CN113571211B - Nuclear power system and method and primary loop system thereof as well as reactor overpressure protection system and method - Google Patents
Nuclear power system and method and primary loop system thereof as well as reactor overpressure protection system and method Download PDFInfo
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- CN113571211B CN113571211B CN202110760238.4A CN202110760238A CN113571211B CN 113571211 B CN113571211 B CN 113571211B CN 202110760238 A CN202110760238 A CN 202110760238A CN 113571211 B CN113571211 B CN 113571211B
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- 238000000034 method Methods 0.000 title claims abstract description 29
- 239000003381 stabilizer Substances 0.000 claims abstract description 116
- 238000007599 discharging Methods 0.000 claims abstract description 7
- IJGRMHOSHXDMSA-UHFFFAOYSA-N Atomic nitrogen Chemical compound N#N IJGRMHOSHXDMSA-UHFFFAOYSA-N 0.000 claims description 31
- 238000002955 isolation Methods 0.000 claims description 26
- 239000002826 coolant Substances 0.000 claims description 24
- 229910052757 nitrogen Inorganic materials 0.000 claims description 16
- 238000004891 communication Methods 0.000 claims description 6
- 238000012544 monitoring process Methods 0.000 claims description 3
- 230000008569 process Effects 0.000 abstract description 18
- 239000002918 waste heat Substances 0.000 abstract description 7
- 238000012423 maintenance Methods 0.000 abstract description 3
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 6
- 238000013461 design Methods 0.000 description 4
- 238000005516 engineering process Methods 0.000 description 4
- 230000008859 change Effects 0.000 description 3
- 238000010521 absorption reaction Methods 0.000 description 1
- 238000009795 derivation Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000008034 disappearance Effects 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 230000000630 rising effect Effects 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
- 230000001960 triggered effect Effects 0.000 description 1
Classifications
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- 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
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- 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
-
- 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
- G21C9/012—Pressure suppression by thermal accumulation or by steam condensation, e.g. ice condensers
-
- 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
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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The invention provides a reactor overpressure protection system and method, a nuclear power system and a loop system thereof. The protection system comprises a voltage stabilizer, a control system and an automatic pressure relief structure, wherein the automatic pressure relief structure comprises an automatic pressure relief pipe arranged at the top of the voltage stabilizer and a pilot type safety valve arranged on the automatic pressure relief pipe, and the pilot type safety valve can be automatically opened and closed according to the steam pressure in the voltage stabilizer during the power operation of a power plant so as to realize the overpressure protection function under the power operation of the power plant. The control system can control the opening and closing of the pilot operated safety valve according to the pressure feedback of the instrument on the loop pipeline in the shutdown process so as to realize the low-pressure protection function in the shutdown process. Therefore, the low-temperature overpressure protection after intervention of the waste heat discharging system in the power plant power operation overpressure protection and shutdown process can be realized by only adopting the pilot-operated safety valve, so that the system has the advantages of centralized equipment, simplified structure, simplicity in maintenance and high safety performance.
Description
Technical Field
The invention particularly relates to a reactor overpressure protection system and method, a nuclear power system and a loop system thereof.
Background
In the design of the current nuclear power technology, overpressure protection of a reactor is an important working content in the direction of system and safety design. Wherein the overpressure protection in turn comprises two aspects:
during power plant power operation, overpressure protection of the reactor;
after the system for performing waste heat discharge in the shutdown process of the power plant is connected with the first loop of the reactor, the first loop of the reactor and the low-temperature overpressure protection of the connection system of the first loop of the reactor are realized.
In the power operation of a power plant, an overpressure event occurs, which is caused by the false start of a part of safety systems, so that a part of medium accidentally enters a first loop of the reactor, or is caused by the loss of a second loop, so that the heat of the first loop cannot be smoothly caused, and the first loop of the reactor is suddenly heated and boosted. Normally, the over-pressure protection valve in the case of loop power operation is implemented by a regulator relief valve, the opening setting value of which is set at 16.6mpa.
The design pressure of equipment and a pipe network of a loop is generally above 17.23MPa.a, but the plasticity of materials is greatly reduced compared with the normal operation temperature under the condition that the loop is at low temperature in the shutdown process of a power plant, and the bearing capacity is greatly reduced compared with the power operation of the power plant. Meanwhile, in the shutdown process, along with the disappearance of the steam cavity of the voltage stabilizer, a loop enters a water entity state, and at the moment, the false start of some safety systems can cause the excessively rapid introduction of quality or energy in loop equipment or a pipe network, so that a loop and a connecting system fail due to overpressure.
