection device for shifting the operation of the nuclear reactor to a safe state when the operation is performed in a region above the alarm generation line L2.

The response characteristics of the control based on the function of the bleed valve opening controller 92 are shown on the short-time scale time axis in FIG.

The influence of the increase or decrease in the amount of extracted steam also affects the turbine inlet side and the reactor pressure vessel side, and various variables.

Grid output request QL (reflected in load change request signal EL)
, each with its own unique delay and amplitude.

Therefore, it has extremely good load following characteristics overall.

However, suppose that a situation occurs in which the load change request signal ε swings only to the positive value side for a relatively long period of time (several minutes or more) (changes in the load request and load set point of the power system, etc.) ). At this time as well, the turbine output is responsive to the above-mentioned control of the extracted steam. However, since the bleed valve is kept from fully open to some degree closed,
The amount of bleed steam supplied to the feed water heaters 25, 26 and 28 decreases, and the feed water temperature begins to gradually decrease.

In this embodiment, in order to compensate for this decrease in the feed water temperature, as described above, the load change request signal E
D is transmitted to the furnace output mask controller 72 of the water level/output control device 70 via the general control bag [1W60. That is, as shown in FIG. 13, since the bleed valve controller 90A includes an integral term KI/S (KI is an integral gain), the signal EV is the integral value of the signal EL, in other words, the cut bleed steam amount. It shows the integral quantity of. therefore,
If the jet pump drive water flow rate (core flow rate) is increased by an amount commensurate with this integral amount, the reactor power will gradually absorb the increase in turbine power, and the amount of extracted steam cut will eventually become zero. Therefore, there will be no significant drop in the water supply temperature.

Specifically, as the jet pump driving water flow rate increases (its speed is given by the water level/output control device '70), the reactor power increases, and the turbine control device 80 keeps the reactor pressure constant. As the steam control valve Cv is opened and the rotation speed of the turbine (generator 15) is about to increase further than the target value, the signal [L becomes a negative value and the signal ε■ gradually decreases. Start, bleed valve 37
and heading in the direction of 39 fully open. In this embodiment, an increase in the output of the generator 15 when the load on the power system increases or when the load setting in load following operation increases is initially covered by cutting the amount of extracted steam, and then increasing the reactor output. covered by When the reactor power increases, the opening degrees of the bleed 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 εQ is corrected based on the signal εFW, a decrease in the feed water temperature can be suppressed in a short time, and thermal shock to the structure of the reactor pressure vessel can be alleviated.

The responses of various variables at this time are shown by solid lines on the long-term scale in FIG.

When the water supply temperature decreases and increases and decreases are repeated over a considerable period of time, the first effect is
In some cases, repeated thermal stress on structural materials such as water supply nozzles can become a problem.

In this embodiment, it is possible to suppress the thermal shock to the internal structure that occurs at this time, and also to significantly reduce the thermal fatigue that occurs in this structure. Secondly, it is considered that the thermal behavior within the core 2 changes significantly. That is, when increasing the reactor power by the same amount, the boiling start point moves only slightly when the reactor core flow rate increases, but the boiling start point moves significantly when the feed water temperature decreases. Along with this,
The axial power distribution also changes when the core flow rate increases.
In contrast, when the feed water temperature decreases, local changes are large and the distortion becomes large compared to the distribution before the reactor power change. Therefore, fluctuations in the water supply temperature are accompanied by the movement of hot spots, resulting in repeated fluctuations in the positions where hot spots occur. In this embodiment, such problems can also be solved.

Further, in this embodiment, by providing the above-mentioned bleed valve control device 90, it is possible to change the output in a small range and in a short period (normally referred to as AFC operation or governor free operation mode), and also to change the output in a large and relatively slow manner. Since the flow rate control (controlled by the water level/output control device 70) of the jet pump drive water, which is the water supply that controls the water supply, is also used, it has a wide range of output changing functions.

The bleed valve opening controller 92 and function generator 93 in this embodiment are removed from the bleed air amount distributor 90B, and the signal selector 47 is
It may also be installed in the feed water temperature controller 46.

According to this embodiment, the ability of the turbine output to quickly adjust to load fluctuations is improved.

(V)g General Control Unit Finally, the specific configuration of the general control unit 60 will be explained. The overall control device 60 includes a water level/output control device 70.
Turbine control device 80. It controls the bleed valve control device 90 and the control rod drive device 100, and exchanges signals with these control devices.

Supervisor i! The tl control device 60 has a load change request signal evaluation section 60A and a control device selection section 60B.

The overall control device 6o also inputs information regarding the plant status of the entire plant including the control device.

