CN109441561B - Protection method of overtemperature protection system of pressurized water reactor of nuclear power unit - Google Patents
Protection method of overtemperature protection system of pressurized water reactor of nuclear power unit Download PDFInfo
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- CN109441561B CN109441561B CN201811545361.9A CN201811545361A CN109441561B CN 109441561 B CN109441561 B CN 109441561B CN 201811545361 A CN201811545361 A CN 201811545361A CN 109441561 B CN109441561 B CN 109441561B
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F01—MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
- F01D—NON-POSITIVE DISPLACEMENT MACHINES OR ENGINES, e.g. STEAM TURBINES
- F01D17/00—Regulating or controlling by varying flow
- F01D17/10—Final actuators
- F01D17/12—Final actuators arranged in stator parts
- F01D17/14—Final actuators arranged in stator parts varying effective cross-sectional area of nozzles or guide conduits
- F01D17/141—Final actuators arranged in stator parts varying effective cross-sectional area of nozzles or guide conduits by means of shiftable members or valves obturating part of the flow path
- F01D17/145—Final actuators arranged in stator parts varying effective cross-sectional area of nozzles or guide conduits by means of shiftable members or valves obturating part of the flow path by means of valves, e.g. for steam turbines
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F01—MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
- F01D—NON-POSITIVE DISPLACEMENT MACHINES OR ENGINES, e.g. STEAM TURBINES
- F01D21/00—Shutting-down of machines or engines, e.g. in emergency; Regulating, controlling, or safety means not otherwise provided for
- F01D21/003—Arrangements for testing or measuring
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F01—MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
- F01D—NON-POSITIVE DISPLACEMENT MACHINES OR ENGINES, e.g. STEAM TURBINES
- F01D21/00—Shutting-down of machines or engines, e.g. in emergency; Regulating, controlling, or safety means not otherwise provided for
- F01D21/14—Shutting-down of machines or engines, e.g. in emergency; Regulating, controlling, or safety means not otherwise provided for responsive to other specific conditions
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F01—MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
- F01D—NON-POSITIVE DISPLACEMENT MACHINES OR ENGINES, e.g. STEAM TURBINES
- F01D25/00—Component parts, details, or accessories, not provided for in, or of interest apart from, other groups
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F01—MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
- F01D—NON-POSITIVE DISPLACEMENT MACHINES OR ENGINES, e.g. STEAM TURBINES
- F01D25/00—Component parts, details, or accessories, not provided for in, or of interest apart from, other groups
- F01D25/08—Cooling; Heating; Heat-insulation
- F01D25/12—Cooling
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- General Engineering & Computer Science (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention relates to the technical field of nuclear power unit stability control, in particular to a nuclear power unit pressurized water reactor overtemperature protection system and a protection method thereof, wherein the system comprises a two-loop main steam pressure measuring device, an air exhaust valve, a demineralized water tank, a bypass valve, a bypass desuperheater, a condenser vacuum measuring device, a condenser water level meter, a demineralized water delivery pump, a demineralized water delivery regulating valve and a control device; the control device collects the measuring results of the two-loop main steam pressure measuring device, the condenser vacuum measuring device and the condenser water level gauge and controls the working states of the air exhaust valve, the bypass desuperheater, the demineralized water delivery pump and the demineralized water delivery regulating valve, the overtemperature protection of the reactor and the steam generator is realized, the two-loop working medium can be supplemented in real time and the condenser can be prevented from being damaged, wherein the bypass desuperheater can spray water to reduce the temperature of high-temperature steam before entering the condenser, and the high-temperature damage to the condenser can be prevented.
Description
Technical Field
The invention relates to the technical field of nuclear power unit stability control, in particular to a protection method of a pressurized water reactor over-temperature protection system of a nuclear power unit.
Background
The power grid breaks down or the nuclear power unit is operated abnormally, when the nuclear power unit cuts off protection actions or loads and the station service is operated, a turbine regulating valve is suddenly closed, when the nuclear power unit causes the steam inlet volume of the turbine to suddenly and suddenly change, working media flowing through a steam generator in the two loops correspondingly reduce, the steam generator cannot take away heat in a reactor, the reactor and the steam generator are over-temperature, equipment can be damaged when the reactor and the steam generator are serious, and nuclear leakage accidents occur.