The arrangement of the low-temperature overpressure protection of the primary circuit is an essential component of the safety protection of the power plant, and a safety valve is generally arranged on the execution waste heat discharging system, and the setting value of the safety valve is set to be about 3.5MPa.
Above, it is known that overpressure protection in a nuclear power plant is necessary, and is also divided into different temperature phases.
In the traditional M310 nuclear power technology and most of the three-generation pressurized water reactor nuclear power technologies, the overvoltage protection of the power plant power operation stage is generally executed by a voltage stabilizer safety valve, and the low-temperature overvoltage protection is executed by a system executing a waste heat derivation function. The involvement of different systems, multiple devices, has resulted in increased investment in nuclear power plants and increased workload on operators.
Disclosure of Invention
The invention aims to solve the technical problems in the prior art, and provides an integrated reactor overpressure protection system which can realize overpressure protection under the condition of power operation and low temperature, simplify the system composition of a power plant and improve the economical efficiency of the power plant. Correspondingly, a method for performing overpressure protection on the reactor by using the system and a loop system with the overpressure protection system of the reactor and a nuclear power system with the loop system are also provided.
The technical scheme adopted for solving the technical problems of the invention is as follows:
the invention provides a reactor overpressure protection system, comprising: the automatic pressure relief structure comprises an automatic pressure relief pipe and a pilot type safety valve,
the automatic pressure relief pipe is arranged at the top of the pressure stabilizer and is used for discharging the coolant steam in the pressure stabilizer when the automatic pressure relief pipe is communicated with the pressure stabilizer,
the pilot type safety valve is arranged on the automatic pressure relief pipe and is used for automatically opening when the pressure in the pressure stabilizer is larger than a pilot type safety valve opening set value during power operation of the power plant, so that the pressure stabilizer is communicated with the automatic pressure relief pipe, coolant steam in the pressure stabilizer is discharged through the automatic pressure relief pipe, and when the pressure in the pressure stabilizer is smaller than a pilot type safety valve closing set value, the pilot type safety valve is automatically closed, so that the pressure stabilizer is disconnected with the automatic pressure relief pipe, and the pilot type safety valve opening set value is larger than the pilot type safety valve closing set value;
the control system is electrically connected with the pilot-operated safety valve and is used for controlling the pilot-operated safety valve to be opened when the pressure in the pressure stabilizer is larger than a cold state opening set value during shutdown, so that the pressure stabilizer is communicated with the automatic pressure relief pipe, coolant steam in the pressure stabilizer is discharged through the automatic pressure relief pipe, and the pilot-operated safety valve is controlled to be closed when the pressure in the pressure stabilizer is smaller than a cold state closing set value, and the cold state opening set value is larger than the cold state closing set value and smaller than the pilot-operated safety valve closing set value.
Optionally, the automatic pressure relief structure further comprises a pilot isolation valve, the pilot isolation valve is arranged on the automatic pressure relief pipe and is positioned behind the pilot safety valve along the steam flow direction, and is used for being opened when the pressure in the pressure stabilizer is in a normal range during the power operation of the power plant, and being automatically closed when the pilot safety valve is opened and the pressure in the pressure stabilizer is smaller than a closing set value of the pilot isolation valve,
the closing set value of the pilot isolation valve is smaller than the closing set value of the pilot safety valve and larger than the cold state opening set value.
Optionally, the voltage stabilizer is communicated with a loop pipeline of the reactor, and a meter for monitoring the pressure of the loop is arranged on the loop pipeline and is electrically connected with the control system and used for feeding back a loop pressure signal to the control system.
Optionally, the system further comprises a nitrogen source, wherein the nitrogen source is connected with the pressure stabilizer through a nitrogen filling pipe and is used for filling nitrogen into the pressure stabilizer to discharge coolant steam in the pressure stabilizer when the temperature of a loop is between 120 ℃ and 180 ℃ during shutdown.
Optionally, the automatic pressure release device further comprises an active pressure release structure, wherein the active pressure release structure comprises an active pressure release pipe and a first valve, the automatic pressure release pipe is arranged at the top of the pressure stabilizer, and the first valve is arranged on the automatic pressure release pipe.
Optionally, the active pressure release structure further comprises a second valve, the second valve is arranged on the automatic pressure release pipe, the first valve is connected with the control system and used for feeding back an opened signal of the first valve to the control system, and the second valve is also connected with the control system and used for feeding back an opened signal of the second valve to the control system.
Optionally, the automatic pressure relief structure is provided with a plurality of pressure relief structures,
the active pressure relief structure is provided with a plurality of active pressure relief pipes, and the active pressure relief pipes of the plurality of active pressure relief structures are connected with the voltage stabilizer through an active pressure relief master pipe.
