CN110970139A - Pressure stabilizer overflow prevention system, pressurized water reactor nuclear power plant and pressure stabilizer overflow prevention method - Google Patents
Pressure stabilizer overflow prevention system, pressurized water reactor nuclear power plant and pressure stabilizer overflow prevention method Download PDFInfo
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- CN110970139A CN110970139A CN201811157894.XA CN201811157894A CN110970139A CN 110970139 A CN110970139 A CN 110970139A CN 201811157894 A CN201811157894 A CN 201811157894A CN 110970139 A CN110970139 A CN 110970139A
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- 239000003381 stabilizer Substances 0.000 title claims abstract description 120
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 title claims abstract description 48
- 230000002265 prevention Effects 0.000 title claims abstract description 47
- 238000000034 method Methods 0.000 title claims abstract description 17
- 239000007788 liquid Substances 0.000 claims abstract description 80
- 239000012530 fluid Substances 0.000 claims abstract description 56
- 239000002826 coolant Substances 0.000 claims abstract description 29
- 238000001816 cooling Methods 0.000 claims description 34
- 238000002347 injection Methods 0.000 claims description 24
- 239000007924 injection Substances 0.000 claims description 24
- 238000001514 detection method Methods 0.000 claims description 17
- 238000000746 purification Methods 0.000 claims description 15
- 230000001105 regulatory effect Effects 0.000 claims description 10
- 238000002955 isolation Methods 0.000 claims description 9
- 230000001276 controlling effect Effects 0.000 claims description 7
- 239000000941 radioactive substance Substances 0.000 claims description 5
- NWUYHJFMYQTDRP-UHFFFAOYSA-N 1,2-bis(ethenyl)benzene;1-ethenyl-2-ethylbenzene;styrene Chemical compound C=CC1=CC=CC=C1.CCC1=CC=CC=C1C=C.C=CC1=CC=CC=C1C=C NWUYHJFMYQTDRP-UHFFFAOYSA-N 0.000 claims description 3
- 239000003456 ion exchange resin Substances 0.000 claims description 3
- 229920003303 ion-exchange polymer Polymers 0.000 claims description 3
- 239000000243 solution Substances 0.000 description 6
- 239000000126 substance Substances 0.000 description 6
- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical compound [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-N 0.000 description 5
- 229910052796 boron Inorganic materials 0.000 description 5
- KGBXLFKZBHKPEV-UHFFFAOYSA-N boric acid Chemical compound OB(O)O KGBXLFKZBHKPEV-UHFFFAOYSA-N 0.000 description 4
- 239000004327 boric acid Substances 0.000 description 4
- 230000008569 process Effects 0.000 description 4
- 230000007123 defense Effects 0.000 description 3
- 238000010586 diagram Methods 0.000 description 3
- 230000002285 radioactive effect Effects 0.000 description 3
- 239000012857 radioactive material Substances 0.000 description 3
- 238000009530 blood pressure measurement Methods 0.000 description 2
- 238000005202 decontamination Methods 0.000 description 2
- 230000003588 decontaminative effect Effects 0.000 description 2
- 238000013461 design Methods 0.000 description 2
- 230000009467 reduction Effects 0.000 description 2
- 238000005507 spraying Methods 0.000 description 2
- 238000006467 substitution reaction Methods 0.000 description 2
- 230000004308 accommodation Effects 0.000 description 1
- 230000004888 barrier function Effects 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 230000008859 change Effects 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 239000000498 cooling water Substances 0.000 description 1
- 230000006837 decompression Effects 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 150000002500 ions Chemical class 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 238000013021 overheating Methods 0.000 description 1
- 239000002245 particle Substances 0.000 description 1
- 230000000149 penetrating effect Effects 0.000 description 1
- 239000002574 poison Substances 0.000 description 1
- 231100000614 poison Toxicity 0.000 description 1
- 238000012545 processing Methods 0.000 description 1
- 238000010926 purge Methods 0.000 description 1
- 230000008054 signal transmission Effects 0.000 description 1
- 229910052724 xenon Inorganic materials 0.000 description 1
- FHNFHKCVQCLJFQ-UHFFFAOYSA-N xenon atom Chemical compound [Xe] FHNFHKCVQCLJFQ-UHFFFAOYSA-N 0.000 description 1
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- 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
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
- G21C13/02—Details
-
- 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
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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Business, Economics & Management (AREA)