The load change request signal evaluation unit 60A uses the bleed valve control bag [90
The load change request signal ε and 0^D output from is analyzed and evaluated. That is, the load change request signal E LOAD is evaluated with respect to the change width ΔQ and the time change rate (or period 2 frequency acid).

The control device selection section 60B includes a control device selection section 60G and regulators 6oD to 60G. The control device selector 60G determines which signal should be sent to which control device with priority. For example, an output change component with a fluctuation range of several percent with a period of several seconds to several minutes is sent to the turbine control device 80, and a small output change component smaller than the above period is sent to the bleed valve control device 9.
0, output change components that are more than a few percent with a cycle of several minutes or more are sent to the water level/output control device i70, and compensation for very slow, drift-like output change components is sent to the control rod drive device control device 100. The necessary control information is output to each. Also regulators 60D to 60G.

Information is exchanged between them, and the control device selection unit 60
B is adjusted so that the whole is stable and there is no mutual interference. For example, non-interference control based on multivariable controller theory is implemented.

Other embodiments of the present invention will be described below.

First, in the first other embodiment, the temperature of the jet pump driving water and the temperature of the feed water sparger water are measured so that the temperatures of the jet pump driving water and the feed water sparger water are adjusted to the target values in order to prevent cavitation from occurring during the operation of the jet pump driven by the feed water. This is a method of controlling so that the The configuration in this case will be explained using FIG. 1.

The bleed steam supplied to the feed water heaters 25, 26 and 27 is
Bleed air control device i! The set jet pump driving water and water supply sparger water temperatures (TJ and T
s) by adjusting the bleed valves 37, 38 and 41 provided in the bleed pipes 36, 38 and 40, respectively. That is, the bleed valve control device 90 operates the bleed valves 37 and 39 to control the temperature of the water supply sparger water, and takes into account the opening degrees of the bleed valves 37 and 39 to control the temperature of the jet pump drive water. Therefore, it is necessary to adjust the opening degree of the bleed valve 41. Since the temperature of both water supplies (the water flowing through the water supply pipes 31 and 33) generally has a large delay time and dead time, one bleed valve control device i! is used in this embodiment. 90 is preferably program controlled.

Another embodiment of the invention is shown in FIG. The reactor plant of this embodiment has water supply piping 3 in the embodiment shown in FIG.
The water supply pumps 28 and 29, which function as water supply flow rate adjustment means in 1 and 33, are replaced with flow rate adjustment valves 61 and 62, and the water supply pump 63 is replaced with a valve between the high pressure water heater 26 and the branch point 34. It is installed in the water supply pipe 30. The other configuration 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 heater 27 and the branch point 34 . Also, the flow rate control valve 62
is provided in the water supply pipe 33. The opening degree of the flow control valve 61 is controlled by the jet pump driving water flow rate request signal WJD. The opening degree of the flow rate control valve 62 is controlled based on the water supply sparger water flow rate request signal Wsp.

This embodiment can achieve the same effects as the nuclear reactor plant shown in FIG. 1.

FIG. 18 shows another embodiment of the present invention. This embodiment has a baffle cylinder 12 added to the structure of the embodiment shown in FIG. Baffle tube 12 is arranged between riser portion 9 and water supply sparger 8 .

The baffle tube 12 is arranged concentrically with the riser portion 9, and its lower end extends to near the upper end of the jet pump 6. A large number of small holes are provided in the upper part of the baffle cylinder 12.

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

The nuclear reactor plant of this embodiment can obtain the same effects as the embodiment shown in FIG. This is lower than in the example.

A nuclear reactor plant according to another embodiment of the present invention shown in FIGS. 19 and 20 is shown. These figures show the structure around the jet pump in the reactor pressure vessel 1 of this embodiment. In this embodiment, jet pumps are arranged in two stages in series.

The other configurations are the same as the embodiment shown in FIG. Two jet pumps 6B and 6C are arranged in parallel.

Jet pump 6A is arranged above jet pumps 6B and 6C. A nozzle 32 is inserted into the upper end of the jet pump 6A. Two nozzles 64A and 64 are provided at the lower end of the jet pump 6A, that is, at the cooling water discharge side. These nozzles 64A and 64B are inserted into the upper ends of jet pumps 6B and 6C. When the M ratio of the jet pump 6A is M1, and the M ratio of the jet pumps 6B and 6C is M2, the M ratio of the entire two-stage jet pump is given by (M1+MzX(Mt+1)).

The lower end of the baffle cylinder 12 provided inside the water supply sparger 8 reaches near the upper ends of the diene 1 to the pump 6A. 12A is a small hole provided in the baffle cylinder 12.

