GB2543591B - Adjustment and control method for atmospheric dump valves in nuclear power plants - Google Patents

Adjustment and control method for atmospheric dump valves in nuclear power plants Download PDF

Info

Publication number
GB2543591B
GB2543591B GB1604874.6A GB201604874A GB2543591B GB 2543591 B GB2543591 B GB 2543591B GB 201604874 A GB201604874 A GB 201604874A GB 2543591 B GB2543591 B GB 2543591B
Authority
GB
United Kingdom
Prior art keywords
dump valves
atmospheric dump
setpoint value
pressure
nuclear power
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Active
Application number
GB1604874.6A
Other versions
GB201604874D0 (en
GB2543591A (en
Inventor
Zhang Ruiping
Zhang Nan
Li Shanshan
Liu Li
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
China Nuclear Power Engineering Co Ltd
Original Assignee
China Nuclear Power Engineering Co Ltd
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by China Nuclear Power Engineering Co Ltd filed Critical China Nuclear Power Engineering Co Ltd
Publication of GB201604874D0 publication Critical patent/GB201604874D0/en
Publication of GB2543591A publication Critical patent/GB2543591A/en
Application granted granted Critical
Publication of GB2543591B publication Critical patent/GB2543591B/en
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C13/00—Pressure vessels; Containment vessels; Containment in general
    • G21C13/02—Details
    • G21C13/022—Ventilating arrangements
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22—STEAM GENERATION
    • F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B35/00—Control systems for steam boilers
    • F22B35/004—Control systems for steam generators of nuclear power plants
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G21C1/04—Thermal reactors ; Epithermal reactors
    • G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
    • G21C1/08—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor
    • G21C1/09—Pressure regulating arrangements, i.e. pressurisers
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/18—Emergency cooling arrangements; Removing shut-down heat
    • G21C15/182—Emergency cooling arrangements; Removing shut-down heat comprising powered means, e.g. pumps
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
    • G21C9/004—Pressure suppression
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D3/00—Control of nuclear power plant
    • G21D3/04—Safety arrangements
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Landscapes

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Chemical & Material Sciences (AREA)
  • Combustion & Propulsion (AREA)
  • Thermal Sciences (AREA)
  • Mechanical Engineering (AREA)
  • Business, Economics & Management (AREA)
  • Emergency Management (AREA)
  • Control Of Turbines (AREA)