- Emergency Management (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention provides a voltage stabilizer overfilling prevention system, a pressurized water reactor nuclear power plant and a voltage stabilizer overfilling prevention method, wherein the voltage stabilizer overfilling prevention system is applied to the pressurized water reactor nuclear power plant, the pressurized water reactor nuclear power plant comprises a reactor coolant system, the reactor coolant system comprises a voltage stabilizer, and the voltage stabilizer overfilling prevention system comprises: the collecting tank, a main pipeline connected between the pressure stabilizer and the collecting tank, a valve group arranged on the main pipeline and a control device connected with the valve group, wherein the control device is used for controlling the valve group to be opened when the liquid level of the pressure stabilizer is higher than or equal to a first preset liquid level so as to enable fluid in the pressure stabilizer to enter the collecting tank through the main pipeline; and when the liquid level of the voltage stabilizer is lower than or equal to a second preset liquid level, controlling the valve group to be closed, wherein the first preset liquid level is greater than the second preset liquid level. The voltage stabilizer overflow-preventing system provided by the embodiment of the invention has high safety and reliability.
Description
Technical Field
The invention relates to the technical field of automatic control of nuclear power stations, in particular to a pressure stabilizer overflow prevention system, a pressurized water reactor nuclear power plant and a pressure stabilizer overflow prevention method.
Background
In the process of designing a benchmark accident of a pressurized water reactor nuclear power plant, in order to continuously cool and depressurize a reactor coolant system after the reactor is shut down so as to safely shut down the nuclear power plant, an emergency boron injection system is required to inject a concentrated boric acid solution into the reactor coolant system so as to compensate the positive and negative reactions caused by cooling of the reactor coolant system and reduction of xenon poison, and the reactor is ensured to be in a subcritical state, so that the safety of the pressurized water reactor nuclear power plant is ensured.
In addition, because the demand of the concentrated boric acid solution is large, in the process of injecting the concentrated boric acid solution into the emergency boron injection system, the water content in the reactor coolant system is greatly increased, so that the overflow of the voltage stabilizer can be caused, when the overflow of the voltage stabilizer occurs, the safety valve of the voltage stabilizer can be opened due to the failure of water, so that the failure of a second radioactive safety barrier of the nuclear power plant can be caused, the pressure regulation function of the reactor coolant system can be lost, and great risk can be brought to the safety of the nuclear power plant.
In the related art, in order to prevent the overflow of the pressurizer, part of the reactor coolant is discharged into the volume control box through the discharge function of the chemical and volume control system, so that the effect of preventing the overflow of the pressurizer can be achieved. However, the chemical and volume control system is used for executing three-level nuclear safety functions, is mainly used for normal operation conditions and predicted operation events of the pressurized water reactor nuclear power station, and belongs to the second level of deep defense of the nuclear power plant. In the process of cooling a reactor coolant system under the condition of a design benchmark accident, the emergency boron injection and voltage stabilizer overflow prevention function is a nuclear safety secondary function, and belongs to the third level of deep defense of a nuclear power plant. In the related art, the chemical and volume control systems with different safety function levels are used for executing the overflow prevention function of the voltage stabilizer, which may cause the risk of common cause failure of the safety systems with different depth defense levels. Moreover, the volume control box of the chemical and volume control system has limited capacity, so that the safety margin when the pressure stabilizer is overflowed is small, thereby reducing the reliability of the overflow prevention function of the pressure stabilizer.
Therefore, the technical scheme of adopting the chemical and volume control system to execute the overflow prevention function of the voltage stabilizer in the related art has the defect of low safety and reliability.
Disclosure of Invention
The embodiment of the invention provides a pressure stabilizer overflow prevention system, a pressurized water reactor nuclear power plant and a pressure stabilizer overflow prevention method, which aim to solve the problem of low safety and reliability in the technical scheme of executing the pressure stabilizer overflow prevention function by adopting a chemical and volume control system in the related technology.
