CN109441561A - A kind of nuclear power unit presurized water reactor overtemperature prote system and its guard method - Google Patents
A kind of nuclear power unit presurized water reactor overtemperature prote system and its guard method Download PDFInfo
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- CN109441561A CN109441561A CN201811545361.9A CN201811545361A CN109441561A CN 109441561 A CN109441561 A CN 109441561A CN 201811545361 A CN201811545361 A CN 201811545361A CN 109441561 A CN109441561 A CN 109441561A
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- condenser
- water
- secondary circuit
- demineralized water
- valve
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Classifications
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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
-
- 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
-
- 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
Abstract
The present invention relates to nuclear power unit stability control techniques fields; more particularly to a kind of nuclear power unit presurized water reactor overtemperature prote system and its guard method, system includes secondary circuit main steam pressure force measuring device, to idle discharge steam valve, sweet-water tank, bypass valve, bypass attemperator, condenser vacuum measuring device, condenser water-level gauge, demineralized water delivery pump, demineralized water feed adjustment valve, control device；Control device acquires secondary circuit main steam pressure force measuring device, condenser vacuum measuring device, the measurement result of condenser water-level gauge and controls to idle discharge steam valve, bypass valve, the working condition for bypassing attemperator, demineralized water delivery pump, demineralized water feed adjustment valve; it realizes and overtemperature prote is carried out to reactor and steam generator; and secondary circuit working medium can be supplemented in real time and prevent condenser from damaging; wherein bypass attemperator can prevent damage of the high temperature to condenser into the high-temperature steam spray desuperheating before condenser.
Description
Technical field
The present invention relates to nuclear power unit stability control techniques fields, and in particular to a kind of nuclear power unit presurized water reactor overtemperature prote
System and its guard method.
Background technique
Grid collapses or operation nuclear power unit occur it is abnormal be inevitable, nuclear power unit cut machine protection act or
When removal of load house load operation, steam turbine pitch turns down suddenly, when core causes steam turbine throttle flow sharply to become smaller, secondary circuit stream
Working medium through steam generator will accordingly tail off, and steam generator can not take away the heat in reactor, will lead to reactor
With steam generator overtemperature, equipment damage will lead to when serious, nuclear leakage accident occurs.
Nuclear power unit presurized water reactor controls reactivity by control rod and adjusting boron concentration, and the adjusting of boron concentration is a slow mistake
Journey, it is contemplated that reactant poisonous substance causes reactive variation and control rod self character, the quick acting of control rod also to have one
Fixed limitation, thus nuclear power unit occur primary Ioops thermal power mismatched on energy with secondary circuit electrical power, occur it is substantially inclined
When poor, it will threaten to nuclear power unit nuclear reactor safety.
Summary of the invention
To solve the above-mentioned problems, the present invention for nuclear power unit there is steam turbine on-load during occur suddenly chaser,
After removal of load idle running or removal of load under the operating conditions such as house load operation, consideration reactor control rod cannot with adjusting boron concentration
The characteristic quickly adjusted provides a kind of nuclear power unit presurized water reactor overtemperature prote system and its guard method, specific technical solution
It is as follows:
A kind of nuclear power unit presurized water reactor overtemperature prote system, it is characterised in that: including secondary circuit main steam pressure force measuring device, right
Idle discharge steam valve, sweet-water tank, bypass valve, bypass attemperator, condenser vacuum measuring device, condenser water-level gauge, demineralized water are defeated
Send pump, demineralized water feed adjustment valve, control device；The secondary circuit main steam pressure force measuring device is for measuring nuclear power unit two
Circuit main steam pressure, and measurement result is delivered to control device, it is mounted on secondary circuit main steam pipe；It is described to idle discharge
Steam valve is used for the discharge of steam in main steam pipe into atmosphere；The sweet-water tank is for containing demineralized water；The bypass
Valve is used to for the discharge of steam in main steam pipe to condenser being mounted on the pipeline for connecting idle discharge steam valve with condenser；
The bypass attemperator is used to carry out spray cooling to the steam in the main steam pipe for being emitted into condenser；Secondary circuit main steam