Description

ADJUSTMENT AND CONTROL METHOD FOR ATMOSPHERIC DUMP
VALVES IN NUCLEAR POWER PLANTS
Field of the Invention
The present invention relates to an adjustment and control method for atmospheric dump valves in nuclear power plants.
Description of Related Art
The control of atmospheric dump valves in nuclear power plants has always been a very important safety-level control system because the power of reactors cannot be changed rapidly as in the case of the load of steam turbine generators. After the load of steam turbines is reduced significantly, the bypass system of steam turbine generators discharges main steam directly into the condenser or the atmosphere, providing an artificial means for reducing the reactor load thereby reducing the amplitude of temperature transient and pressure transient of the nuclear steam supply steam. Once the steam condenser discharge system becomes inoperable, the atmospheric dump valve will provide a controllable artificial load to ensure safety of the reactor.
To improve the safety and advance level of reactors, the third-generation nuclear power plants have incorporated the design concept that, in order to allow the medium head safety injection system to be put into operation as soon as possible in the event of emergencies, the secondary side of the steam generator is required to reduce temperature at certain rate thus reducing the pressure of this circuit as soon as possible, which is called “rapid cooling”. In addition, to minimize the risk of the reactors due to operator mis-operation following an accident, the control requirement that no intervention by the operators within 30 minutes after the accident occurs is put forward. All these additional requirements set for the atmospheric dump valve have created difficulty in implementing the major safety control.
Summary of the Invention
The present invention provides a control method for automatically calculating according to the cooling rate and the rate of saturated pressure and saturated temperature of the secondary loop and automatically adjusting and controlling an atmospheric dump valve in response to the safety design requirements of nuclear power plants.
The present invention is an adjustment and control method for atmospheric dump valves in nuclear power plants, comprising: setting a pressure setpoint value for the atmospheric dump valves of a steam turbine bypass system, adjusting an opening of the atmospheric dump valves by use of a difference between outlet pressure of a steam generator and the pressure setpoint value of the atmospheric dump valves of the steam turbine bypass system, wherein when the outlet pressure of the steam generator becomes higher than the pressure setpoint value of the atmospheric dump valves, the opening of the atmospheric dump valves is adjusted according to the difference and steam in a secondary system is discharged, thereby reducing pressure of the secondary system to achieve the pressure setpoint value of the atmospheric dump valves; wherein the pressure setpoint value of the atmospheric dump valves is set by using programs in a protection group cabinet, or is manually adjusted and set by operators via a computer information and control system of nuclear power plants, or is adjusted and set through an adjustment unit on a backup panel, wherein in case of a breaking accident of heat transfer tubes of the steam generator, once trigger signals are received, the opening of the atmospheric dump valves is adjusted such that the temperature of the primary system is adjusted at a cooling rate of 100°C/h through the pressure change in the secondary system, and a function calculation module performs relevant calculation and an adjustment unit automatically adjusts the pressure setpoint value of the atmospheric dump valves, gradually reducing the pressure setpoint value of the atmospheric dump valves from the setpoint value in normal operating condition to a target setpoint value; and when the elapsed time following the accident reaches 30 minutes, operators are allowed to manually adjust the pressure setpoint value or the opening of the atmospheric dump valves of the system.
Preferably when the nuclear power plants operate at power, the pressure setpoint value of the atmospheric dump valves is set to be 7.85MPa(a), (a) standing for an absolute pressure.
Preferably during the reactor start-up of nuclear power plants, the pressure setpoint value or the opening of the atmospheric dump valve is manually set by operators to discharge surplus steam in the secondary system.
Preferably during reactor shutdown of nuclear power plants and the condenser becomes unavailable, the opening of the atmospheric dump valves is adjusted and the temperature of a primary system is automatically adjusted at a cooling rate of 28°C/h or 56°C/h through the pressure change in the secondary system until a residual heat removal system is put into service.
Preferably the opening of the atmospheric dump valve is automatically adjusted based on the pressure setpoint value of the atmospheric dump valve set by operators, or is manually adjusted by operators totally.
The advantageous effects of the present invention are as follows:
By designing an automatic control solution disclosed herein, in case of a breaking accident of heat transfer tubes of the steam generator, the use of atmospheric dump valve enables rapid cooling to be triggered automatically by safety injection signals. In this way, no operator intervention is required in 30 minutes and the temperature at secondary side of the steam generator can be reduced at required rate so as to reduce the pressure and temperature of the reactor coolant loop as soon as possible. As automatic adjustment is performed in 30 minutes without artificial intervention, so that the safety risks to the reactor due to operator mis-operation following an accident can be greatly mitigated. With the automatic control solution disclosed herein, the atmospheric dump valve can be automatically adjusted at a cooling rate of 28°C/h or 56°C/h, or can be automatically adjusted at the cooling rate of the primary system input by operators. This is in contrast to the case with M310 nuclear power plants where operators have to manually adjust the pressure setpoint value of the atmospheric dump valves from time to time based on the detected temperature of the primary system so as to ensure the temperature reduction rate.
Brief Description of the Drawings
Fig. 1 is a schematic diagram of a control method for an atmospheric dump valve in accordance with the present invention; and
Fig.2 is a schematic diagram of a control method for an atmospheric dump valve in accordance an embodiment of the present invention.