The jet pump 6A mainly sucks low-temperature cooling water outside the baffle tube 12 using the jet pump drive water (supplied through the water supply pipe 31) spouted from the nozzle 32. The cooling water sucked into the jet pump 6A flows through the nozzle 64.
Jet pumps 6B and 6 are ejected from A and 64B.
This becomes the driving water for C. In this embodiment, the M ratio can be increased without causing cavitation within the jet pump. Moreover, the range in which cavitation can be prevented is wide.

A nuclear reactor plant according to another embodiment of the present invention will be described based on FIG. 21. Components that are the same as those in the embodiment shown in FIG. 1 are designated by the same reference numerals. This embodiment uses the feed water temperature control device 46 of the embodiment shown in FIG. The water level/output control device 5!70 and the bleed valve control device 90 are replaced by the feed water temperature control device r1149. Signal selector 47 in place of water level/output control device @75 and bleed valve control device 94
is removed. Furthermore, the temperature T of cooling water (saturated water)
A thermometer 59 for measuring s^ is installed inside the reactor pressure vessel 1 (for example, inside the riser section 9). Reactor pressure PR
A pressure gauge 62 for measuring the pressure is attached to the reactor pressure vessel 1. The measurement signals of the thermometer 59 and pressure gauge 62 are the water level and
It is input to the output control device i75.

The feed water temperature control device 49 will be explained with reference to FIG. 22. The feed water temperature control device 49 is a temperature estimator 46A.

Adders 46B, 49C, 49E and 49G, function generators 49A and 49B, target temperature difference setter 49D and PID
It has a controller 49F. Function generators 49A and 49
Each input terminal of B is connected to the output detector 56, and each output terminal is connected to the adder 49G. Adder 49C is connected to target temperature difference setter 49D. The input end of the adder 49E is connected to the target temperature difference setter 49D and the adder 46B.

An output end is connected to a PID controller 49E. PID controller 49F is connected to bleed valve 41 via adder 49G. The function generator 49A generates a temperature difference Δ between the reactor output QR and the temperature difference Δ.
Characteristic LUG showing the relationship with Tz (alarm generation line LU stored in the operating state determiner 76A shown in FIG. 24)
2) is memorized. The function generator 49B generates a characteristic LD! which shows the relationship between the reactor output QR and the temperature difference ΔTδ! (Alarm generation line LD that is stored in the operating state determiner 76A and has a lower level than the alarm generation line Lu2
2) is memorized. Operating state determiner 76
The area between the upper limit alarm generation line Lux and the lower limit alarm generation line Loz stored in A is the operation permissible area.

The function generator 49A outputs a temperature difference ΔTz corresponding to the input reactor output QR. The function generator 49B outputs a temperature difference ΔT3 corresponding to the input reactor output QR. The adder 49C outputs a temperature difference ΔT4 obtained by adding the temperature difference ΔT2 and the temperature difference ΔTa. The target temperature difference setter 49D calculates the target temperature difference ΔT* based on the input temperature difference ΔT4. In this embodiment, the target temperature difference Δτ is 0.5 times the temperature difference ΔT4, that is, the average value of the temperature difference ΔT2 and the temperature difference ΔT3. The adder 49E is.

Temperature difference ΔT obtained by adder 46B and target temperature difference Δ
Calculate the deviation from TI. 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 water supply sparger water by a predetermined temperature. Adder 49G outputs opening signal STa based on this control signal. The opening degree of the bleed valve 41 is adjusted based on the opening degree signal ST5.

In this embodiment, the feed water heater 27. Since the water supply pipes 31 and 33 are provided, the control mode of item (1) can be performed, which provides the same function as the embodiment shown in FIG. The feed water temperature control device 49 controls the difference between the temperature of the feed water flowing in the water supply pipe 31 and the temperature of the feed water flowing in the water supply pipe 33 to a predetermined temperature.

The water level/output control device 75 that implements the control mode in section (■) above will be described. FIG. 23 shows the configuration of the water level/output control device 75. Water level/output control device 75
is the water level controller 7 provided in the water level/output control device 7o.
1 and a furnace discharge master controller 72,
In addition to these, a plant state determiner 76 is provided. Water level controller 71 of water level/output control device 75. The furnace output master controller 72 and the plant status determiner 76 are (
When implementing the control mode in item (2), the water level controller 71 of the water level/output control device 70. It operates in the same manner as the operations performed by the furnace discharge master controller 72 and the plant state determiner 73.

