CN117976261A - Passive pressurized water reactor containment pressure relief system - Google Patents
Passive pressurized water reactor containment pressure relief system Download PDFInfo
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- CN117976261A CN117976261A CN202211312703.9A CN202211312703A CN117976261A CN 117976261 A CN117976261 A CN 117976261A CN 202211312703 A CN202211312703 A CN 202211312703A CN 117976261 A CN117976261 A CN 117976261A
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- containment
- pressure relief
- pressure
- pressurized water
- water reactor
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- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 title claims abstract description 42
- 229910001868 water Inorganic materials 0.000 title claims abstract description 41
- 238000013461 design Methods 0.000 claims abstract description 17
- 239000002918 waste heat Substances 0.000 claims abstract description 16
- 238000007599 discharging Methods 0.000 claims abstract description 8
- 238000004891 communication Methods 0.000 claims description 8
- 238000009825 accumulation Methods 0.000 claims description 3
- 230000008859 change Effects 0.000 description 14
- 239000007789 gas Substances 0.000 description 13
- 238000001816 cooling Methods 0.000 description 9
- 238000007789 sealing Methods 0.000 description 5
- 238000000034 method Methods 0.000 description 4
- 230000008569 process Effects 0.000 description 4
- 239000002826 coolant Substances 0.000 description 3
- 239000001257 hydrogen Substances 0.000 description 3
- 229910052739 hydrogen Inorganic materials 0.000 description 3
- 239000007788 liquid Substances 0.000 description 3
- 230000007774 longterm Effects 0.000 description 3
- IJGRMHOSHXDMSA-UHFFFAOYSA-N Atomic nitrogen Chemical compound N#N IJGRMHOSHXDMSA-UHFFFAOYSA-N 0.000 description 2
- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 description 2
- 230000004888 barrier function Effects 0.000 description 2
- 230000001276 controlling effect Effects 0.000 description 2
- 230000002596 correlated effect Effects 0.000 description 2
- 230000007423 decrease Effects 0.000 description 2
- 239000000463 material Substances 0.000 description 2
- 230000002285 radioactive effect Effects 0.000 description 2
- 239000000941 radioactive substance Substances 0.000 description 2
- DGAQECJNVWCQMB-PUAWFVPOSA-M Ilexoside XXIX Chemical compound C[C@@H]1CC[C@@]2(CC[C@@]3(C(=CC[C@H]4[C@]3(CC[C@@H]5[C@@]4(CC[C@@H](C5(C)C)OS(=O)(=O)[O-])C)C)[C@@H]2[C@]1(C)O)C)C(=O)O[C@H]6[C@@H]([C@H]([C@@H]([C@H](O6)CO)O)O)O.[Na+] DGAQECJNVWCQMB-PUAWFVPOSA-M 0.000 description 1
- 229910000831 Steel Inorganic materials 0.000 description 1
- 229910052768 actinide Inorganic materials 0.000 description 1
- 150000001255 actinides Chemical class 0.000 description 1
- 239000000443 aerosol Substances 0.000 description 1
- 229910052790 beryllium Inorganic materials 0.000 description 1
- ATBAMAFKBVZNFJ-UHFFFAOYSA-N beryllium atom Chemical compound [Be] ATBAMAFKBVZNFJ-UHFFFAOYSA-N 0.000 description 1
- 239000000498 cooling water Substances 0.000 description 1
- 230000000875 corresponding effect Effects 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 238000011038 discontinuous diafiltration by volume reduction Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 239000002360 explosive Substances 0.000 description 1
- 239000012530 fluid Substances 0.000 description 1
- 238000011010 flushing procedure Methods 0.000 description 1
- 239000013505 freshwater Substances 0.000 description 1
- 230000005484 gravity Effects 0.000 description 1
- 150000002431 hydrogen Chemical class 0.000 description 1
- 230000003993 interaction Effects 0.000 description 1
- 229910001338 liquidmetal Inorganic materials 0.000 description 1
- 238000012423 maintenance Methods 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 229910052757 nitrogen Inorganic materials 0.000 description 1
- 230000000149 penetrating effect Effects 0.000 description 1
- 238000010248 power generation Methods 0.000 description 1
- 239000013535 sea water Substances 0.000 description 1
- 229910052708 sodium Inorganic materials 0.000 description 1
- 239000011734 sodium Substances 0.000 description 1
- 239000007787 solid Substances 0.000 description 1
- 239000010959 steel Substances 0.000 description 1
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- 230000009466 transformation Effects 0.000 description 1
- 230000001960 triggered effect Effects 0.000 description 1
Classifications
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The invention discloses a passive pressurized water reactor containment pressure relief system which comprises at least two units, pressure relief devices and waste heat discharging devices, wherein each unit is correspondingly provided with at least one first containment, the containment of the unit is communicated with the first containment of the other unit through a pipeline, the pressure relief devices are arranged on the pipeline to control the opening and closing of the pipeline, the preset trigger threshold of the pressure relief devices is positively related to the rated design pressure of the first containment, the waste heat discharging devices are arranged on the first containment of the unit, and the waste heat discharging devices are connected with the first containment to lead out the heat of the first containment. The passive pressurized water reactor containment pressure relief system provided by the invention has the advantages of flexible configuration, stable operation, low failure risk and the like.
Description
Technical Field
The invention relates to the technical field of safety equipment of nuclear power stations, in particular to a passive pressurized water reactor containment pressure relief system.