In the figures, the designations shall have the corresponding meaning shown below. TSM: main steam system; IIC: computer information and control system of power plants; IRS: remote reactor shutdown station system; EES: power supply system of hydraulic test pump; IDA: test data acquisition system; BUP: backup panel; CS: signal output; EP: electrical converter; ID: indicating system; RCM: manual/automatic control station; RCS: remote control station; RPC: setpoint value station; KU: control devices for the equipment operated in the computer information and control system of nuclear power plants; RG: adjustment module, k (1+1/Tp) stands for a proportional integral adjustment unit, k is proportional gain and Tp is integral time.
Description of the Preferred Embodiment
Below is a detailed description of the present invention in connection with the accompanying drawings and the preferred embodiments.
As shown in Fig.l, an adjustment and control method of an atmospheric dump valve of nuclear power plants comprises setting a pressure setpoint value for the atmospheric dump valves of a steam turbine bypass system, adjusting an opening of the atmospheric dump valve by use of a difference between outlet pressure of a steam generator and the pressure setpoint value of the atmospheric dump valves of the steam turbine bypass system; when the outlet pressure of the steam generator becomes higher than the pressure setpoint value of the atmospheric dump valve, the opening of the atmospheric dump valves is adjusted according to the difference. The larger the difference, the larger the opening of the adjusted valve becomes. In this way, steam in a secondary system is discharged thereby reducing pressure of the secondary system to achieve the pressure setpoint value of the atmospheric dump valves. c
As shown in Fig.2, three atmospheric dump valves TSA131VV, 132VV and 133VV of the steam turbine bypass system (TSA) are respectively adjusted at the protection group cabinets IIP, HIP and IVP. This is achieved using a proportional integral control circuit and based on the difference between outlet pressure of the steam generator and the pressure setpoint value of the atmospheric dump valve. A fixed setpoint value is set by programs in the protection group cabinet, which is referred to as internal setpoint value. Alternatively, the operators of a computer information and control system (IIC) of nuclear power plants may manually adjust the pressure setpoint value (referred to as external setpoint value) or may elect to manually adjust the cooling rate temperature gradient. Moreover, when the IIC is unavailable, an adjustment unit (RC) on a backup panel (BUP) may be used to adjust the pressure setpoint value. A transfer switch on the IIC may be used to manually set the temperature gradient or pressure setpoint value and to transfer between the internal and external pressure setpoint value. When the IIC is unavailable, the RC on the BUP may be used instead. Alternatively, the opening of the valves may be set manually to adjust. This is achieved on the IIC or the remote reactor shutdown station (IRS) using the control device (KU) for the equipment operated in the computer information and control system of nuclear power plants, and is achieved on the BUP using the RC.
When nuclear power plants operate at power, the pressure setpoint value of the atmospheric dump valves is set by the program in the protection group cabinet. It is the internal setpoint value of 7.85MPa (a), wherein (a) stands for an absolute pressure, which corresponds to position 2 of the transfer switch as shown in Fig.2.
When the reactor is started up, the pressure setpoint value (corresponding to position 3 of the transfer switch as shown in Fig.2) or the opening of the valve is set by the operators.
During shutdown of the reactor of nuclear power plants, if the condenser is
A unavailable, the opening of the three atmospheric dump valves f SA131 VV, 132VV and 133VV of the TSA system are respectively adjusted and, in this way, the temperature of the primary system may be automatically adjusted at a cooling rate of 28°C/h or 56°C/h (set by the operators) through the pressure change of the secondary system. The automatic adjustment may be performed using function calculation module 2 as shown in Fig.2 (in this case, the transfer switch is switched to position 4). The function calculation module 2 automatically calculates the pressure setpoint value based on the pressure of the secondary system and the temperature of the primary system and then the adjustment unit functions so that the primary circuit is cooled down to the condition where the residual removal system is put into service. Alternatively, the opening of the atmospheric dump valve may be automatically adjusted (in this case, the transfer switch is switched to position 3) when selected by the operators depending upon the demands or is manually adjusted by the operators totally.
In case of breaking of heat transfer tubes of the steam generator, once safety injection signals are received, the rapid cooling is triggered and the transfer switch will automatically be switched to the pressure setpoint value in the condition of rapid cooling(in this case, the transfer switch is switched to position 1). The function calculation module 1 automatically calculates the setpoint value based on the cooling rate and the rate of saturated pressure and saturated temperature of the secondary loop and then the adjustment unit performs adjustment. During the adjustment, the temperature reduction rate of the primary system is maintained at a rate of 100°C/h temperature gradient and the pressure setpoint value is gradually adjusted from 7.85MPa (a) to 4.5MPa (a). The accident analysis shows that, when the pressure setpoint value drops to 4.5MPa(a), the rapid cooling rate can be reduced to 28°C/h. When the pressure of the secondary system drops to a certain value (4.5MPa(a)), a slow cooling rate may be employed until the residual heat 7 removal system is put into service. Alter tne elapsed time toiiowing an accident reaches 30 minutes, manual switching by operators is allowed.
The function relationship between the function calculation module 1 and the function calculation module 2 is expressed as:
Pressure setpoint value at the current point of time = temperature drop ratex time step x (DP/DT)sat + pressure setpoint value at the previous point of time (DP/DT)sat: The rate of saturated pressure and saturated temperature of the secondary loop
The function calculation module 1 is used for rapid cooling at a rate of 100°C/h when accidents occur. For the function calculation module 2, manual setting by operators is allowed and the temperature drop rate may be 28°C/h or 56°C/h.
The above disclosure is related to the detailed technical contents and inventive features thereof. People skilled in this field may proceed with a variety of modifications and replacements based on the disclosures and suggestions of the invention as described without departing from the characteristics thereof. Nevertheless, although such modifications and replacements are not fully disclosed in the above descriptions, they have substantially been covered in the following claims as appended. s