The protection function performed by the plant state determiner 73 in the control mode (III) in the embodiment of FIG. 1 is provided by the plant state determiner 76 in this embodiment. A detailed configuration of the plant state determiner 76 is shown in FIG. Like the plant state determiner 70, the plant state determiner 76 includes flow rate request signal regulators 73A and 73B, and a limiter 7.
3C state determiner 73D, temperature estimator 73E and adder 7
It is equipped with 3G. In addition to the above configuration, the plant state determiner 76 includes an operating state determiner 76A, a heat** determiner 76
B and 76G and an OR circuit 76D. Thermal shock determiner 76B includes thermometers 54 and 59 and output detector 5.
6. The thermal shock determination device 76C is a thermometer 5
5 and 59 and the output detector 56. The operating state determiner 76A includes an adder 73G and an output detector 56.
connected to. Each output terminal of the operating state determiner 76A and the thermal shock determiners 76B and 76C is connected to a limiter 73C via an OR circuit 76D. Thermal shock determiner 76B
is the jet pump driving water temperature T, + measured by the thermometer 54 and the saturated water temperature Ts^ measured by the thermometer 59
Input and make a judgment using the following formula. Thermal shock determiner 76B
is TSA-TJ<ΔTJ(QR)-(1)
When formula (1) is satisfied, "0" is output, and when formula (1) is not satisfied, "1" is output. ΔTJ can prevent thermal shock and thermal fatigue caused by supplying jet pump driving water into the reactor pressure vessel 1. Indicates the maximum permissible change rate of the jet pump driving water temperature, and the reactor output Q
It is a function of R. The thermal shock determination device 76C inputs the feed water sparger water temperature Ts and the saturated water temperature Ts^ measured by the thermometer 55, and performs determination according to the following equation. The thermal shock determiner 76C returns "0" when formula (2) is satisfied.

TSA-Ts<ΔTS(QR)-(2
) Outputs "1" when not satisfied. ΔTs indicates the maximum permissible rate of change in the feed water sparger water temperature that can prevent the occurrence of thermal shock and thermal fatigue caused by supplying the feed water sparger water into the reactor pressure vessel 1, and the reactor output Q
It is a function of R.

The operating state determiner 76A stores characteristics of the alarm generation line Lux indicating the upper limit of the temperature difference ΔT and the alarm generation line LD2 indicating the lower limit of the temperature difference ΔT.

The temperature difference ΔT determined between these alarm generation lines LU2 and LD2 is a function of the reactor output QR. The alarm generation line Lυ2 corresponds to the alarm generation line L2 in FIG. The alarm generation line LD2 is set below the alarm generation line LU2, and is set to prevent cavitation within the jet pump 6. The line Lux shown in FIG. 24 is the line L! (
10). Line LDI is the jet pump 6 located below the alarm generation line Loz.
This indicates the limit temperature difference within which cavitation will not occur. Area above line Lυ1 and line L
The area below oz is a prohibited area for nuclear reactor operation.

The area between the alarm generation line Lux and the alarm generation line LO2 is the operation permissible area. The operating state determiner 76A is
Input the temperature difference ΔT output from the adder 73G, and check whether the temperature difference ΔT exists in the area between the alarm generation line Lu2 and the alarm generation line Lot, reflecting the reactor output QR at that time. Determine. The operating state determiner 76A is
If it is determined that rOJ "exists," it outputs "1" if it determines that rOJ "does not exist."

The OR circuit 76D inputs the outputs of the thermal shock determiners 76B and 76C and the operating state determiner 76A, and outputs "1" or "r".
The OJ determination result signal LM is output to the limiter 73G.

The protection function of the plant state determiner 76 described above is the first
The plant state determiner 76 of this embodiment is a function of the second protection unit shown in the control mode of item (III) of the embodiment in the figure.
The function of the first protection section in the embodiment of FIG. 1 is similar to that of the first protection section in the embodiment of FIG.
B. This can be achieved by the limiter 73C and the state determiner 73D.

The first protection part and the second protection part of the plant state determination device 76 produce the same effect as the effect obtained by the first protection part and the second protection part of the plant state determination device 73. Furthermore, since this embodiment includes the thermal shock determiners 76B and 76G, it is possible to prevent thermal shock and thermal fatigue caused by changes in the temperature of the water supply. Further, the operating state determiner 76A determines whether the temperature difference T is above or below the alarm generation line Lox, and uses a judgment result signal LM based on this judgment to activate the limiter 73G. Since the jet pump 6 is operated, cavitation can be prevented from occurring within the jet pump 6.