The reactivity of a pressurized water reactor of a nuclear power unit is controlled by a control rod and the boron concentration is adjusted, the boron concentration is a slow process, the reactivity change caused by reactant poison and the characteristics of the control rod are considered, and the rapid action of the control rod is limited to a certain extent, so that the safety of the reactor of the nuclear power unit is threatened when the thermal power of a primary circuit and the electric power of a secondary circuit are not matched in energy and have large deviation.
Disclosure of Invention
In order to solve the problems, the invention provides a pressurized water reactor over-temperature protection system of a nuclear power unit and a protection method thereof, aiming at the working conditions of sudden trip, load shedding idling or service-related operation after load shedding of a steam turbine of the nuclear power unit, and the like, and considering the characteristics of a reactor control rod and the regulation of boron concentration which cannot be quickly regulated, and the specific technical scheme is as follows:
a nuclear power unit pressurized water reactor over-temperature protection system comprises a two-loop main steam pressure measuring device, an air exhaust valve, a demineralized water tank, a bypass valve, a bypass desuperheater, a condenser vacuum measuring device, a condenser water level meter, a demineralized water delivery pump, a demineralized water delivery regulating valve and a control device; the secondary loop main steam pressure measuring device is used for measuring secondary loop main steam pressure of the nuclear power unit, transmitting a measuring result to the control device and installing the measuring result on a secondary loop main steam main pipe; the pair of air exhaust valves is used for exhausting the steam in the main steam main pipe to the atmosphere; the desalting water tank is used for containing desalting water; the bypass valve is used for discharging steam in the main steam main pipe to the condenser and is arranged on a pipeline connecting the air exhaust valve and the condenser; the bypass desuperheater is used for spraying water to cool steam discharged into a main steam main pipe of the condenser; the secondary loop main steam main pipe is connected with a condenser through a pipeline; an air exhaust valve, a bypass valve and a bypass desuperheater are sequentially arranged on a pipeline connecting a main steam main pipe of the second loop and a condenser; the condenser vacuum measuring device is used for measuring the vacuum value of the condenser and transmitting the measuring result to the control device, and the condenser water level gauge is used for measuring the water level condition in the condenser and transmitting the measuring result to the control device and is arranged on the outer side surface of the condenser; the demineralized water conveying pump is used for conveying demineralized water in the demineralized water tank to the condenser; the demineralized water conveying regulating valve is used for opening or closing a pipeline between the demineralized water conveying pump and the condenser; the desalted water tank, the desalted water conveying pump, the desalted water conveying regulating valve and the condenser are sequentially connected through pipelines; the control device is used for acquiring the measurement results of the two-loop main steam pressure measuring device, the condenser vacuum measuring device and the condenser water level gauge and controlling the working states of the air exhaust valve, the bypass desuperheater, the demineralized water delivery pump and the demineralized water delivery regulating valve; the control device is respectively connected with the two-loop main steam pressure measuring device, the air exhaust valve, the bypass desuperheater, the condenser vacuum measuring device, the condenser water level gauge, the demineralized water delivery pump and the demineralized water delivery regulating valve.
Preferably, the secondary loop main steam pressure measuring device comprises a pressure sampling tube and a pressure transmitter, wherein the pressure sampling tube is used for transmitting a secondary loop main steam pressure signal of the nuclear power unit to the pressure transmitter; the pressure transmitter is used for converting a main steam pressure signal of a secondary loop of the nuclear power unit into a measurable direct current signal of minus 5 to plus 5V or plus 1 to plus 5V and transmitting the direct current signal to the control device; the pressure sampling tube is arranged on the two-loop main steam main pipe.
Preferably, the pressure transmitter is an EJA series pressure transmitter or a Rosemont series pressure transmitter.
Preferably, the condenser vacuum measuring device comprises a vacuum gauge.
Preferably, the condenser vacuum measuring device comprises a net cage probe, a sampling tube and a vacuum gauge, the net cage probe arranged in a steam chamber of the condenser is connected with the vacuum gauge outside the condenser through the sampling tube, the vacuum gauge adopts an EJA series absolute pressure transmitter, and the absolute pressure transmitter converts a condenser vacuum signal into a DC electric signal of-5 to +5V or 1 to +5V and then inputs the DC electric signal into the control device.