Main pipe is connect with condenser by pipeline；It sets gradually on the pipeline that secondary circuit main steam pipe is connect with condenser to idle discharge
Steam valve, bypass valve, bypass attemperator；The condenser vacuum measuring device is used to measure the vacuum values of condenser and ties measurement
Fruit is delivered to control device, and the water level conditions of inside of the condenser water-level gauge for measuring condenser are simultaneously defeated by measurement result
It send to control device, is mounted on condenser lateral surface；The demineralized water delivery pump is used to convey the demineralized water in sweet-water tank
To condenser；The demineralized water feed adjustment valve is used to open or close the pipeline between demineralized water delivery pump and condenser；Institute
It states sweet-water tank, demineralized water delivery pump, demineralized water feed adjustment valve, condenser and passes sequentially through pipeline connection；The control device
For acquiring secondary circuit main steam pressure force measuring device, condenser vacuum measuring device, the measurement result of condenser water-level gauge simultaneously
Control the working condition to idle discharge steam valve, bypass valve, bypass attemperator, demineralized water delivery pump, demineralized water feed adjustment valve；It is described
Control device respectively with secondary circuit main steam pressure force measuring device, true to idle discharge steam valve, bypass valve, bypass attemperator, condenser
Empty measuring device, condenser water-level gauge, demineralized water delivery pump, the connection of demineralized water feed adjustment valve.
Preferably, the secondary circuit main steam pressure force measuring device includes pressure samples pipe, pressure transmitter, pressure samples
Pipe is for being transmitted to pressure transmitter for nuclear power unit secondary circuit main steam pressure force signal；The pressure transmitter is used for nuclear power
Unit secondary circuit main steam pressure force signal is converted into the DC signal of measurable -5 ~+5V or+1 ~+5V, and by direct current telecommunications
Number it is transmitted to control device；The pressure samples pipe is mounted on secondary circuit main steam pipe.
Preferably, the pressure transmitter uses EJA series of pressure transmitters or Rosemount series of pressure transmitters.
Preferably, the condenser vacuum measuring device includes vacuum meter.
Preferably, the condenser vacuum measuring device includes cylinder mould probe, probe tube and vacuum meter, is installed on condensing
The indoor cylinder mould probe of device vapour is connected by probe tube with the vacuum meter outside condenser room, and vacuum meter is using EJA series
Condenser vacuum signal is converted into -5 ~+5 V or 1 ~+5 V DC signals by absolute pressure transducer, absolute pressure transducer
Input control device afterwards.
Preferably, the condenser water-level gauge is connect by two probe tubes with condenser chamber, level measuring electric signal
Input control device.
A kind of guard method of nuclear power unit presurized water reactor overtemperature prote system the following steps are included:
S1: when the real-time testing value of secondary circuit main steam pressure force measuring device is more than 5%PNWhen, wherein PNFor specified main vapour pressure,
Control device control bypass attemperator unlatching is sprayed water, while being controlled bypass valve and being opened reduction main vapour pressure and make its stabilization；
S2: when the real-time testing value of condenser vacuum measuring device is greater than P0When, wherein P0For absolute pressure value, control device control
Bypass valve processed is closed, and prevents from damaging condenser；
S3: when real-time testing value of the bypass valve because being unsatisfactory for when condition is fail to open and working as secondary circuit main steam pressure force measuring device
More than 5%PNWhen, idle discharge steam valve is opened in control device control to be reduced main vapour pressure and makes its stabilization；
S4: when the real-time testing value of secondary circuit main steam pressure force measuring device is more than 10%PNWhen, control device is controlled to idle discharge vapour
Valve (2), which is opened, to be reduced main vapour pressure and makes its stabilization；
S5: when the water level of condenser water level meter measurement condenser is lower than preset value, control device control demineralized water delivery pump is removed
The starting of salt water feed adjustment valve supplements demineralized water to condenser by the cooperation of demineralized water delivery pump, demineralized water feed adjustment valve,
As the supplement after secondary circuit medium-loss；The demineralized water supplements flow by demineralized water feed adjustment valve regulation in real time；When solidifying
When the water level value of vapour device water-level gauge measurement condenser reaches normal value, control device control demineralized water delivery pump stops and closes to remove
Salt water feed adjustment valve.