In order to solve the technical problems, the invention adopts the following technical scheme:
in a first aspect, an embodiment of the present invention provides a voltage regulator overfill prevention system, which is applied to a pressurized water reactor nuclear power plant, where the pressurized water reactor nuclear power plant includes a reactor coolant system, the reactor coolant system includes a voltage regulator, and the voltage regulator overfill prevention system includes:
a collection box;
a main pipe connected between the pressurizer and the collection tank;
the valve group is arranged on the main pipeline; and the number of the first and second groups,
the control device is connected with the valve group and is used for controlling the valve group to be opened when the liquid level of the pressure stabilizer is higher than or equal to a first preset liquid level so as to enable the fluid in the pressure stabilizer to enter the collection box through the main pipeline; and when the liquid level of the voltage stabilizer is lower than or equal to a second preset liquid level, controlling the valve group to be closed, wherein the first preset liquid level is greater than the second preset liquid level.
Optionally, the overflow-preventing system of the voltage stabilizer further includes:
and the pressure relief device is arranged on the main pipeline and used for reducing the pressure of the fluid flowing through the main pipeline to a preset pressure.
Optionally, the overflow-preventing system of the voltage stabilizer further includes:
and the pressure detection device is arranged on the main pipeline and positioned on the low-pressure side of the pressure relief device.
Optionally, the overflow-preventing system of the voltage stabilizer further includes:
and the cooling device is arranged on the main pipeline and used for reducing the temperature of the fluid flowing through the main pipeline to a preset temperature.
Optionally, the overflow-preventing system of the voltage stabilizer further includes:
the temperature detection device is arranged on the main pipeline and connected with the control device, and the control device adjusts the cooling power of the cooling device according to the temperature of the fluid flowing through the main pipeline detected by the temperature detection device so as to reduce the temperature of the fluid to the preset temperature.
Optionally, the overflow-preventing system of the voltage stabilizer further includes:
and the purifying device is arranged on the main pipeline and is used for removing radioactive substances in the fluid flowing through the main pipeline.
Optionally, the purification device comprises a filter and an ion exchange resin.
Optionally, the overflow-preventing system of the voltage stabilizer further includes:
and the flow detection device is arranged on the main pipeline.
Optionally, the overflow-preventing system of the voltage stabilizer further includes:
set up in pressure relief device, cooling device and purifier on the trunk line, wherein, cooling device set up in pressure relief device with between the purifier, just pressure relief device set up in cooling device be close to one side of stabiliser.
Optionally, the valve group further includes:
and the flow regulating valve is arranged on the main pipeline and used for regulating the flow of the fluid flowing in the main pipeline to a preset flow, wherein the preset flow is determined according to the performance of at least one of the pressure relief device, the cooling device and the purifying device.
Optionally, the valve set includes:
the first isolation valve is arranged at one end, close to the voltage stabilizer, of the main pipeline; and/or the presence of a gas in the gas,
and the second isolation valve is arranged at one end of the main pipeline close to the collecting box.
Optionally, the pressurized water reactor nuclear power plant further comprises a safe injection system, the collecting box is a safe injection system water tank of the safe injection system, a nozzle is arranged at a position, facing the pipeline outlet in the safe injection system water tank, of the main pipeline, and the nozzle is used for uniformly spraying fluid sprayed out of the main pipeline into the safe injection system water tank.
Optionally, the main pipeline is connected to the bottom of the lower end enclosure of the voltage stabilizer.
In a second aspect, an embodiment of the present invention further provides a pressurized water reactor nuclear power plant, including a reactor coolant system, where the reactor coolant system includes a pressurizer, and the pressurized water reactor nuclear power plant further includes the above-mentioned pressurizer overfill prevention system.
Optionally, the pressurized water reactor nuclear power plant further includes a containment vessel, and the pressurizer overfilling prevention system is disposed in the containment vessel.
In a third aspect, an embodiment of the present invention further provides an anti-overflow method for a voltage regulator, which is applied to the above-mentioned anti-overflow system for a voltage regulator, where the method includes:
detecting a liquid level in the potentiostat;
opening the valve group to reduce the liquid level in the pressure stabilizer under the condition that the liquid level in the pressure stabilizer is higher than or equal to a first preset liquid level;
and closing the valve group under the condition that the liquid level in the voltage stabilizer is reduced to the second preset liquid level, wherein the first preset liquid level is greater than the second preset liquid level.