The invention also provides a method for protecting the overpressure of the reactor by using the system, which comprises the following steps:
during power plant power operation, when the pressure in the pressure stabilizer is larger than a pilot-operated safety valve opening set value, the pilot-operated safety valve is automatically opened, so that the pressure stabilizer is communicated with an automatic pressure relief pipe, coolant steam in the pressure stabilizer is discharged through the automatic pressure relief pipe, and when the pressure in the pressure stabilizer is smaller than a pilot-operated safety valve closing set value, the pilot-operated safety valve is automatically closed;
during shutdown, when the pressure in the pressure stabilizer is greater than a cold state opening set value, the control system controls the pilot type safety valve to be opened so that the pressure stabilizer is communicated with the automatic pressure relief pipe, coolant steam in the pressure stabilizer is discharged through the automatic pressure relief pipe, and when the pressure in the pressure stabilizer is smaller than a cold state closing set value, the control system controls the pilot type safety valve to be closed.
The invention also provides a nuclear power primary loop system which comprises a loop pipeline and the reactor overpressure protection system, wherein the voltage stabilizer is communicated with the loop pipeline.
The invention also provides a nuclear power system, which comprises the reactor pressure vessel and the nuclear power primary loop system, wherein the reactor pressure vessel is communicated with a loop pipeline of the nuclear power primary loop system.
According to the invention, the control system is arranged, so that the opening and closing of the safety valve on the voltage stabilizer can be controlled according to the pressure feedback of the instrument on the primary loop pipeline in the shutdown process, and the low-pressure protection function in the shutdown process is realized; and the safety valve on the voltage stabilizer can be automatically opened and closed according to the steam pressure in the voltage stabilizer during the power running of the power plant, so that the overpressure protection function under the power running of the power plant is realized, and the overpressure protection of the power plant and the low-temperature overpressure protection after the intervention of the waste heat discharge system in the shutdown process can be realized by adopting the pilot-operated safety valve. Therefore, the system has the advantages of centralized equipment, simplified structure, simple maintenance and high safety performance.
Drawings
Fig. 1 is a schematic structural diagram of a reactor overpressure protection system provided in embodiment 1 of the present invention.
In the figure: 001-a voltage stabilizer; 100-a first automatic pressure relief tube; 101-a first pilot operated safety valve protection valve; 102-a first pilot operated safety valve isolation valve; 200-a second automatic pressure relief pipe; 201-a second pilot-operated safety valve protection valve; 202-a second pilot operated safety valve isolation valve; 300-a third automatic pressure relief tube; 301-a third pilot operated relief valve protection valve; 302-a third pilot operated safety valve isolation valve; 400-an active pressure relief pipeline main pipe; 401-a first active pressure relief tube; 402-a second active pressure relief tube; 403-a first electrically operated isolation valve; 404-a second electrically operated isolation valve; 405-a first electrically powered angle valve; 406-a second electrically operated angle valve; 501-control lines; 502-a power plant control system; 601-nitrogen filling pipe.
Detailed Description
The following description of the embodiments of the present invention will be made more apparent, and the embodiments described in detail, but not necessarily all, in connection with the accompanying drawings. All other embodiments, which can be made by those skilled in the art based on the embodiments of the invention without making any inventive effort, are intended to fall within the scope of the invention.
In the description of the present invention, it should be noted that the orientation or positional relationship indicated by "upper" or the like is based on the orientation or positional relationship shown in the drawings, and is merely for convenience and simplicity of description, and is not meant to indicate or imply that the apparatus or element to be referred to must be provided with a specific orientation, be configured and operated in a specific orientation, and thus should not be construed as limiting the present invention.
In the description of the present invention, the terms "first," "second," and "second" are used for descriptive purposes only and are not to be construed as indicating or implying relative importance.
In the description of the present invention, it should be noted that, unless explicitly specified and limited otherwise, the terms "connected," "configured," "mounted," "secured," and the like are to be construed broadly and may be either fixedly connected or detachably connected, or integrally connected, for example; can be directly connected or indirectly connected through an intermediate medium, and can be communication between two elements. The specific meaning of the above terms in the present invention will be understood by those skilled in the art in specific cases.