Preferably, the condenser water level gauge is connected with the condenser cavity through two sampling pipes, and a water level measuring electric signal is input into the control device.
A protection method of a pressurized water reactor over-temperature protection system of a nuclear power unit comprises the following steps:
s1: when the real-time test value of the two-loop main steam pressure measuring device exceeds 5 percent PNIn which P isNThe control device controls the bypass desuperheater to be opened to spray water for rated main steam pressure, and controls the bypass valve to be opened to reduce and stabilize the main steam pressure;
s2: when the real-time test value of the condenser vacuum measuring device is greater than P0In which P is0The control device controls the bypass valve to be closed when the pressure value is an absolute pressure value, so that the condenser is prevented from being damaged;
s3: when the bypass valve can not be opened due to unsatisfied conditions and when the real-time test value of the two-loop main steam pressure measuring device exceeds 5 percent PNWhen the main steam pressure is reduced, the control device controls the air exhaust valve to be opened, so that the main steam pressure is reduced and stabilized;
s4: when the real-time test value of the two-loop main steam pressure measuring device exceeds 10 percent PNWhen the main steam pressure is reduced and stabilized, the control device controls the opening of the air exhaust valve (2);
s5: when the water level of the condenser measured by the condenser water level meter is lower than a preset value, the control device controls the start of the demineralized water delivery pump and the demineralized water delivery regulating valve, and demineralized water is supplemented to the condenser through the matching of the demineralized water delivery pump and the demineralized water delivery regulating valve to be supplemented after the working medium of the second loop is lost; the real-time supplement flow of the desalted water is regulated by a desalted water conveying regulating valve; when the water level value of the condenser measured by the condenser water level meter reaches a normal value, the control device controls the demineralized water delivery pump to stop and closes the demineralized water delivery regulating valve.
The invention has the beneficial effects that:
1. when the steam inlet volume of the steam turbine is suddenly and sharply reduced due to the fault of the nuclear power unit, working media flowing through the steam generator in the two loops are correspondingly reduced, the steam generator cannot take away heat in the reactor, and the reactor and the steam generator are over-heated. The working medium flow of the two loops flowing through the steam generator can be improved by opening the bypass valve, the overtemperature of the reactor and the steam generator can be prevented, and the time is strived for power regulation and control of the reactor.
2. The bypass desuperheater has the function of spraying water to high-temperature steam before entering the condenser to reduce the temperature, and can prevent the high temperature from damaging the condenser.
3. When the bypass valve is in fault or cannot be opened after being locked, the working medium flow of the two loops flowing through the steam generator can be improved by opening the pair of air exhaust valves, and the overtemperature of the reactor and the steam generator is prevented.
4. When the secondary loop working medium is seriously lost and the condenser water level gauge is too low to alarm, the demineralized water in the demineralized water tank passes through the self-started demineralized water delivery pump and then is supplemented to the condenser through the demineralized water delivery regulating valve, so that the secondary loop working medium is supplemented in real time.
5. The invention can realize the overtemperature protection of the reactor and the steam generator, and can supplement the working medium of the two loops in real time and prevent the condenser from being damaged.
Drawings
FIG. 1 is a schematic structural diagram of an overtemperature protection system of a pressurized water reactor of a nuclear power unit.
Detailed Description
For a better understanding of the present invention, reference is made to the following detailed description taken in conjunction with the accompanying drawings in which:
the nuclear power unit comprises a primary circuit and a secondary circuit, wherein the primary circuit comprises a nuclear reactor, a voltage stabilizer, a steam generator and a coolant pump; the two loops comprise a high-pressure valve, a reheater, a high-pressure cylinder, a low-pressure cylinder, a generator, a condenser, a condensate pump, a low-pressure heater, a deaerator, a water feed pump and a high-pressure heater, and the connection relation between the first loop and the second loop is shown in fig. 1, which is the prior art and is not described herein again.