The control mode (IV) executed in the embodiment of FIG. 1 is executed by the bleed valve control device 94 of this embodiment. As shown in FIG. 25, the bleed valve control device 94 includes a bleed valve controller 90A, a jet pump drive water flow rate compensation controller 90G,
It includes adders 90D and 90E and a bleed air amount distributor 95. The components other than the bleed air amount distributor 95 are provided in the bleed valve control device 90. The bleed air amount distributor 95 has a bleed air valve controller 96 and a bleed valve opening degree corrector 97, as shown in FIG. The bleed valve controller 96 is
Adjusters 92A and 92B, correction amount distributors 96A and 96
B, and adders 96C and 96D. The adder 96C has input terminals connected to the adjuster 92A and the correction amount distributor 96.
A, the output end is connected to the bleed valve 37, respectively. The adder 96D has input terminals connected to the adjuster 92B and the correction amount distributor 9.
6B, the output ends are connected to the bleed valve 39, respectively. The bleed valve opening degree corrector 97 includes a feed water temperature target setter 97A that inputs the reactor output QR, an adder 97B that is connected to the feed water temperature target setter 97A and the thermometer 55.

It has a dead band device 97C connected to the adder 97B and a PrD controller 97D connected to the dead band device 97C to perform proportional and integral calculations. The output terminal of the PID controller 97D is
It is connected to correction amount distributors 96A and 96B.

The feed water temperature target setter 97A uses the input reactor output QR.
Control target value Ts of the supply water sparger water temperature Ts based on
Find *. The adder 97B calculates the feed water sparger water temperature T.
The deviation (TS-Ts'') between s and the control target value TS is calculated.The dead band device 97C is.

It has a dead zone of width δ on the + side and - side from 0, and the deviation (Ts
−Ts fist) becomes larger than δ, a positive signal is given,
When it becomes larger than -δ, a negative signal is output. Based on the output signal of the dead band device 97C, the PID controller 97D outputs a correction signal SA. The correction signal SA is
It is input to correction amount distributors 96A and 96B. Controller 9
2A and 93B output the opening degree signals STa and Sr1 based on the deviation signal v8 as described above. The correction amount allocator 96A calculates α·SA. α is the distribution coefficient and is 0
Takes a value of ≦α<1. The correction amount allocator 96B calculates (1-α
)・Perform SA calculation. The adder 96G is.

α output from the correction amount distributor 96A to the opening signal STa
・SA is added to obtain the opening signal STe, and this opening signal S
Ta is output to the bleed valve 37. The bleed valve 37 is adjusted to an opening corresponding to the opening signal STe. The adder 96D is
The correction amount distributor 96B outputs the opening signal ST3 (
1-α)・SA is added to obtain the opening signal ST? and this opening signal ST? is output to the bleed valve 37. The bleed valve 37 is
The opening degree is adjusted to correspond to the opening degree signal ST. The bleed valves 37 and 39 controlled in this way are controlled by the jet pump 6.
In order to prevent cavitation and to secure the core inlet enthalpy, a relatively slow fluctuation component included in the load change request signal c is combined with a small width and short period fluctuation component contained in the load change request signal εL. It will work on both.

This embodiment can also obtain the same effect as the control mode of item (IV) in FIG. 1.

In this embodiment, since the bleed valve opening corrector 97 is provided, the accuracy of the opening control of the bleed valves 37 and 39 is improved compared to the embodiment shown in FIG.

This embodiment also has a general control device 60 having the same functions as the embodiment shown in FIG. Therefore, the effects brought about by the overall control device 60 shown in FIG. 16 can be obtained even in this embodiment.

〔Effect of the invention〕

According to the first feature of the present invention, there is no need to provide in the reactor a means for lowering the temperature of the cooling water sucked into the jet pump, so the structure of the reactor can be simplified.

According to the second feature of the present invention, it is possible to prevent cavitation from occurring within the jet pump, thereby making it possible to significantly change the reactor output through core flow rate control.

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

According to the fourth feature, a portion of the feed water is supplied to the feed water sparger by bypassing the feed water heater necessary for the nuclear reactor plant, so it is possible to reduce the temperature of the feed water supplied to the feed water sparger with simple equipment. can.

According to the fifth feature, water level control is performed by controlling the feed water flow rate of the system that supplies water to the feed water sparger, which is one of the two systems that lead water into the reactor, making water level control easy. can.

According to the sixth feature, since the reactor output can be controlled by adjusting the flow rate of water supplied to the jet pump, the reactor output can be easily controlled.

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

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

According to the ninth feature, it is possible to improve the quick solubility of the turbine output in response to load fluctuations.