Claims (5)

Claims
1. An adjustment and control method for atmospheric dump valves in nuclear power plants, comprising: setting a pressure setpoint value for the atmospheric dump valves of a steam turbine bypass system, adjusting an opening of the atmospheric dump valves by use of a difference between outlet pressure of a steam generator and the pressure setpoint value of the atmospheric dump valves of the steam turbine bypass system, wherein when the outlet pressure of the steam generator becomes higher than the pressure setpoint value of the atmospheric dump valves, the opening of the atmospheric dump valves is adjusted according to the difference and steam in a secondary system is discharged, thereby reducing pressure of the secondary system to achieve the pressure setpoint value of the atmospheric dump valves; wherein the pressure setpoint value of the atmospheric dump valves is set by using programs in a protection group cabinet, or is manually adjusted and set by operators via a computer information and control system of nuclear power plants, or is adjusted and set through an adjustment unit on a backup panel, wherein in case of a breaking accident of heat transfer tubes of the steam generator, once trigger signals are received, the opening of the atmospheric dump valves is adjusted such that the temperature of the primary system is adjusted at a cooling rate of 100°C/h through the pressure change in the secondary system, and a function calculation module performs relevant calculation and an adjustment unit automatically adjusts the pressure setpoint value of the atmospheric dump valves, gradually reducing the pressure setpoint value of the atmospheric dump valves from the setpoint value in normal operating condition to a target setpoint value; and when the elapsed time following the accident reaches 30 minutes, operators are allowed to manually adjust the pressure setpoint value or the opening of the atmospheric dump valves of the system.
2. The adjustment and control method for the atmospheric dump valves in nuclear power plants as claimed in claim 1, wherein when the nuclear power plants operate at power, the pressure setpoint value of the atmospheric dump valves is set to be 7.85MPa(a), (a) standing for an absolute pressure.
3. The adjustment and control method for the atmospheric dump valves in nuclear power plants as claimed in claim 1, wherein during the reactor start-up of nuclear power plants, the pressure setpoint value or the opening of the atmospheric dump valves is manually set by operators to discharge surplus steam in the secondary system.
4. The adjustment and control method for the atmospheric dump valves in nuclear power plants as claimed in claim 1, wherein during the reactor shutdown of nuclear power plants and the condenser becomes unavailable, the opening of the atmospheric dump valves is adjusted and the temperature of a primary system is automatically adjusted at a cooling rate of 28°C/h or 56°C/h through the pressure change in the secondary system until a residual heat removal system is put into service.
5. The adjustment and control method for the atmospheric dump valves in nuclear power plants as claimed in claim 4, wherein the opening of the atmospheric dump valves is automatically adjusted based on the pressure setpoint value of the atmospheric dump valves set by operators, or is manually adjusted by operators totally.
GB1604874.6A 2015-10-22 2016-03-22 Adjustment and control method for atmospheric dump valves in nuclear power plants Active GB2543591B (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201510690026.8A CN105298556B (en) 2015-10-22 2015-10-22 Regulation control method for atmospheric emission valve of nuclear power station

Publications (3)

Publication Number Publication Date
GB201604874D0 GB201604874D0 (en) 2016-05-04
GB2543591A GB2543591A (en) 2017-04-26
GB2543591B true GB2543591B (en) 2019-06-05

Family

ID=55196279

Family Applications (1)

Application Number Title Priority Date Filing Date
GB1604874.6A Active GB2543591B (en) 2015-10-22 2016-03-22 Adjustment and control method for atmospheric dump valves in nuclear power plants

Country Status (2)

Country Link
CN (1) CN105298556B (en)
GB (1) GB2543591B (en)