As shown in fig. 1, the overtemperature protection system for the pressurized water reactor of the nuclear power unit comprises a two-loop main steam pressure measuring device 1, an air exhaust valve 2, a demineralized water tank 3, a bypass valve 4, a bypass desuperheater 5, a condenser vacuum measuring device 6, a condenser water level gauge 7, a demineralized water delivery pump 8, a demineralized water delivery regulating valve 9 and a control device 10; the secondary loop main steam pressure measuring device 1 is used for measuring secondary loop main steam pressure of the nuclear power unit, transmitting a measuring result to the control device 10 and installing the measuring result on a secondary loop main steam main pipe; the air exhaust valve 2 is used for exhausting steam in the main steam main pipe to the atmosphere; the demineralized water tank 3 is used for containing demineralized water; the bypass valve 4 is used for discharging steam in the main steam main pipe to the condenser and is arranged on a pipeline connecting the air exhaust valve 2 and the condenser; the bypass desuperheater 5 is used for spraying water to cool steam discharged into a main steam main pipe of the condenser; the secondary loop main steam main pipe is connected with a condenser through a pipeline; an air exhaust valve 2, a bypass valve 4 and a bypass desuperheater 5 are sequentially arranged on a pipeline for connecting a main steam main pipe of the second loop with a condenser; the condenser vacuum measuring device 6 is used for measuring the vacuum value of the condenser and transmitting the measuring result to the control device 10, the condenser vacuum measuring device 6 comprises a net cage probe, a sampling tube and a vacuum gauge, the net cage probe arranged in a steam chamber of the condenser is connected with the vacuum gauge outside the condenser through the sampling tube, the vacuum gauge adopts an EJA series absolute pressure transmitter, and the absolute pressure transmitter converts the condenser vacuum signal into a DC signal of-5 to +5V or 1 to +5V and then inputs the DC signal into the control device 10; the condenser water level gauge is used for measuring the water level condition in the condenser and transmitting the measurement result to the control device 10, is arranged on the outer side surface of the condenser and is connected with a condenser chamber through two sampling pipes, and a water level measurement electric signal is input into the control device 10; the demineralized water conveying pump 8 is used for conveying the demineralized water in the demineralized water tank 3 to the condenser; the demineralized water conveying regulating valve 9 is used for opening or closing a pipeline between the demineralized water conveying pump 8 and the condenser; the demineralized water tank 3, the demineralized water delivery pump 8, the demineralized water delivery regulating valve 9 and the condenser are sequentially connected through pipelines; the control device 10 is used for acquiring the measurement results of the two-loop main steam pressure measuring device 1, the condenser vacuum measuring device 6 and the condenser water level gauge 7 and controlling the working states of the air exhaust valve 2, the bypass valve 4, the bypass desuperheater 5, the demineralized water delivery pump 8 and the demineralized water delivery regulating valve 9; the control device 10 is respectively connected with the two-loop main steam pressure measuring device 1, the air exhaust valve 2, the bypass valve 4, the bypass desuperheater 5, the condenser vacuum measuring device 6, the condenser water level gauge 7, the demineralized water delivery pump 8 and the demineralized water delivery regulating valve 9 through wires.
The secondary loop main steam pressure measuring device 1 comprises a pressure sampling tube and a pressure transmitter, wherein the pressure sampling tube is used for transmitting a secondary loop main steam pressure signal of the nuclear power unit to the pressure transmitter; the pressure transmitter is used for converting a main steam pressure signal of a secondary loop of the nuclear power unit into a measurable direct current signal of minus 5 to plus 5V or plus 1 to plus 5V and transmitting the direct current signal to the control device 10; the pressure sampling tube is installed on the two-loop main steam main pipe, and the pressure transmitter adopts EJA series pressure transmitter. The condenser vacuum measuring device 6 comprises a vacuum gauge. A plurality of the air exhaust valves 2 and the bypass valve 4 may be provided.