The invention has the benefit that
1, when nuclear power unit failure causes steam turbine throttle flow sharply to become smaller, secondary circuit flows through the working medium of steam generator for phase
It should tail off, steam generator can not take away the heat in reactor, will lead to reactor and steam generator overtemperature.By opening
Opening bypass valve can be improved the working medium flow that secondary circuit flows through steam generator, can prevent reactor and steam generator overtemperature, right
The power regulation of reactor is raced against time with control.
2, bypass attemperator has into the high-temperature steam spray desuperheating function before condenser, high temperature can be prevented to condensing
The damage of device.
3, when bypass valve failure or locking are fail to open, idle discharge steam valve raising raising secondary circuit can be flowed through by opening
The working medium flow of steam generator prevents reactor and steam generator overtemperature.
4, secondary circuit medium-loss is serious, the too low alarm of condenser water-level gauge when, the demineralized water in sweet-water tank pass through from
The demineralized water delivery pump of starting, then demineralized water is supplemented to condenser through demineralized water feed adjustment valve, realize supplement secondary circuit in real time
Working medium.
5, the present invention can be realized reactor and steam generator overtemperature prote, and can carry out to secondary circuit working medium real-time
It supplements and prevents condenser from damaging.
Detailed description of the invention
Fig. 1 is a kind of structural schematic diagram of nuclear power unit presurized water reactor overtemperature prote system in the present invention.
Specific embodiment
In order to better understand the present invention, the present invention will be further explained below with reference to the attached drawings and specific examples:
Nuclear power unit includes primary Ioops and secondary circuit, and primary Ioops include nuclear reactor, voltage-stablizer, steam generator, coolant pump；
Secondary circuit includes high-pressure governing valve, reheater, high pressure cylinder, low pressure (LP) cylinder, generator, condenser, condensate pump, low-pressure heater, removes
The connection relationship of oxygen device, feed pump, high-pressure heater, primary Ioops and secondary circuit as shown in Figure 1, the part is the prior art,
This is repeated no more.
As shown in Figure 1, a kind of nuclear power unit presurized water reactor overtemperature prote system includes secondary circuit main steam pressure force measuring device
1, to idle discharge steam valve 2, sweet-water tank 3, bypass valve 4, bypass attemperator 5, condenser vacuum measuring device 6, condenser water-level gauge
7, demineralized water delivery pump 8, demineralized water feed adjustment valve 9, control device 10；Secondary circuit main steam pressure force measuring device 1 is for surveying
Nuclear power unit secondary circuit main steam pressure is measured, and measurement result is delivered to control device 10, it is female to be mounted on secondary circuit main steam
Guan Shang；Idle discharge steam valve 2 is used for the discharge of steam in main steam pipe into atmosphere；Sweet-water tank 3 is for containing demineralized water；
Bypass valve 4 is used to the discharge of steam in main steam pipe to condenser being mounted on the pipe for connecting idle discharge steam valve 2 with condenser
On road；Attemperator 5 is bypassed to be used to carry out spray cooling to the steam in the main steam pipe for being emitted into condenser；The main steaming of secondary circuit
Vapour main pipe is connect with condenser by pipeline；It sets gradually on the pipeline that secondary circuit main steam pipe is connect with condenser to sky
Exhaust steam valve 2, bypass valve 4, bypass attemperator 5；Condenser vacuum measuring device 6 is used to measure the vacuum values of condenser and will measurement
As a result it is delivered to control device 10, condenser vacuum measuring device 6 includes cylinder mould probe, probe tube and vacuum meter, is installed on
The indoor cylinder mould probe of condenser vapour is connected by probe tube with the vacuum meter outside condenser room, and vacuum meter uses EJA
Condenser vacuum signal is converted into -5 ~+5 V or 1 ~+5 V direct currents by serial absolute pressure transducer, absolute pressure transducer