Families Citing this family (9)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN106593555B (en) * 2016-12-13 2018-10-26 中国船舶重工集团公司第七一九研究所 A kind of multifunctional steam emission control systems and control method
CN107068214B (en) * 2017-05-09 2024-03-26 中广核研究院有限公司 Nuclear power plant steam atmosphere discharge device and two-loop pressure release method
CN107845436B (en) * 2017-09-27 2023-11-14 中国核电工程有限公司 Remote shutdown station control method for main control room of pressurized water reactor nuclear power plant when not being resident
CN109712733B (en) * 2018-12-05 2020-11-06 深圳中广核工程设计有限公司 Safety level function control system and method for steam atmospheric emission system of nuclear power station
CN112242205B (en) * 2019-07-16 2022-08-19 中核核电运行管理有限公司 Method for quickly cooling voltage stabilizer of nuclear power unit
CN110718313B (en) * 2019-09-18 2023-08-04 上海电力大学 Nuclear power station primary loop cooling control method under heat transfer pipe rupture accident
CN112466497B (en) * 2020-11-10 2024-04-09 中广核工程有限公司 Automatic control method, system, computer equipment and medium thereof for pressure and temperature
CN112530617A (en) * 2020-11-10 2021-03-19 中广核工程有限公司 Primary loop cooling method and device under power loss working condition of whole plant
CN114459013B (en) * 2022-01-27 2023-09-08 华能山东石岛湾核电有限公司 Protection system and method for high-temperature gas cooled reactor steam generator

Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4584164A (en) * 1982-06-03 1986-04-22 Combustion Engineering, Inc. Valve control for low temperature overpressure protection in a nuclear power plant
US20150194225A1 (en) * 2014-01-06 2015-07-09 Babcock & Wilcox Mpower, Inc. Passively initiated depressurization for light water reactor

Family Cites Families (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US194225A (en) * 1877-08-14 Improvement in band-saw mills
CN203858871U (en) * 2013-05-30 2014-10-01 中国核电工程有限公司 Control device of nuclear power plant air emission system
CN104299661B (en) * 2014-10-11 2017-05-03 中广核工程有限公司 Transient test control method and system used in debugging and starting process of nuclear power station

Patent Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4584164A (en) * 1982-06-03 1986-04-22 Combustion Engineering, Inc. Valve control for low temperature overpressure protection in a nuclear power plant
US20150194225A1 (en) * 2014-01-06 2015-07-09 Babcock & Wilcox Mpower, Inc. Passively initiated depressurization for light water reactor

Also Published As

Publication number Publication date
GB201604874D0 (en) 2016-05-04
CN105298556B (en) 2019-12-13
GB2543591A (en) 2017-04-26
CN105298556A (en) 2016-02-03

Similar Documents

Publication Publication Date Title
GB2543591B (en) Adjustment and control method for atmospheric dump valves in nuclear power plants
EP2661753B1 (en) System of controlling steam generator level during main feed-water control valve transfer for nuclear power plant
EP3667678B1 (en) Depressurisation valve
US4738818A (en) Feedwater control in a PWR following reactor trip
US8559584B2 (en) Nuclear reactor automatic depressurization system
KR20200073162A (en) Depressurisation valve
CN104332206A (en) Overpressure protection method for reactor startup/shutdown condition of PWR (pressurized water reactor) nuclear power plant
JPH08170998A (en) Reinforcement protective system against transient excessive output
EP3757355A1 (en) Control device for steam governing valve of power generation plant, and method for controlling steam governing valve of power generation plant
JPH0221558B2 (en)
CN113571211B (en) Nuclear power system and method and primary loop system thereof as well as reactor overpressure protection system and method
JP2544446B2 (en) Automatic cooling operation system from pressurized state to cold state of pressurized water nuclear power plant
US7912170B2 (en) Protection systems for nuclear boiling water reactors
GB2538567A (en) Method and system for controlling output of nuclear power plants
US20130152588A1 (en) Method and apparatus for controlling output of pressure setting signal to automatically control steam bypass control system, and method and apparatus for automatically controlling steam bypass control system by using the pressure setting signal
JPS6015912B2 (en) Reactor
CN100373741C (en) Protection system, construction method and use for beam source furnace power-off or misoperation
JPS6217121B2 (en)
CN111416385A (en) Control system and control method for debugging emergency diesel generator of nuclear power station
Tian et al. Design characteristics analysis of RTVO for a nuclear power plant
JPH05119189A (en) Nuclear reactor injection water flow automatic controller
Kai et al. Study of Application of Automatic Cooldown/Heatup Technology on CPR1000 Nuclear Power Plant
Wenhui et al. PSA Application in the Diverse Actuation System Design
JP5639808B2 (en) Reactor water supply controller
CN114251646A (en) Steam generator liquid level control method suitable for main pump start-stop working condition