The invention provides a reactor overpressure protection system, comprising: the automatic pressure relief structure comprises an automatic pressure relief pipe and a pilot type safety valve,
the automatic pressure relief pipe is arranged at the top of the pressure stabilizer and is used for discharging the coolant steam in the pressure stabilizer when the automatic pressure relief pipe is communicated with the pressure stabilizer,
the pilot type safety valve is arranged on the automatic pressure relief pipe and is used for automatically opening when the pressure in the pressure stabilizer is larger than a pilot type safety valve opening set value during power operation of the power plant, so that the pressure stabilizer is communicated with the automatic pressure relief pipe, coolant steam in the pressure stabilizer is discharged through the automatic pressure relief pipe, and when the pressure in the pressure stabilizer is smaller than a pilot type safety valve closing set value, the pilot type safety valve is automatically closed, so that the pressure stabilizer is disconnected with the automatic pressure relief pipe, and the pilot type safety valve opening set value is larger than the pilot type safety valve closing set value;
the control system is electrically connected with the pilot-operated safety valve and is used for controlling the pilot-operated safety valve to be opened when the pressure in the pressure stabilizer is larger than a cold state opening set value during shutdown, so that the pressure stabilizer is communicated with the automatic pressure relief pipe, coolant steam in the pressure stabilizer is discharged through the automatic pressure relief pipe, and the pilot-operated safety valve is controlled to be closed when the pressure in the pressure stabilizer is smaller than a cold state closing set value, and the cold state opening set value is larger than the cold state closing set value and smaller than the pilot-operated safety valve closing set value.
The invention also provides a method for protecting the overpressure of the reactor by using the system, which comprises the following steps:
during power plant power operation, when the pressure in the pressure stabilizer is larger than a pilot-operated safety valve opening set value, the pilot-operated safety valve is automatically opened, so that the pressure stabilizer is communicated with an automatic pressure relief pipe, coolant steam in the pressure stabilizer is discharged through the automatic pressure relief pipe, and when the pressure in the pressure stabilizer is smaller than a pilot-operated safety valve closing set value, the pilot-operated safety valve is automatically closed;
during shutdown, when the pressure in the pressure stabilizer is greater than a cold state opening set value, the control system controls the pilot type safety valve to be opened so that the pressure stabilizer is communicated with the automatic pressure relief pipe, coolant steam in the pressure stabilizer is discharged through the automatic pressure relief pipe, and when the pressure in the pressure stabilizer is smaller than a cold state closing set value, the control system controls the pilot type safety valve to be closed.
The invention also provides a nuclear power primary loop system which comprises a loop pipeline and the reactor overpressure protection system, wherein the voltage stabilizer is communicated with the loop pipeline.
The invention also provides a nuclear power system, which comprises the reactor pressure vessel and the nuclear power primary loop system, wherein the reactor pressure vessel is communicated with a loop pipeline of the nuclear power primary loop system.
Example 1:
as shown in fig. 1, the present embodiment provides a reactor overpressure protection system, including: voltage regulator 001, control system 502, and automatic pressure relief structure.
The automatic pressure relief structure comprises an automatic pressure relief pipe and a pilot type safety valve,
an automatic pressure relief pipe is arranged at the top of the pressure stabilizer 001 and is used for discharging the coolant vapor in the pressure stabilizer 001 when the automatic pressure relief pipe is communicated with the pressure stabilizer 001,
the pilot type safety valve is arranged on the automatic pressure relief pipe and is used for automatically opening when the pressure in the pressure stabilizer 001 is larger than a pilot type safety valve opening set value during power operation of the power plant, so that the pressure stabilizer 001 is communicated with the automatic pressure relief pipe, coolant steam in the pressure stabilizer 001 is discharged through the automatic pressure relief pipe, and when the pressure in the pressure stabilizer 001 is smaller than a pilot type safety valve closing set value, the pilot type safety valve is automatically closed, so that the pressure stabilizer 001 is disconnected from the automatic pressure relief pipe, and the pilot type safety valve opening set value is larger than the pilot type safety valve closing set value;
the control system 502 is electrically connected with the pilot-operated safety valve through a control line 501, and is used for controlling the pilot-operated safety valve to be opened when the pressure in the pressure stabilizer 001 is greater than a cold state opening set value during shutdown, so that the pressure stabilizer 001 is communicated with an automatic pressure relief pipe, coolant steam in the pressure stabilizer 001 is discharged through the automatic pressure relief pipe, and the pilot-operated safety valve is controlled to be closed when the pressure in the pressure stabilizer 001 is smaller than a cold state closing set value, and the cold state opening set value is greater than the cold state closing set value and smaller than the pilot-operated safety valve closing set value.
Therefore, by arranging the control system 502, the opening and closing of the safety valve on the voltage stabilizer 001 can be controlled according to the pressure feedback of the instrument on the primary pipeline in the shutdown process, so as to realize the low-pressure protection function in the shutdown process; and the safety valve on the voltage stabilizer 001 can be automatically opened and closed according to the steam pressure in the voltage stabilizer 001 during the power operation of the power plant, so that the overpressure protection function under the power operation of the power plant is realized, and the overpressure protection of the power plant and the low-temperature overpressure protection after the intervention of the waste heat discharge system in the shutdown process can be realized by adopting the pilot-operated safety valve. Therefore, the system has the advantages of centralized equipment, simplified structure, simple maintenance and high safety performance.