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

[Brief explanation of the drawing]

FIG. 1 is a configuration diagram of a BWR power generation plant that is a preferred embodiment of the present invention, FIG. The figure is a block diagram of the feed water temperature control device in figure 1, Figure 5 is a detailed block diagram of the water level/output control unit in figure 1, figure 6 is a detailed block diagram of the water level controller in figure 5, and figure 7 is a detailed block diagram of the water level controller in figure 5. The figure shows a detailed configuration diagram of the reactor output master controller shown in Figure 5, Figure 8 shows a detailed configuration diagram of the plant status determiner shown in Figure 5, and Figure 9 shows the relationship between jet pump drive water flow rate and reactor output. Figure 10 is a characteristic diagram showing the relationship between reactor output and temperature difference ΔT.
Figure 1 is a diagram of the operating characteristics of the Norimittar shown in Figure 8, Figure 12 is a detailed configuration diagram of the turbine control device and bleed valve control device in Figure 1, and Figure 13 is a detailed configuration diagram of the bleed valve controller in Figure 12. ,
Fig. 14 is a block diagram of the bleed air amount distributor in Fig. 12, Fig. 15 is a response characteristic diagram of <BWR power generation plan 1- based on the operation of the bleed valve control device in Fig. 12, and Fig. 16 is a diagram of the 17 to 19 are configuration diagrams of other embodiments of the present invention, and FIG. 20 is a Y-Y sectional view of FIG. 19.
Fig. 21 is a block diagram of a BWR power generation plant which is another embodiment of the present invention, Fig. 22 is a block diagram of the feed water temperature control device of Fig. 21, and Fig. 23 is a block diagram of the water level/output control device of Fig. 21. Fig. 24 is a block diagram of the plant state determiner shown in Fig. 23, Fig. 25 is a block diagram of the bleed valve control device shown in Fig. 21,
FIG. 26 is a block diagram of the bleed air amount distributor shown in FIG. 25. 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, 26.27... High pressure feed water heater, 28.29 ...
Water supply pump, 30.31.33... Water supply piping, 60.
... General control device, 70 ... Water level/output control device, 7
1... Water level controller, 72... Furnace output master controller, 73... Plant status determiner, 73A, 73
B...Flow rate request signal regulator, 73C...Limiter
173D...Status determiner, 73F...Operating state determiner, 80...Turbine controller, 80A...Pressure controller, 80B...Speed controller, 80G...Low value priority gate, 90...Bleed air valve controller, 90A...Bleed air valve controller, 90B...Bleed air amount distributor, 90C...Jet pump drive water flow rate compensation controller, 100...Control rod drive device control device . Fig. 2 Fig. 3 Fig. 60 Whistle 7 Fig. 1 Mouth Fig. 70 Fig. 11 Fig. 12 Fig. t-'t:, v Fig. 74 Fig. 15 Fig. 16 Brown 73 Fig. 31.3.3... Withered 7I <, Piping No. nrM No. 20m Fig. 21 1-Takayoshi, Haja Jl, 33-Kenyaga Piping No. 2
2 Kukatsu 230 (Enemy result Sumido Ki "" Xi 7 words reward K tj & aq) Part 24
fI No. 250 Procedural amendment (formality)

Claims (1)