In the embodiment of the invention, when the liquid level in the voltage stabilizer is too high, the valve group on the main pipeline is opened so that the fluid in the voltage stabilizer flows into the collecting tank through the main pipeline, thereby preventing the overflow of the voltage stabilizer caused by the too high liquid level in the voltage stabilizer; in addition, the valve group is closed when the liquid level in the voltage stabilizer is reduced to the required level, so that the damage of a heater and the like in the voltage stabilizer caused by the excessively low liquid level in the voltage stabilizer is avoided, and the safety and the reliability of the voltage stabilizer are improved.
Drawings
In order to more clearly illustrate the technical solutions of the embodiments of the present invention, the drawings needed to be used in the description of the embodiments or the prior art will be briefly described below, and it is obvious that the drawings in the following description are only some embodiments of the present invention, and it is obvious for those skilled in the art that other drawings can be obtained according to these drawings without creative efforts.
Fig. 1 is a schematic structural diagram of an anti-overflow system of a voltage regulator according to an embodiment of the present invention;
FIG. 2 is a schematic diagram of the pressurizer overfill prevention system of FIG. 1 disposed in a containment vessel of a pressurized water reactor nuclear power plant;
fig. 3 is a flowchart of an anti-overflow method for a voltage regulator according to an embodiment of the present invention.
Detailed Description
The technical solutions in the embodiments of the present invention will be clearly and completely described below with reference to the drawings in the embodiments of the present invention, and it is obvious that the described embodiments are some, not all, embodiments of the present invention. All other embodiments, which can be derived by a person skilled in the art from the embodiments given herein without making any creative effort, shall fall within the protection scope of the present invention.
Referring to fig. 1, a schematic structural diagram of an overfill prevention system for a pressure stabilizer according to an embodiment of the present invention is provided, where the overfill prevention system is applied to a pressurized water reactor nuclear power plant, the pressurized water reactor nuclear power plant includes a reactor coolant system 200, and the reactor coolant system 200 includes a pressure stabilizer 201.
As shown in fig. 1, the anti-overflow system of the voltage regulator includes: a collecting tank 101, a main pipe 102 connected between the pressurizer 201 and the collecting tank 101, a valve group (not numbered) provided on the main pipe 102, and a control device (not shown) connected to the valve group.
The control device is used for controlling the valve group to be opened when the liquid level of the pressure stabilizer 201 is higher than or equal to a first preset liquid level, so that fluid in the pressure stabilizer 201 enters the collecting tank 101 through the main pipeline 102; when the liquid level of the pressure stabilizer 201 is lower than or equal to a second preset liquid level, the valve set is controlled to be closed, and the first preset liquid level is larger than the second preset liquid level.
The overflow-preventing system of the pressure stabilizer provided by the embodiment of the invention has a simple structure, and devices such as the main pipeline 102, the valve group, the collecting box 101 and the like and the pressure stabilizer 201 can be in the same safety level, during the normal operation of a pressurized water reactor nuclear power plant, for example: the power operation, the hot shutdown, the hot standby, the material change and other normal operation conditions are adopted, the valve group is closed, and the overflow-preventing system of the voltage stabilizer is in a standby state.
Wherein, under the condition that takes place design benchmark accident, reactor coolant system lowers the temperature and steps down to adopt emergent boron injection system to continue to pour into boric acid solution into reactor coolant system, cause the water charge volume in the reactor coolant system to constantly increase, further cause stabiliser 201 water level to rise, when the liquid level in stabiliser 201 surpassed first predetermined liquid level, the valve group was opened, and the stabiliser prevents that the overflow system is in and puts into the running state this moment.
In addition, because the fluid in the pressure stabilizer 201 flows into the collecting tank 101 through the main pipeline 102, when the temperature reduction and depressurization of the reactor coolant system are finished, or after the emergency boron injection is finished, and the liquid level in the pressure stabilizer 201 is lower than or equal to a second preset liquid level, the valve group is closed, and at the moment, the pressure stabilizer prevents the overflow system from running off.