Wherein the stabilizer 001 is connected to the primary loop pipeline of the reactor, and the immersed heater at the bottom of the stabilizer makes the water in the stabilizer at saturation temperature during the power running period of the power plant, and forms a steam cavity above the space for controlling the pressure and absorption volume change of the primary loop. A circuit line is provided with a meter for monitoring a circuit pressure, the meter being electrically connected to the control system 502 for feeding back a circuit pressure signal to the control system 502.
In this embodiment, the automatic pressure relief structure further includes a pilot-operated isolation valve disposed on the automatic pressure relief pipe and located at the rear of the pilot-operated safety valve in the steam flow direction, for being opened when the pressure in the pressure regulator 001 is within a normal range during power operation of the power plant, and being automatically closed when the pilot-operated safety valve is opened and the pressure in the pressure regulator 001 is less than a set value for closing the pilot-operated isolation valve,
the closing set value of the pilot isolating valve is smaller than the closing set value of the pilot safety valve and larger than the cold state opening set value.
During power operation of the power plant, the operating pressure of a loop is 15.5MPa.a, the pilot-operated safety valve is closed, and the pilot-operated isolation valve is in an open state, so that the increase of failure risk caused by opening two valves when the overpressure protection requirement begins is avoided.
In this embodiment, the pressure of a loop in normal operation: 15.5MPa.a, design pressure: 17.23mpa.a;
pilot-operated relief valve protection valve opening set point (thermal state): 16.6mpa.a, closing the set point (hot): 16.0MPa;
cold state opening set value of pilot type safety valve protection valve: 3.5MPa.a, cold shut-off setpoint: 3.2MPa;
pilot-operated relief valve isolation valve opening set point (thermal state): 14.6mpa.a, closing the set point (hot): 13.9Mpa.
In order to improve the reliability of automatic pressure relief, in this embodiment, three automatic pressure relief structures are provided, as shown in fig. 1, a first pilot-operated safety valve protection valve 101 and a first pilot-operated safety valve isolation valve 102 are installed on a first automatic pressure relief pipe 100; a second pilot-operated relief valve protection valve 201 and a second pilot-operated relief valve isolation valve 202 are installed on the second automatic relief pipe 200; a third pilot operated relief valve protection valve 301 and a third pilot operated relief valve isolation valve 302 are mounted on the third automatic relief pipe 300.
In this embodiment, during the power running of the power plant, when a false start of the related safety system occurs or the two circuits are suddenly lost, the pressure of the first circuit is increased until the opening constant value (the opening set value of the pilot-operated safety valve) of the pilot-operated safety valve reaches 16.6mpa.a, the pilot-operated safety valve protection valves 101, 201, 301 are tripped, and the pressure of the first circuit is relieved to prevent the breakage of the first circuit caused by the further increase of the pressure. When the primary circuit pressure falls back to 16.0mpa.a (pilot operated relief valve closing set point), the pilot operated valve protection valve automatically closes, preventing further pressure drop.
In the shutdown process, when the primary loop reaches the access parameter of the waste heat discharging system, the pressure is 3.0MPa.a, the temperature is 180 ℃, and the control system 502 switches the state of the pilot-operated safety valve according to the pressure feedback of the instrument on the primary loop pipeline.
During shutdown, when the related safety system is started by mistake or a main pump which has stopped is started by mistake, a circuit pressure is suddenly increased or a circuit pressure is fluctuated, when the pressure is increased to 3.5mpa.a (cold state opening set value), the control system 502 generates a trigger signal, and the pilot type safety valve protection valves 101, 201 and 301 are triggered to open by the control line 501, so that a circuit is decompressed to prevent the damage of the circuit caused by further pressure increase. When the pressure of the primary circuit is reduced to 3.2MPa (cold state closing set value), the protection system triggers the pilot type safety valve to close so as to prevent the pressure from further reducing.
The control system 502 is also electrically connected to each of the pilot operated relief valve isolation valves 102, 202, 302. The pilot valve isolation valve is controlled to be in a continuous opening state so as to be ready for overpressure protection at low temperature.
When the pilot operated relief valve protection valve 101, 201, 301 is opened by mistake, or after overpressure protection is opened, it does not fall back in time at the closing setpoint, the primary circuit pressure will continue to drop until the isolation setpoint of the pilot operated relief valve isolation valve 102, 202, 302 is reached, and the isolation valve is closed to prevent complete loss of coolant.