[Scope of Claims] 1. A reactor vessel containing a reactor core, a jet pump disposed within the reactor vessel to supply coolant to the reactor core, and a water supply spargeer installed within the reactor vessel. ,
A nuclear reactor plant comprising a water supply means for guiding a part of the feed water to the jet pump as driving water and guiding the rest of the feed water to the water spargeer in a lower temperature state than the feed water for guiding the rest of the feed water to the jet pump. 2. The nuclear reactor plant according to claim 1, further comprising a control means for adjusting a temperature difference between the feed water introduced to the jet pump as driving water and the feed water introduced to the feed water spargeer. 3. A baffle cylinder disposed inside the water supply spargeer and extending toward the jet pump, and further suppressing mixing of the high temperature coolant discharged from the reactor core and the feed water discharged from the water supply spargeer. A nuclear reactor plant according to item 1. 4. a coolant flow path for guiding the coolant; a means for guiding the coolant in the coolant flow path as driving water to a jet pump in the reactor vessel; A nuclear reactor plant comprising means for guiding water to a feed water spargeer in the reactor vessel as feed water at a temperature lower than that of the coolant supplied to the jet pump. 5. a reactor vessel containing a reactor core; a jet pump disposed within the reactor vessel to supply coolant to the reactor core; and a water supply spargeer installed within the reactor vessel;
a first pipe line that leads a portion of the feed water to the jet pump as driving water; a second pipe line that leads the remainder of the feed water to the water supply spargeer; and a water supply provided in the first pipe line that leads to the jet pump. heating means for raising the temperature of the feed water higher than the temperature of the feed water introduced to the feed water spargeer. 6. The nuclear reactor plant according to claim 5, further comprising means for controlling the amount of heating by said heating means. 7. A reactor vessel containing a reactor core, a jet pump disposed within the reactor vessel to supply coolant to the reactor core, and a water supply spargeer installed within the reactor vessel;
a first pipe line that guides the water supply to the jet pump as driving water; a second pipe line that is connected to the first pipe line and guides the water supply to the water supply spargeer; a feed water heater that makes the temperature of the feed water led to the pump higher than the temperature of the feed water led to the feed water spargeer, the second pipe line being attached to the first pipe line upstream of the feed water heater. Nuclear reactor plant. 8. The nuclear reactor plant according to claim 7, further comprising another feed water heater connected to the joint between the first pipe line and the second pipe line and located upstream of the joint part. . 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 through the second pipe line. 10. The nuclear reactor plant according to claim 9, wherein said control means is means for controlling the amount of heating medium supplied to said feed water heater. 11. The nuclear reactor plant according to claim 7, further comprising means for guiding steam generated in the reactor vessel to the feed water heater as a heating medium. 12. A first pipe line that guides a portion of the feed water as driving water to a jet pump that is disposed in the reactor vessel and supplies coolant to the reactor core, and a second pipe line that guides the remainder of the feed water to the water supply spargeer. a heating means provided in the first pipe line to make the temperature of the feed water led to the jet pump higher than the temperature of the feed water led to the feed water spargeer; and a heating means for measuring the flow rate of steam discharged from the reactor vessel. 1 flow meter; and the first flow meter;
a second flow meter that measures the flow rate of the water supplied through the pipe;
a third flow meter that measures the flow rate of the feed water guided through the second pipe, a water level meter that measures the liquid level of the coolant in the reactor vessel, and the steam measured by the first flow meter. outputting a control signal for maintaining the water level in the reactor vessel at a predetermined level based on the flow rate, each water supply flow rate measured by the second and third flowmeters, and the water level measured by the water level meter; A nuclear reactor plant comprising: a water level control means for controlling the water level; and a flow rate adjusting means provided in the second pipe line and adjusting the flow rate of water supply in the second pipe line based on the control signal. 13. A first pipe line that guides a portion of the feed water as driving water to a jet pump that is disposed in the reactor vessel and supplies coolant to the reactor core, and a second pipe line that leads the remainder of the feed water to the water supply spargeer. a heating means provided in the first pipe line to make the temperature of the feed water led to the jet pump higher than the temperature of the feed water led to the feed water spargeer; and a nuclear reactor that outputs a control signal for adjusting reactor power. A nuclear reactor plant comprising: an output control means; and a flow rate adjustment means that is provided in the first pipe line and adjusts the flow rate of water supply in the first pipe line based on the control signal. 14. A first pipe line that guides a portion of the feed water as driving water to a jet pump that is disposed in the reactor vessel and supplies coolant to the reactor core, and a second pipe line that leads the remainder of the feed water to the water supply spargeer. a heating means provided in the first pipe line to make the temperature of the feed water led to the jet pump higher than the temperature of the feed water led to the feed water spargeer; and outputting a first control signal for adjusting reactor power. a reactor output control means; 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 a water level control means provided in the first conduit and based on the first control signal. a first flow rate adjusting means for adjusting the water supply flow rate in the first pipe line; and a first flow rate adjusting means provided in the second pipe line for adjusting the water supply flow rate in the second pipe line based on the second control signal. A nuclear reactor plant comprising: two flow rate adjusting means; and means for modifying at least one of the first and second control signals when a trip signal is input. 