In application, a heat pipe section 203 is connected between the reactor coolant system and the pressure vessel 202, and the pressure stabilizer 201 is communicated with the heat pipe section 203, so that high-temperature and high-pressure fluid in the reactor coolant system enters the pressure stabilizer 201 through the heat pipe section 203.
If the liquid level in the pressurizer 201 is higher than the first predetermined liquid level, the pressurizer 201 may overflow, thereby damaging the safety of the pressurizer and the reactor coolant system 200.
In addition, the second preset liquid level is slightly lower than the first preset liquid level and is larger than the lowest liquid level of the liquid level in the pressure stabilizer 201, so that the problem that the valve group is repeatedly opened and closed to cause overwork damage due to the fact that the liquid level in the pressure stabilizer 201 floats up and down on the first preset liquid level is avoided.
It should be noted that the collection tank 101 may be an existing water tank in a pressurized water reactor nuclear power plant, for example: the water tank of the safe injection system in the safe injection system can be a collection box which is newly added in the overflow prevention system of the voltage stabilizer and has the same safety level with the voltage stabilizer and is used for collecting the fluid discharged from the voltage stabilizer.
In the embodiment of the invention, when the liquid level in the voltage stabilizer is too high, the valve group on the main pipeline is opened so that the fluid in the voltage stabilizer flows into the collecting tank through the main pipeline, thereby preventing the overflow of the voltage stabilizer caused by the too high liquid level in the voltage stabilizer; in addition, the valve group is closed when the liquid level in the voltage stabilizer is reduced to a normal level, so that the damage of a heater and the like in the voltage stabilizer caused by the excessively low liquid level in the voltage stabilizer is avoided, and the safety and the reliability of the voltage stabilizer are improved.
During use, the fluid within the pressurizer 201 is often at a high temperature and pressure and is also doped with radioactive materials, which makes it inconvenient to handle and discharge the fluid discharged from the pressurizer 201.
Thus, at least one of the pressure relief device 104, the cooling device 105, and the purging device 106 may be provided in the potentiostat overfill prevention system.
The pressure relief device 104 is disposed on the main pipe 102, and is configured to reduce a pressure of a fluid flowing through the main pipe 102 to a preset pressure. The preset pressure may be determined according to the structures and properties of the cooling device 105, the purifying device 106 and the collection box 101, so as to ensure that the cooling device 105, the purifying device 106 and the collection box 101 can normally operate under the preset pressure.
Specifically, the pressure relief device 104 may be a pressure relief orifice, wherein the structure is simple and durable.
In addition, a cooling device 105 is provided on the main pipe 102 for reducing the temperature of the fluid flowing in the main pipe 102 to a preset temperature. The preset temperature may be determined according to the structure and performance of the purification device 106 and the collection box 101, so as to ensure that the purification device 106 and the collection box 101 can work normally or discharge normally at the preset temperature.
Specifically, the cooling device 105 is a heat exchanger, and the cooling medium in the heat exchanger is provided by an equipment cooling water system of the pressurized water reactor nuclear power plant, so that a new cooling medium is not required to be provided, and the structure of the anti-overflow system of the pressure stabilizer is simpler.
In addition, a decontamination apparatus 106 is provided on the main conduit for removing radioactive material from the fluid flowing in the main conduit 102.
Specifically, the purification device 106 includes a filter for removing radioactive particles from the fluid and an ion exchange resin for removing radioactive ions from the fluid to ensure that the radioactivity of the fluid being transferred meets the emission requirements.
In a preferred embodiment, the pressurizer overfill prevention system comprises a pressure relief device 104, a cooling device 105 and a purification device 106 arranged on the main pipe 102, wherein the cooling device 105 is arranged between the pressure relief device 104 and the purification device 106, and the pressure relief device 104 is arranged on the side of the cooling device 105 close to the pressurizer 201.
Therefore, the fluid can be decompressed through the decompression device, so that the pressure bearing requirements on the cooling device, the purification device and the collection box are reduced, the heat resisting requirements on the purification device and the collection box are reduced after the cooling device cools the fluid, the radioactive substances in the fluid are removed after the purification device purifies the fluid, and the isolation and accommodation requirements of the collection box on the radioactive substances are reduced.