Input control device 10 after signal；The water level conditions of inside of the condenser water-level gauge for measuring condenser are simultaneously defeated by measurement result
It send to control device 10, is mounted on condenser lateral surface, connect by two probe tubes with condenser chamber, level measuring telecommunications
Number input control device 10；Demineralized water delivery pump 8 is used to the demineralized water in sweet-water tank 3 being delivered to condenser；Demineralized water is defeated
Send regulating valve 9 for opening or closing the pipeline between demineralized water delivery pump 8 and condenser；Sweet-water tank 3, demineralized water delivery pump
8, demineralized water feed adjustment valve 9, condenser pass sequentially through pipeline connection；Control device 10 is for acquiring secondary circuit main steam pressure
Measuring device 1, condenser vacuum measuring device 6, the measurement result of condenser water-level gauge 7 are simultaneously controlled to idle discharge steam valve 2, bypass valve
4, the working condition of attemperator 5, demineralized water delivery pump 8, demineralized water feed adjustment valve 9 is bypassed；Control device 10 respectively with two times
Road main steam pressure force measuring device 1, to idle discharge steam valve 2, bypass valve 4, bypass attemperator 5, condenser vacuum measuring device 6, solidifying
Vapour device water-level gauge 7, demineralized water delivery pump 8, demineralized water feed adjustment valve 9 pass through wired connection.
Wherein, secondary circuit main steam pressure force measuring device 1 includes pressure samples pipe, pressure transmitter, and pressure samples are effective
In nuclear power unit secondary circuit main steam pressure force signal is transmitted to pressure transmitter；Pressure transmitter is for returning nuclear power unit two
Road main steam pressure force signal is converted into the DC signal of measurable -5 ~+5V or+1 ~+5V, and DC signal is transmitted to
Control device 10；Pressure samples pipe is mounted on secondary circuit main steam pipe, and pressure transmitter uses EJA Series Pressure pick-up
Device.Condenser vacuum measuring device 6 includes vacuum meter.It is settable multiple to idle discharge steam valve 2, bypass valve 4.
A kind of guard method of nuclear power unit presurized water reactor overtemperature prote system the following steps are included:
S1: when the real-time testing value of secondary circuit main steam pressure force measuring device 1 is more than 5%PNWhen, wherein PNFor specified main vapour pressure
Power, the control bypass unlatching of attemperator 5 of control device 10 is sprayed water, while being controlled bypass valve 4 and being opened reduction main vapour pressure and make
It is stablized；
S2: when the real-time testing value of condenser vacuum measuring device 6 is greater than 19.7kPa, wherein 19.7kPa is absolute pressure
Value, control device control bypass valve 4 and close, prevent from damaging condenser；
S3: when real-time testing of the bypass valve 4 because being unsatisfactory for when condition is fail to open and working as secondary circuit main steam pressure force measuring device 1
Value is more than 5%PNWhen, idle discharge steam valve 2 is opened in control device control to be reduced main vapour pressure and makes its stabilization；
S4: when the real-time testing value of secondary circuit main steam pressure force measuring device 1 is more than 10%PNWhen, control device is controlled to idle discharge
Steam valve 2, which is opened, to be reduced main vapour pressure and makes its stabilization；
S5: when the water level that condenser water-level gauge 7 measures condenser is lower than preset value, control device 10 controls demineralized water delivery pump
8, demineralized water feed adjustment valve 9 starts, and is supplemented by the cooperation of demineralized water delivery pump 8, demineralized water feed adjustment valve 9 to condenser
Demineralized water, as the supplement after secondary circuit medium-loss；Demineralized water supplements flow in real time and is adjusted by demineralized water feed adjustment valve 9；
When the water level value that condenser water-level gauge 7 measures condenser reaches normal value, control device 10, which controls demineralized water delivery pump 8, to be stopped
And close demineralized water feed adjustment valve 9.