In this embodiment, the apparatus further comprises a nitrogen source connected to the stabilizer 001 through a nitrogen filling pipe 601, and is used for filling nitrogen into the stabilizer 001 to discharge the coolant vapor in the stabilizer 001 when a loop temperature is between 120 ℃ and 180 ℃ during shutdown.
In the shutdown process, when the temperature of the first loop is 120-180 ℃, the steam cavity of the voltage stabilizer is eliminated as soon as possible, and a nitrogen source is utilized to charge nitrogen into the voltage stabilizer 001 through the nitrogen charging pipe 601, so as to form a nitrogen cavity, thereby avoiding the first loop from entering a thorough water entity state and reducing the risk capability of resisting low temperature and overpressure. The voltage stabilizer 001 still has a certain capacity of absorbing pressure change caused by volume change of the water body.
In this embodiment, still include initiative relief structure, initiative relief structure includes initiative relief pipe and first valve, and automatic relief pipe is located the top of stabiliser 001, and first valve is located on the automatic relief pipe.
In this embodiment, the active pressure relief structure further includes a second valve, the second valve is disposed on the automatic pressure relief pipe, the first valve is connected with the control system 502 and is used for feeding back an opened signal to the control system 502, and the second valve is also connected with the control system 502 and is used for feeding back an opened signal to the control system 502.
In this embodiment, in order to improve the reliability of active pressure relief, two active pressure relief structures are provided, as shown in fig. 1, a first electric isolation valve 403 and a first electric angle valve 405 are installed on a first active pressure relief pipe 401, a second electric isolation valve 404 and a second electric angle valve 406 are installed on a second active pressure relief pipe 402, and the active pressure relief pipes of the two active pressure relief structures are connected with a pressure stabilizer 001 through an active pressure relief main pipe 400, and each pressure relief pipe has 100% overpressure protection capability.
The active pressure relief structure is used for releasing the primary loop medium by opening the valves 403, 404, 405 and 406 in the main control room by an operator when the automatic pressure relief structure fails to complete the overpressure protection in time. In order to prevent a loop opening caused by misoperation, two valves 403-405, 404-406 on each pressure release pipeline are provided with a chain alarm, and the opening of any valve can generate an alarm of sound and light in a main control room and cannot be eliminated in the whole process until the valves on each row of the valves are closed, so that the core damage caused by the misoperation of the valves is avoided.
The active pressure relief pipeline and the automatic pressure relief pipeline can discharge air pressure into the atmosphere of the containment, can discharge air pressure into a special pressure relief box, and can discharge air pressure into a built-in refueling water tank.
On the premise that the existing safety valve successively has setting value switching capability, in the existing nuclear power technology, two independent sets of overpressure protection equipment are still configured for the overpressure protection function of reactor power operation and the overpressure protection capability in the shutdown process, so that redundancy of the equipment, rising of investment cost and related arrangement and operation cost are caused. Therefore, the integrated reactor overpressure protection system provided by the invention has the overpressure protection function under the power operation of a power plant and the low-pressure protection function in the shutdown process, and simultaneously, the steam cavity is not simply eliminated in the shutdown process, but the nitrogen cavity is replaced by the integrated reactor overpressure protection system.
Example 2:
this embodiment provides a method for reactor overpressure protection using the system of embodiment 1, comprising:
during power plant power operation, when the pressure in the pressure stabilizer 001 is larger than a pilot type safety valve opening set value, the pilot type safety valve is automatically opened, so that the pressure stabilizer 001 is communicated with an automatic pressure relief pipe, coolant steam in the pressure stabilizer 001 is discharged through the automatic pressure relief pipe, and when the pressure in the pressure stabilizer 001 is smaller than the pilot type safety valve closing set value, the pilot type safety valve is automatically closed;
during shutdown, when the pressure in the pressure stabilizer 001 is greater than the cold state opening set value, the control system 502 controls the pilot-operated safety valve to be opened so that the pressure stabilizer 001 is communicated with the automatic pressure relief pipe, the coolant vapor in the pressure stabilizer 001 is discharged through the automatic pressure relief pipe, and when the pressure in the pressure stabilizer 001 is less than the cold state closing set value, the control system 502 controls the pilot-operated safety valve to be closed.
Example 3:
the present embodiment provides a nuclear power-loop system, including a loop pipe, and the reactor overpressure protection system of embodiment 1, the voltage regulator is in communication with the loop pipe.
Examples:
the present embodiment provides a nuclear power system, including a reactor pressure vessel, and the nuclear power primary loop system of embodiment 3, where the reactor pressure vessel is in communication with a loop pipe of the nuclear power primary loop system.