Optionally, the valve set includes a flow regulating valve 1031 disposed on the main pipe 102, and the flow regulating valve 1031 is configured to regulate the flow of the fluid flowing through the main pipe 102 to a preset flow.
Wherein the preset flow rate is determined according to the performances of the pressure relief device 104, the cooling device 105 and the purification device 106.
In addition, the flow of the fluid flowing through the main pipe 102 is controlled to be less than or equal to the preset flow by the flow regulating valve 1031, which can prevent the pressure of the fluid from being reduced to the preset pressure by the pressure relief device 104 due to the fact that the flow of the fluid exceeds the flow which can be processed by the pressure relief device 104, the cooling device 105 and the purification device 106 due to overlarge flow, and further prevent the pressure which should be born by the cooling device 105, the purification device 106 and the collection box 101 from being damaged or affecting the performance; or, the cooling device 105 is unable to lower the temperature of the fluid to the preset temperature, further causing the purification device 106 and the collection box 101 to be damaged or affecting the performance due to overheating; alternatively, the decontamination apparatus 106 may not be able to sufficiently absorb the radioactive material of the fluid to meet the emission requirements.
Therefore, the flow of the fluid flowing through the main pipeline is controlled by the flow regulating valve, and the normal operation of each device can be ensured in the process of treating the fluid flowing through the main pipeline, so that the safety and reliability of the anti-overflow system of the pressure stabilizer are improved.
Optionally, the pressure stabilizer overflow prevention system further comprises a pressure detection device 107 disposed on the main pipe 102 and located on the low-pressure side of the pressure relief device 104.
Like this, can detect the fluid pressure after the pressure release constantly, through looking over the pressure value that pressure measurement device detected when it surpasss preset pressure, the staff in the nuclear power plant of being convenient for in time discovers, perhaps pressure measurement device can also be with surpassing the signal transmission who predetermines pressure to controlling means to close in time through controlling means control valve group, avoid pressure too big and damage the stabiliser and prevent the overfilling system, thereby promoted the fail safe nature of overfilling system is prevented to the stabiliser.
Optionally, the anti-overflow system of the pressure stabilizer further includes a temperature detection device 108 disposed on the main pipe 102 and connected to the control device, and the control device adjusts the cooling power of the cooling device 105 according to the temperature of the fluid flowing through the main pipe 102 detected by the temperature detection device 108, so as to reduce the temperature of the fluid to the preset temperature.
In this way, the temperature detection device can detect that the temperature of the cooled fluid exceeds the preset temperature when the cooling device fails or the flow rate of the fluid in the main pipe exceeds the processing capacity of the cooling device due to the failure of the flow rate control valve. The detection temperature of the temperature detection device is checked, so that workers in the nuclear power plant can find the temperature conveniently in time; or the temperature detection device can also send a signal exceeding the preset temperature to the control device so as to control the valve set to be closed in time or adjust the flow regulating valve to reduce the flow of the fluid through the control device, and the situation that the overflow-preventing system of the voltage stabilizer is damaged due to overhigh temperature is avoided, so that the safety and reliability of the overflow-preventing system of the voltage stabilizer are improved.
Optionally, the manostat overflow prevention system further comprises a flow detection device 109 disposed on the main pipe 102.
Therefore, the flow of the fluid flowing through the main pipeline can be checked through the flow detection device, and personnel or a control device in the nuclear power plant can conveniently adjust the flow regulating valve according to the measured flow value.
Optionally, the valve group further includes a first isolation valve 1032 disposed at an end of the main pipe 102 near the end where the pressure stabilizer 201 is located; and/or the presence of a gas in the gas,
a second isolation valve 1033 is provided at an end of the main conduit 102 near the collection tank 101.
Therefore, the start and stop of the voltage stabilizer overflow prevention system are realized by opening or closing the first isolation valve and/or the second isolation valve, the misoperation of the voltage stabilizer overflow prevention system can be avoided, and the voltage stabilizer overflow prevention system is in a standby state when the nuclear power plant operates normally.