The present invention is not limited to above-described specific embodiment, and the foregoing is merely preferable case study on implementation of the invention
, it is not intended to limit the invention, any modification done within the spirit and principles of the present invention and changes equivalent replacement
Into etc., it should all be included in the protection scope of the present invention.
Claims (7)
1. a kind of nuclear power unit presurized water reactor overtemperature prote system, it is characterised in that: including secondary circuit main steam pressure force measuring device
(1), to idle discharge steam valve (2), sweet-water tank (3), bypass valve (4), bypass attemperator (5), condenser vacuum measuring device (6),
Condenser water-level gauge (7), demineralized water delivery pump (8), demineralized water feed adjustment valve (9), control device (10)；
The secondary circuit main steam pressure force measuring device (1) will measure for measuring nuclear power unit secondary circuit main steam pressure
As a result control device (10) are delivered to, are mounted on secondary circuit main steam pipe；
It is described that idle discharge steam valve (2) are used for the discharge of steam in main steam pipe into atmosphere；
The sweet-water tank (3) is for containing demineralized water；
The bypass valve (4) is used to for the discharge of steam in main steam pipe to condenser being mounted on to idle discharge steam valve (2) and solidifying
On the pipeline of vapour device connection；
Bypass attemperator (5) is used to carry out spray cooling to the steam in the main steam pipe for being emitted into condenser；
Secondary circuit main steam pipe is connect with condenser by pipeline；In the pipeline that secondary circuit main steam pipe is connect with condenser
On set gradually to idle discharge steam valve (2), bypass valve (4), bypass attemperator (5)；
The condenser vacuum measuring device (6) is used to measure the vacuum values of condenser and measurement result is delivered to control device
(10),
The condenser water-level gauge (7) is used to measure the water level conditions of the inside of condenser and measurement result is delivered to control dress
(10) are set, condenser lateral surface is mounted on；
The demineralized water delivery pump (8) is used to the demineralized water in sweet-water tank (3) being delivered to condenser；
The demineralized water feed adjustment valve (9) is used to open or close the pipeline between demineralized water delivery pump (8) and condenser；Institute
It states sweet-water tank (3), demineralized water delivery pump (8), demineralized water feed adjustment valve (9), condenser and passes sequentially through pipeline connection；
The control device (10) is for acquiring secondary circuit main steam pressure force measuring device (1), condenser vacuum measuring device
(6), the measurement result of condenser water-level gauge (7) and control to idle discharge steam valve (2), bypass valve (4), bypass attemperator (5), desalination
The working condition of water delivery pump (8), demineralized water feed adjustment valve (9)；
The control device (10) is respectively with secondary circuit main steam pressure force measuring device (1), to idle discharge steam valve (2), bypass valve
(4), attemperator (5), condenser vacuum measuring device (6), condenser water-level gauge (7), demineralized water delivery pump (8), desalination are bypassed
Water feed adjustment valve (9) connection.
2. a kind of nuclear power unit presurized water reactor overtemperature prote system according to claim 1, it is characterised in that: the secondary circuit
Main steam pressure force measuring device (1) includes pressure samples pipe, pressure transmitter, and pressure samples pipe is used for nuclear power unit secondary circuit
Main steam pressure force signal is transmitted to pressure transmitter；The pressure transmitter is used to believe nuclear power unit secondary circuit main steam pressure
Number it is converted into the DC signal of measurable -5 ~+5V or+1 ~+5V, and DC signal is transmitted to control device (10)；
The pressure samples pipe is mounted on secondary circuit main steam pipe.
3. a kind of nuclear power unit presurized water reactor overtemperature prote system according to claim 2, it is characterised in that: the pressure becomes
Send device using EJA series of pressure transmitters or Rosemount series of pressure transmitters.
4. a kind of nuclear power unit presurized water reactor overtemperature prote system according to claim 1, it is characterised in that: the condenser
Vacuum measuring device (6) includes vacuum meter.