A protection method of a pressurized water reactor over-temperature protection system of a nuclear power unit comprises the following steps:
s1: when the real-time test value of the two-loop main steam pressure measuring device 1 exceeds 5 percent PNIn which P isNFor rated main steam pressure, the control device 10 controls the bypass desuperheater 5 to be opened to spray water, and controls the bypass valve 4 to be opened to reduce and stabilize the main steam pressure;
s2: when the real-time test value of the condenser vacuum measuring device 6 is larger than 19.7kPa, wherein 19.7kPa is an absolute pressure value, the control device controls the bypass valve 4 to be closed, so that the condenser is prevented from being damaged;
s3: when the bypass valve 4 can not be opened due to the unsatisfied condition and when the real-time test value of the two-loop main steam pressure measuring device 1 exceeds 5 percent PNWhen the main steam pressure is reduced and stabilized, the control device controls the air exhaust valve 2 to be opened;
s4: when the real-time test value of the two-loop main steam pressure measuring device 1 exceeds 10 percent PNWhen the main steam pressure is reduced and stabilized, the control device controls the air exhaust valve 2 to be opened;
s5: when the condenser water level meter 7 measures that the water level of the condenser is lower than a preset value, the control device 10 controls the demineralized water delivery pump 8 and the demineralized water delivery regulating valve 9 to be started, and demineralized water is supplemented to the condenser through the cooperation of the demineralized water delivery pump 8 and the demineralized water delivery regulating valve 9 and is used as supplement after the two-loop working medium is lost; the real-time supplement flow of the demineralized water is regulated by a demineralized water conveying regulating valve 9; when the water level value of the condenser measured by the condenser water level gauge 7 reaches a normal value, the control device 10 controls the demineralized water delivery pump 8 to stop and closes the demineralized water delivery regulating valve 9.
The present invention is not limited to the above-described embodiments, which are merely preferred embodiments of the present invention, and the present invention is not limited thereto, and any modification, equivalent replacement, and improvement made within the spirit and principle of the present invention should be included in the protection scope of the present invention.
Claims (6)
1. A protection method of a pressurized water reactor over-temperature protection system of a nuclear power unit is characterized by comprising the following steps: the overtemperature protection system comprises a two-loop main steam pressure measuring device (1), an air exhaust valve (2), a desalted water tank (3), a bypass valve (4), a bypass desuperheater (5), a condenser vacuum measuring device (6), a condenser water level meter (7), a desalted water conveying pump (8), a desalted water conveying regulating valve (9) and a control device (10);
the secondary circuit main steam pressure measuring device (1) is used for measuring the secondary circuit main steam pressure of the nuclear power unit, transmitting the measuring result to the control device (10) and installing the measuring result on a secondary circuit main steam main pipe;
the pair of air exhaust valves (2) is used for exhausting steam in the main steam main pipe to the atmosphere;
the demineralized water tank (3) is used for containing demineralized water;
the bypass valve (4) is used for discharging steam in the main steam main pipe to the condenser and is arranged on a pipeline for connecting the air exhaust valve (2) and the condenser;
the bypass desuperheater (5) is used for spraying water to cool steam discharged into a main steam main pipe of the condenser;
the secondary loop main steam main pipe is connected with a condenser through a pipeline; an air exhaust valve (2), a bypass valve (4) and a bypass desuperheater (5) are sequentially arranged on a pipeline connecting a main steam main pipe of the two loops and a condenser;
the condenser vacuum measuring device (6) is used for measuring the vacuum value of the condenser and transmitting the measuring result to the control device (10),
the condenser water level gauge (7) is used for measuring the water level condition in the condenser and transmitting the measurement result to the control device (10) and is arranged on the outer side surface of the condenser;
the demineralized water conveying pump (8) is used for conveying the demineralized water in the demineralized water tank (3) to the condenser;
the demineralized water conveying regulating valve (9) is used for opening or closing a pipeline between the demineralized water conveying pump (8) and the condenser; the desalted water tank (3), the desalted water conveying pump (8), the desalted water conveying regulating valve (9) and the condenser are sequentially connected through pipelines;
the control device (10) is used for acquiring the measurement results of the two-loop main steam pressure measuring device (1), the condenser vacuum measuring device (6) and the condenser water level meter (7) and controlling the working states of the air exhaust valve (2), the bypass valve (4), the bypass desuperheater (5), the demineralized water conveying pump (8) and the demineralized water conveying regulating valve (9);