15. A first pipe line that guides a portion of the feed water as driving water to a jet pump that is disposed in the reactor vessel and supplies coolant to the reactor core, and a second pipe line that guides the remainder of the feed water to the water supply spargeer. a heating means provided in the first pipe line to make the temperature of the feed water led to the jet pump higher than the temperature of the feed water led to the feed water spargeer; and a nuclear reactor that outputs a control signal for adjusting reactor power. an output control means, a first thermometer provided in the first pipe line, a second thermometer provided in the second pipe line, an output detector provided in the reactor core, and the first thermometer provided in the first pipe line; Based on each feed water temperature measured by the second thermometer and the reactor power measured by the output detector, it is determined whether the operating state of the reactor has reached an allowable limit, and the operating state is and means for modifying the control signal so that the operating state does not exceed the allowable limit when the allowable limit is reached. 16. A reactor vessel containing a reactor core, a jet pump disposed in the reactor vessel to supply coolant to the reactor core, a water supply spargeer installed in the reactor vessel, and a jet pump for supplying water to the reactor vessel. a first pipe line leading to the water supply spargeer, a second pipe line connected to the first pipe line and guiding the water supply to the water supply spargeer, and a first feed water heater provided in a portion of the first pipe line; a second feed water heater provided in a portion of the first pipe downstream of the connection point; a turbine driven by steam; a bleed line provided with a flow control valve to guide the steam to the first feedwater heater; means for detecting the rotational speed of the turbine; and a means for detecting the rotational speed of the turbine. A nuclear reactor plant comprising means for extracting a change component having a predetermined period or less and a predetermined variation width or less from the output, and means for controlling the opening degree of the flow control valve based on the extracted change component. 17. Another flow control valve is provided to direct the steam to the second
another air extraction pipe line leading to the feed water heater, a first temperature detection means provided in the first pipe line, a second temperature detection means provided in the second pipe line, and the first temperature detection means Claim 16, further comprising means for controlling the opening degree of said other flow rate regulating valve based on the difference between the supply water temperature measured by said second temperature detection means and the supply water temperature measured by said second temperature detection means. nuclear reactor plant. 18. A heating means for heating a part of the feed water used as drive water for the jet pump in the reactor vessel, and a first temperature detection for measuring the temperature of the remaining feed water supplied to the feed water spargeer in the reactor vessel. a second temperature detection means for measuring the temperature of a portion of the water supply discharged from the heating means; and a supply water discharged from the heating means based on output signals of the first and second temperature detection means. and means for controlling the heating amount of the heating means so that the temperature of the remaining feed water is higher than the temperature of the remaining feed water. 19. Another heating means for heating a part of the feed water supplied to the heating means and the remaining feed water supplied to the feed water spargeer, and a heating means 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 feed water heating control device according to claim 18. 20. The water level is determined based on three elements: the measured water level in the reactor vessel, a first flow rate of feed water supplied into the reactor vessel, and a second flow rate of steam discharged from the reactor. Of the feed water, the flow rate of the feed water that is lower in temperature than the feed water that is led to the jet pump in the reactor vessel as drive water and that is led to the feed water spargeer in the reactor vessel is determined so that A nuclear reactor water level control device with means for controlling. 21. Among the feed water supplied into the reactor vessel, the feed water whose temperature is higher than the feed water supplied to the feed water spargeer in the reactor vessel and which is supplied to the jet pump in the reactor vessel. A nuclear reactor power control device comprising means for controlling a flow rate based on measured reactor power. 22. Reactor power control means for outputting a first control signal for adjusting the reactor power; water level control means for outputting a second control signal for maintaining the water level in the reactor vessel at a predetermined level; and means for modifying at least one of the first and second control signals when the signal is input. 23. Means for determining the fluctuation period and fluctuation width of the input load change request signal, and selecting from a plurality of control devices according to the fluctuation period and fluctuation width obtained from the control device to which the control information signal should be output. A general control device equipped with means to 24. A reactor vessel containing a reactor core, a coolant flow path for guiding the coolant, and means for guiding the coolant in the coolant flow path as water supply to a water supply spargeer installed in the reactor vessel; the coolant in the coolant flow path at a higher temperature than the coolant supplied as water supply to the water supply spargeer;
a driving water supply means for supplying driving water to a jet pump provided in the reactor vessel; and a main steam pipe connected to the reactor vessel by a main steam pipe having a first valve for controlling a steam flow rate. a turbine driven by steam guided by the turbine; a means connected to the main steam pipe and having a second valve for bypassing the steam supplied to the turbine; and a heating device provided in the coolant flow path. reactor power control means for outputting a first control signal for adjusting reactor power; and means provided in the drive water supply means for adjusting the flow rate of the drive water based on the first control signal. and a turbine control means for controlling the opening degrees of the first and second valves;
A heating amount control means for adjusting the heating amount of the heating means, a control rod insertion amount control means for adjusting the degree of insertion of the control rods inserted into the reactor core, and a control means for outputting a control information signal. integrated control means for selecting from among 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 period and fluctuation width of the load change request signal. nuclear reactor plant. 25. Determine whether the operating state of the reactor has reached the permissible limit based on the temperature of a portion of the feed water led to the jet pump as driving water, the temperature of the remaining feed water led to the feed water spargeer, and the reactor output. and means for modifying a control signal for adjusting reactor power when the operating condition reaches a permissible limit so that the operating condition does not exceed the permissible limit.