Optionally, the pressurized water reactor nuclear power plant further includes a safety injection system, the collection tank 101 is a safety injection system water tank in the safety injection system, a nozzle 110 is disposed at a pipe outlet of the main pipe 102 facing the safety injection system water tank, and the nozzle 110 is used for uniformly spraying fluid sprayed from the main pipe 102 into the safety injection system water tank.
Therefore, the contact area of the sprayed fluid and the water contained in the safe injection system water tank can be increased, the temperature of the fluid can be quickly reduced, and the fluid is mixed with the water contained in the safe injection system water tank.
Optionally, the main pipe 102 is connected to the bottom of the lower head of the pressurizer 201.
Of course, a through hole may be provided near the bottom of the regulator 201, and the main pipe 102 may communicate with the regulator 201 through the through hole.
Referring to fig. 2, an embodiment of the present invention further provides a pressurized water reactor nuclear power plant, which includes a reactor coolant system, the reactor coolant system includes a pressurizer 201, and the pressurized water reactor nuclear power plant further includes a pressurizer overfill prevention system as shown in fig. 1.
Optionally, as shown in fig. 2, the pressurized water reactor nuclear power plant further includes a containment 10, and the pressurizer overfilling prevention system is disposed in the containment 10.
In the embodiment of the invention, the voltage stabilizer overflow prevention system is arranged in the containment vessel, so that no containment vessel penetrating piece exists, and radioactive substances cannot be leaked to the external environment when the pipeline in the voltage stabilizer overflow prevention system is broken.
Referring to fig. 3, a flowchart of an anti-overflow method for a voltage regulator according to an embodiment of the present invention is applied to the anti-overflow system for a voltage regulator shown in fig. 1 or fig. 2, where the method includes:
Step 301 may be performed by using a liquid level measuring device provided in the pressure stabilizer itself, or step 301 may be performed by adding a liquid level measuring device to the pressure stabilizer overflow prevention system.
The control device in the overflow-preventing system of the voltage stabilizer can send a first control signal to the valve group when receiving a signal that the liquid level in the voltage stabilizer is higher than or equal to a first preset liquid level, and the valve group is opened according to the first control signal.
In this step, when the liquid level in the stabiliser is higher than or equal to the signal of first predetermined liquid level, open the valve group, make the trunk line intercommunication to make in the fluid in the stabiliser passes through the trunk line and gets into the collecting box, in order to reduce the liquid level in the stabiliser, avoid the stabiliser to take place the overflow and endanger nuclear power plant's safety.
The control device in the overflow-preventing system of the voltage stabilizer can send a second control signal to the valve group when receiving a signal that the liquid level in the voltage stabilizer is lower than or equal to a second preset liquid level, and the valve group closes according to the second control signal.
In the step, when the liquid level in the voltage stabilizer is lower than or equal to the signal of the second preset liquid level, the valve group is closed, and the main pipeline is not communicated, so that the fluid in the voltage stabilizer stops being discharged, and the situation that the safety of the nuclear power plant is endangered due to the fact that the liquid level in the voltage stabilizer is too low is avoided.
The overflow prevention method for the voltage regulator provided in the embodiment of the invention is applied to the overflow prevention system for the voltage regulator shown in fig. 1 or fig. 2, and can obtain the same beneficial effects, and is not described herein again to avoid repetition.
The above description is only for the specific embodiments of the present invention, but the scope of the present invention is not limited thereto, and any person skilled in the art can easily conceive of the changes or substitutions within the technical scope of the present invention, and the changes or substitutions should be covered within the scope of the present invention. Therefore, the protection scope of the present invention shall be subject to the protection scope of the claims.
Claims (16)
1. An overfill prevention system for a pressurized water reactor nuclear power plant, the pressurized water reactor nuclear power plant comprising a reactor coolant system, the reactor coolant system comprising a pressure stabilizer, the overfill prevention system comprising:
a collection box;
a main pipe connected between the pressurizer and the collection tank;
the valve group is arranged on the main pipeline; and the number of the first and second groups,
the control device is connected with the valve group and is used for controlling the valve group to be opened when the liquid level of the pressure stabilizer is higher than or equal to a first preset liquid level so as to enable the fluid in the pressure stabilizer to enter the collection box through the main pipeline; and when the liquid level of the voltage stabilizer is lower than or equal to a second preset liquid level, controlling the valve group to be closed, wherein the first preset liquid level is greater than the second preset liquid level.