the control device (10) is respectively connected with the two-loop main steam pressure measuring device (1), the air exhaust valve (2), the bypass valve (4), the bypass desuperheater (5), the condenser vacuum measuring device (6), the condenser water level meter (7), the demineralized water conveying pump (8) and the demineralized water conveying regulating valve (9);
the method comprises the following steps:
s1: when the real-time test value of the two-loop main steam pressure measuring device (1) exceeds 5 percent PNIn which P isNFor rated main steam pressure, the control device (10) controls the bypass desuperheater (5) to be opened for spraying water, and simultaneously controls the bypass valve (4) to be opened to reduce and stabilize the main steam pressure;
s2: when the real-time test value of the condenser vacuum measuring device (6) is more than P0In which P is0The control device controls the bypass valve (4) to be closed for an absolute pressure value, so that the condenser is prevented from being damaged;
s3: when the bypass valve (4) cannot be opened due to the condition not being met and when the real-time test value of the two-circuit main steam pressure measuring device (1)More than 5% PNWhen the main steam pressure is reduced and stabilized, the control device controls the opening of the air exhaust valve (2);
s4: when the real-time test value of the two-loop main steam pressure measuring device (1) exceeds 10 percent PNWhen the main steam pressure is reduced and stabilized, the control device controls the opening of the air exhaust valve (2);
s5: when the condenser water level meter (7) measures that the water level of the condenser is lower than a preset value, the control device (10) controls the demineralized water delivery pump (8) and the demineralized water delivery regulating valve (9) to be started, and demineralized water is supplemented to the condenser through the cooperation of the demineralized water delivery pump (8) and the demineralized water delivery regulating valve (9) and is used as supplement after the working medium of the two loops is lost; the real-time supplement flow of the desalted water is regulated by a desalted water conveying regulating valve (9); when the water level value of the condenser measured by the condenser water level gauge (7) reaches a normal value, the control device (10) controls the demineralized water delivery pump (8) to stop and closes the demineralized water delivery regulating valve (9).
2. The protection method of the overtemperature protection system of the pressurized water reactor of the nuclear power unit according to claim 1, characterized by comprising the following steps: the secondary loop main steam pressure measuring device (1) comprises a pressure sampling tube and a pressure transmitter, wherein the pressure sampling tube is used for transmitting a secondary loop main steam pressure signal of the nuclear power unit to the pressure transmitter; the pressure transmitter is used for converting a main steam pressure signal of a secondary loop of the nuclear power unit into a measurable direct current signal of minus 5 to plus 5V or plus 1 to plus 5V and transmitting the direct current signal to the control device (10); the pressure sampling tube is arranged on the two-loop main steam main pipe.
3. The protection method of the overtemperature protection system of the pressurized water reactor of the nuclear power unit according to claim 2, characterized by comprising the following steps: the pressure transmitter adopts EJA series pressure transmitter or Rosemont series pressure transmitter.
4. The protection method of the overtemperature protection system of the pressurized water reactor of the nuclear power unit according to claim 1, characterized by comprising the following steps: the condenser vacuum measuring device (6) comprises a vacuum meter.
5. The protection method of the overtemperature protection system of the pressurized water reactor of the nuclear power unit according to claim 1, characterized by comprising the following steps: the condenser vacuum measuring device (6) comprises a net cage probe, a sampling tube and a vacuum gauge, the net cage probe arranged in a steam chamber of the condenser is connected with the vacuum gauge outside the condenser through the sampling tube, the vacuum gauge adopts an EJA series absolute pressure transmitter, and the absolute pressure transmitter converts a condenser vacuum signal into a DC electric signal of-5 to +5V or 1 to +5V and then inputs the DC electric signal into the control device (10).
6. The protection method of the overtemperature protection system of the pressurized water reactor of the nuclear power unit according to claim 1, characterized by comprising the following steps: the condenser water level gauge (7) is connected with a condenser cavity through two sampling pipes, and a water level measuring electric signal is input into the control device (10).
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| JPS61118692A (en) * | 1984-11-13 | 1986-06-05 | ウエスチングハウス エレクトリック コ−ポレ−ション | Method of operating generation system of pressurized water type reactor |
| US4920751A (en) * | 1989-01-24 | 1990-05-01 | Pyropower Corporation | System and method for reheat steam temperature control in circulating fluidized bed boilers |
| JPH0343603A (en) * | 1989-07-11 | 1991-02-25 | Toshiba Corp | Turbine controlling device |
| CN105781630A (en) * | 2016-03-02 | 2016-07-20 | 王欣 | Bypass control system of electric power generation steam turbine |
| CN209369880U (en) * | 2018-12-17 | 2019-09-10 | 广西电网有限责任公司电力科学研究院 | A kind of nuclear power unit presurized water reactor overtemperature prote system |
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