It is to be understood that the above embodiments are merely illustrative of the application of the principles of the present invention, but not in limitation thereof. Various modifications and improvements may be made by those skilled in the art without departing from the spirit and substance of the invention, and are also considered to be within the scope of the invention.
Claims (9)
1. A reactor overpressure protection system, comprising: the automatic pressure relief structure comprises an automatic pressure relief pipe and a pilot type safety valve,
the automatic pressure relief pipe is arranged at the top of the pressure stabilizer (001) and is used for discharging the coolant steam in the pressure stabilizer (001) when the automatic pressure relief pipe is communicated with the pressure stabilizer (001),
the pilot type safety valve is arranged on the automatic pressure relief pipe and is used for automatically opening when the pressure in the pressure stabilizer (001) is larger than a pilot type safety valve opening set value during power operation of the power plant, so that the pressure stabilizer (001) is communicated with the automatic pressure relief pipe, coolant steam in the pressure stabilizer (001) is discharged through the automatic pressure relief pipe, and when the pressure in the pressure stabilizer (001) is smaller than a pilot type safety valve closing set value, the pilot type safety valve is automatically closed, so that the pressure stabilizer (001) is disconnected from the automatic pressure relief pipe, and the pilot type safety valve opening set value is larger than the pilot type safety valve closing set value;
the control system (502) is electrically connected with the pilot-operated safety valve and is used for controlling the pilot-operated safety valve to be opened when the pressure in the pressure stabilizer (001) is larger than a cold state opening set value during shutdown, so that the pressure stabilizer (001) is communicated with the automatic pressure relief pipe, coolant steam in the pressure stabilizer (001) is discharged through the automatic pressure relief pipe, and the pilot-operated safety valve is controlled to be closed when the pressure in the pressure stabilizer (001) is smaller than a cold state closing set value, wherein the cold state opening set value is larger than the cold state closing set value and smaller than the pilot-operated safety valve closing set value;
the automatic pressure relief structure also comprises a pilot type isolation valve which is arranged on the automatic pressure relief pipe and is positioned behind the pilot type safety valve along the steam flow direction and is used for being opened when the pressure in the pressure stabilizer (001) is in a normal range during the power operation of the power plant and being automatically closed when the pilot type safety valve is opened and the pressure in the pressure stabilizer (001) is smaller than the closing set value of the pilot type isolation valve,
the closing set value of the pilot isolation valve is smaller than the closing set value of the pilot safety valve and larger than the cold state opening set value.
2. The reactor overpressure protection system of claim 1, wherein the pressure regulator (001) is in communication with a loop conduit of the reactor, the loop conduit having a meter thereon for monitoring a loop pressure, the meter being electrically connected to the control system (502) for feeding back a loop pressure signal to the control system (502).
3. The reactor overpressure protection system of claim 1 further comprising a nitrogen source connected to the pressurizer (001) by a nitrogen filling pipe (601) for filling nitrogen into the pressurizer (001) to discharge coolant vapor from the pressurizer (001) during shutdown at a loop temperature between 120 ℃ and 180 ℃.
4. A reactor overpressure protection system as set forth in any one of claims 1-3 further comprising an active pressure relief structure comprising an active pressure relief tube and a first valve, the automatic pressure relief tube being disposed on top of the pressurizer (001), the first valve being disposed on the automatic pressure relief tube.
5. The reactor overpressure protection system of claim 4, wherein the active pressure relief structure further comprises a second valve disposed on the automatic pressure relief tube, the first valve being connected to the control system (502) for feeding back its open signal to the control system (502), the second valve also being connected to the control system (502) for feeding back its open signal to the control system (502).
6. The reactor overpressure protection system of claim 4, wherein said automatic pressure relief structure is provided with a plurality of,
the active pressure relief structure is provided with a plurality of active pressure relief pipes, and the active pressure relief pipes of the plurality of active pressure relief structures are connected with the voltage stabilizer (001) through an active pressure relief master pipe (400).
7. A method of reactor overpressure protection utilizing the system of any of claims 1-6, comprising:
during power plant power operation, when the pressure in the pressure stabilizer (001) is larger than a pilot-operated safety valve opening set value, the pilot-operated safety valve is automatically opened, so that the pressure stabilizer (001) is communicated with an automatic pressure relief pipe, coolant steam in the pressure stabilizer (001) is discharged through the automatic pressure relief pipe, and when the pressure in the pressure stabilizer (001) is smaller than a pilot-operated safety valve closing set value, the pilot-operated safety valve is automatically closed;
during shutdown, when the pressure in the pressure stabilizer (001) is greater than a cold state opening set value, the control system (502) controls the pilot type safety valve to be opened so that the pressure stabilizer (001) is communicated with the automatic pressure relief pipe, coolant steam in the pressure stabilizer (001) is discharged through the automatic pressure relief pipe, and when the pressure in the pressure stabilizer (001) is less than the cold state closing set value, the control system (502) controls the pilot type safety valve to be closed.