2. The regulator anti-overfill system of claim 1, wherein said regulator anti-overfill system further comprises:
and the pressure relief device is arranged on the main pipeline and used for reducing the pressure of the fluid flowing through the main pipeline to a preset pressure.
3. The regulator anti-overfill system of claim 2, wherein said regulator anti-overfill system further comprises:
and the pressure detection device is arranged on the main pipeline and positioned on the low-pressure side of the pressure relief device.
4. The regulator anti-overfill system of claim 1, wherein said regulator anti-overfill system further comprises:
and the cooling device is arranged on the main pipeline and used for reducing the temperature of the fluid flowing through the main pipeline to a preset temperature.
5. The regulator anti-overfill system of claim 4, wherein said regulator anti-overfill system further comprises:
the temperature detection device is arranged on the main pipeline and connected with the control device, and the control device adjusts the cooling power of the cooling device according to the temperature of the fluid flowing in the main pipeline detected by the temperature detection device so as to reduce the temperature of the fluid to the preset temperature.
6. The regulator anti-overfill system of claim 1, wherein said regulator anti-overfill system further comprises:
and the purifying device is arranged on the main pipeline and is used for removing the radioactive substances in the fluid flowing in the main pipeline.
7. The potentiostat overfill prevention system of claim 6, wherein the purification device comprises a filter and an ion exchange resin.
8. The regulator anti-overfill system of claim 1, wherein said regulator anti-overfill system further comprises:
and the flow detection device is arranged on the main pipeline.
9. The regulator anti-overfill system of claim 1, wherein said regulator anti-overfill system further comprises:
set up in pressure relief device, cooling device and purifier on the trunk line, wherein, cooling device set up in pressure relief device with between the purifier, just pressure relief device set up in cooling device be close to one side of stabiliser.
10. The regulator anti-overfill system of claim 9, wherein said valve set further comprises:
and the flow regulating valve is arranged on the main pipeline and is used for regulating the flow of the fluid flowing in the main pipeline to a preset flow, wherein the preset flow is determined according to the performance of at least one of the pressure relief device, the cooling device and the purification device.
11. The regulator anti-overfill system of claim 1, wherein said valve set comprises:
the first isolation valve is arranged at one end, close to the voltage stabilizer, of the main pipeline; and/or the presence of a gas in the gas,
and the second isolation valve is arranged at one end of the main pipeline close to the collecting box.
12. The pressurizer overfill prevention system of claim 1, wherein the pressurized water reactor nuclear power plant further comprises a safety injection system, the collection tank is a safety injection system tank in the safety injection system, and a nozzle is disposed at a pipe outlet of the main pipe facing the safety injection system tank, the nozzle being configured to uniformly inject fluid ejected from the main pipe into the safety injection system tank.
13. The anti-overfill system of claim 1, wherein said main pipe is connected to a bottom head of said pressurizer.
14. A pressurized water reactor nuclear power plant comprising a reactor coolant system including a pressurizer, characterized in that the pressurized water reactor nuclear power plant further comprises a pressurizer overfill prevention system according to any one of claims 1 to 13.
15. The pressurized water reactor nuclear power plant of claim 14 further comprising a containment vessel, the pressurizer overfill prevention system being disposed within the containment vessel.
16. An overfill prevention method for a regulator, the overfill prevention system for a regulator according to any one of claims 1-13, said method comprising:
detecting a liquid level in the potentiostat;
opening the valve group to reduce the liquid level in the pressure stabilizer under the condition that the liquid level in the pressure stabilizer is higher than or equal to a first preset liquid level;
and closing the valve group under the condition that the liquid level in the voltage stabilizer is reduced to the second preset liquid level, wherein the first preset liquid level is greater than the second preset liquid level.
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| CA1264257A (en) * | 1985-01-16 | 1990-01-09 | James S. Schlonski | Control of nuclear reactor power plant on occurence of rupture in coolant tubes |
| JPH04104597U (en) * | 1991-02-20 | 1992-09-09 | 三菱重工業株式会社 | Pressurizer water level control device |
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