5. a kind of nuclear power unit presurized water reactor overtemperature prote system according to claim 1, it is characterised in that: the condenser
Vacuum measuring device (6) includes cylinder mould probe, probe tube and vacuum meter, is installed on the indoor cylinder mould probe of condenser vapour and passes through
Probe tube is connected with the vacuum meter outside condenser room, and vacuum meter uses EJA series absolute pressure transducer, absolute pressure
Condenser vacuum signal is converted into input control device (10) after -5 ~+5 V or 1 ~+5 V DC signals by transmitter.
6. a kind of nuclear power unit presurized water reactor overtemperature prote system according to claim 1, it is characterised in that: the condenser
Water-level gauge (7) is connect by two probe tubes with condenser chamber, level measuring electric signal input control device (10).
7. a kind of guard method of nuclear power unit presurized water reactor overtemperature prote system as described in claim 1-6 is any, feature
It is: the following steps are included:
S1: when the real-time testing value of secondary circuit main steam pressure force measuring device (1) is more than 5%PNWhen, wherein PNFor specified main vapour pressure
Power, control device (10) control bypass attemperator (5) are opened and are sprayed water, while being controlled bypass valve (4) and being opened the main vapour pressure of reduction
Power simultaneously makes its stabilization；
S2: when the real-time testing value of condenser vacuum measuring device (6) is greater than P0When, wherein P0For absolute pressure value, control device
It controls bypass valve (4) to close, prevents from damaging condenser；
S3: when bypass valve (4) is because being unsatisfactory for when condition is fail to open and working as the real-time of secondary circuit main steam pressure force measuring device (1)
Test value is more than 5%PNWhen, idle discharge steam valve (2) are opened in control device control to reduce main vapour pressure and makes its stabilization；
S4: when the real-time testing value of secondary circuit main steam pressure force measuring device (1) is more than 10%PNWhen, control device is controlled to idle discharge
Steam valve (2), which is opened, to be reduced main vapour pressure and makes its stabilization；
S5: when the water level of condenser water-level gauge (7) measurement condenser is lower than preset value, it is defeated that control device (10) controls demineralized water
Pump (8), demineralized water feed adjustment valve (9) starting are sent, the cooperation of demineralized water delivery pump (8), demineralized water feed adjustment valve (9) is passed through
Demineralized water is supplemented to condenser, as the supplement after secondary circuit medium-loss；The demineralized water supplements flow by demineralized water in real time
Feed adjustment valve (9) is adjusted；When the water level value of condenser water-level gauge (7) measurement condenser reaches normal value, control device
(10) control demineralized water delivery pump (8) stops and closes demineralized water feed adjustment valve (9).
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201811545361.9A CN109441561B (en) | 2018-12-17 | 2018-12-17 | Protection method of overtemperature protection system of pressurized water reactor of nuclear power unit |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201811545361.9A CN109441561B (en) | 2018-12-17 | 2018-12-17 | Protection method of overtemperature protection system of pressurized water reactor of nuclear power unit |
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| CN109441561A true CN109441561A (en) | 2019-03-08 |
| CN109441561B CN109441561B (en) | 2021-06-15 |
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| Application Number | Title | Priority Date | Filing Date |
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2022189611A1 (en) * | 2021-03-12 | 2022-09-15 | Framatome | Method and system for controlling a nuclear power plant |
Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN85108160A (en) * | 1984-11-13 | 1986-07-16 | 西屋电气公司 | The control presurized water reactor produces the method for overvoltage when preventing insufficient water |
| 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 |
-
2018
- 2018-12-17 CN CN201811545361.9A patent/CN109441561B/en active Active
Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN85108160A (en) * | 1984-11-13 | 1986-07-16 | 西屋电气公司 | The control presurized water reactor produces the method for overvoltage when preventing insufficient water |
| 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 |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2022189611A1 (en) * | 2021-03-12 | 2022-09-15 | Framatome | Method and system for controlling a nuclear power plant |
| FR3120734A1 (en) * | 2021-03-12 | 2022-09-16 | Framatome | Process and control system of a nuclear power plant |
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| Publication number | Publication date |
|---|---|
| CN109441561B (en) | 2021-06-15 |
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