8. A nuclear power-loop system comprising a loop conduit, and the reactor overpressure protection system of any one of claims 1-6, the pressure regulator in communication with the loop conduit.
9. A nuclear power system comprising a reactor pressure vessel in communication with a circuit conduit of the nuclear power-circuit system of claim 8, and the nuclear power-circuit system of claim 8.
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Citations (10)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH01285897A (en) * | 1988-05-12 | 1989-11-16 | Nippon Atom Ind Group Co Ltd | Automatic pressure reducing device of nuclear reactor |
| JPH0236398A (en) * | 1988-07-27 | 1990-02-06 | Mitsubishi Heavy Ind Ltd | Automatic cooling operation device for operation from hot state to cold state of pressurized water nuclear power plant |
| CN104332206A (en) * | 2013-07-22 | 2015-02-04 | 中国核动力研究设计院 | Overpressure protection method for reactor startup/shutdown condition of PWR (pressurized water reactor) nuclear power plant |
| CN104425045A (en) * | 2013-09-11 | 2015-03-18 | 中国广核集团有限公司 | Information processing method of loop voltage stabilizer in nuclear power plant and checking method |
| CN104425043A (en) * | 2013-08-27 | 2015-03-18 | 中广核工程有限公司 | Control method and system for overpressure protection of main loop of nuclear power plant |
| CN106229021A (en) * | 2016-07-27 | 2016-12-14 | 中广核工程有限公司 | Prevent control system and the control method of nuclear power station main steam line superpressure |
| CN106409360A (en) * | 2016-09-27 | 2017-02-15 | 中广核研究院有限公司 | Method used for achieving nuclear power plant overpressure protection functions |
| CN211788195U (en) * | 2020-03-18 | 2020-10-27 | 华龙国际核电技术有限公司 | Overpressure protection pressure relief discharge system and nuclear power station with same |
| CN212990694U (en) * | 2020-08-14 | 2021-04-16 | 中国核电工程有限公司 | Overpressure protection device of waste heat discharge system and waste heat discharge system |
| CN112923109A (en) * | 2021-03-22 | 2021-06-08 | 上海核工程研究设计院有限公司 | Safety relief valve door system |
Family Cites Families (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US8559584B2 (en) * | 2010-12-20 | 2013-10-15 | Westinghouse Electric Company Llc | Nuclear reactor automatic depressurization system |
| GB201820328D0 (en) * | 2018-12-13 | 2019-01-30 | Rolls Royce Plc | Depressurisation valve |
-
2021
- 2021-07-06 CN CN202110760238.4A patent/CN113571211B/en active Active
Patent Citations (10)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH01285897A (en) * | 1988-05-12 | 1989-11-16 | Nippon Atom Ind Group Co Ltd | Automatic pressure reducing device of nuclear reactor |
| JPH0236398A (en) * | 1988-07-27 | 1990-02-06 | Mitsubishi Heavy Ind Ltd | Automatic cooling operation device for operation from hot state to cold state of pressurized water nuclear power plant |
| CN104332206A (en) * | 2013-07-22 | 2015-02-04 | 中国核动力研究设计院 | Overpressure protection method for reactor startup/shutdown condition of PWR (pressurized water reactor) nuclear power plant |
| CN104425043A (en) * | 2013-08-27 | 2015-03-18 | 中广核工程有限公司 | Control method and system for overpressure protection of main loop of nuclear power plant |
| CN104425045A (en) * | 2013-09-11 | 2015-03-18 | 中国广核集团有限公司 | Information processing method of loop voltage stabilizer in nuclear power plant and checking method |
| CN106229021A (en) * | 2016-07-27 | 2016-12-14 | 中广核工程有限公司 | Prevent control system and the control method of nuclear power station main steam line superpressure |
| CN106409360A (en) * | 2016-09-27 | 2017-02-15 | 中广核研究院有限公司 | Method used for achieving nuclear power plant overpressure protection functions |
| CN211788195U (en) * | 2020-03-18 | 2020-10-27 | 华龙国际核电技术有限公司 | Overpressure protection pressure relief discharge system and nuclear power station with same |
| CN212990694U (en) * | 2020-08-14 | 2021-04-16 | 中国核电工程有限公司 | Overpressure protection device of waste heat discharge system and waste heat discharge system |
| CN112923109A (en) * | 2021-03-22 | 2021-06-08 | 上海核工程研究设计院有限公司 | Safety relief valve door system |
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