Background
The pressurized water reactor containment is the last safety barrier of the pressurized water reactor nuclear power station for controlling the release of radioactive substances to the environment, and is a key device for guaranteeing the nuclear safety. When certain design standard accidents or even over-design accidents occur in the nuclear power station, the pressure boundary of a first loop of the reactor is invalid, a large amount of high-temperature and high-pressure water vapor, noncondensable gas and aerosol containing radioactivity are rapidly released into the atmosphere of the containment, so that the temperature and pressure in the containment are rapidly increased, if corresponding measures are not taken to timely lead out the heat released into the containment after the accidents, the temperature and pressure in the containment are reduced, the integrity of the last barrier of the nuclear power station is seriously endangered, and the risk of radioactive leakage is brought. In the related art, the technical scheme represented by the European advanced pressurized water reactor (Evolutionary Power Reactors, EPR) adopts a plurality of redundant active containment cooling systems to eliminate or relieve the risk of containment failure, however, certain disadvantages exist, and the excessive redundant design leads to the high cost of the EPR; if all power is lost, all heat traps are lost or the active equipment fails due to common cause, the containment after an accident may lose cooling and finally fail. By setting the passive safety system, the technical scheme represented by the AP1000 has the defects of slow system start, uncontrollable system parameters, incapability of being closed in time once being triggered by mistake and the like, and under the non-accident condition, the daily operation and maintenance are complicated, and the industrial potential safety hazard exists.
Disclosure of Invention
The present invention aims to solve at least one of the technical problems in the related art to some extent.
Therefore, the embodiment of the invention provides an inactive pressurized water reactor containment pressure relief system, which has the advantages of flexible configuration, stable operation, low failure risk and the like. According to the passive pressurized water reactor containment pressure relief system provided by the embodiment of the invention, the passive pressurized water reactor containment pressure relief system comprises at least two units, a pressure relief device and a waste heat discharge device, wherein each unit is correspondingly provided with at least one first containment, the containment of the unit is communicated with the first containment of the other unit through a pipeline, the pressure relief device is arranged on the pipeline to control the opening and closing of the pipeline, the preset trigger threshold value of the pressure relief device is positively correlated with the rated design pressure of the first containment, the waste heat discharge device is arranged on the first containment of the unit, and the waste heat discharge device is connected with the first containment to discharge the heat of the first containment.
The passive pressurized water reactor containment pressure relief system provided by the embodiment of the invention has the advantages of flexible configuration, stable operation, low failure risk and the like.
In some embodiments, the pressure relief device comprises a gate valve, a connecting rod and an accumulator tank, wherein the gate valve is positioned in the pipeline, a first end of the connecting rod is connected with the gate valve, a second end of the connecting rod is connected with the accumulator tank, the gate valve is opened to relieve pressure when the pressure in the first containment is greater than a preset trigger threshold, and the gate valve is closed when the pressure in the first containment is less than the preset trigger threshold.
In some embodiments, the accumulator tank includes a sleeve, a sealing ring, and a central baffle, the central baffle is connected to the second end of the connecting rod, the connecting rod drives the central baffle to move in the sleeve along with opening and closing of the gate valve, and the sealing ring is disposed between the central baffle and the sleeve.
In some embodiments, a second containment is disposed between the first containment of the unit and the first containment of the other unit, the second containment being in communication with the first containment of both units via a pipeline.
In some embodiments, the passive pressurized water reactor containment pressure relief system further includes a third containment vessel, wherein the third containment vessel is used as a center, a plurality of first containment vessels and second containment vessels are distributed in a ring shape, the second containment vessels are distributed with the first containment vessels in a staggered manner, the first containment vessel is connected with two adjacent second containment vessels through pipelines, and a plurality of second containment vessels are connected with the third containment vessel through pipelines.
In some embodiments, the triggering threshold of the pressure relief device on the conduit in communication with the second containment vessel is 50% of the rated design pressure of the first containment vessel.
In some embodiments, non-return valves are provided on the lines between the first containment and the adjacent second containment and on the lines between the second containment and the third containment.
In some embodiments, the elevation of the second and/or third containment vessel is 5-15 m below the height of the first containment vessel.
In some embodiments, the waste heat removal device is further disposed on the second containment and the third containment.
In some embodiments, the preset trigger threshold of the pressure relief device is 75% of the rated design pressure of the first containment vessel.
Drawings
Fig. 1 is a schematic structural view of a pressurized water reactor containment pressure relief system according to an embodiment of the present invention.
Fig. 2 is a schematic structural view of a passive pressurized water reactor containment pressure relief system in accordance with another embodiment of the present invention.
Fig. 3 is a schematic structural view of a passive pressurized water reactor containment pressure relief system according to another embodiment of the present invention.
Reference numerals: 1. a first containment vessel; 2. a second containment vessel; 3. a third containment vessel; 4. and the pressure relief device.
Detailed Description
Reference will now be made in detail to embodiments of the present invention, examples of which are illustrated in the accompanying drawings. The embodiments described below by referring to the drawings are illustrative and intended to explain the present invention and should not be construed as limiting the invention.
The coolant and the moderator used in the pressurized water reactor are mainly water (liquid light water), and compared with an LMR liquid metal reactor, the coolant and the moderator have different properties, so that the design mode and the connection mode of a containment are different, and the moderator solid beryllium of the LMR is extremely toxic and is not suitable for being connected by adopting a penetrating piece. The radioactive products released from the pressurized water reactor mainly comprise: the free volume of the containment vessel determines the volume of the containment vessel due to the volume of water, hydrogen, actinides and the like, and the cooling mode can be water-cooled immersed under the condition of a pressurized water reactor accident, unlike a pressurized water reactor, the LMR must rely on external energy sources to operate a waste heat removal system due to sodium water reaction and the like. The pressurized water reactor adopts liquid water as a coolant and a moderator, the operation pressure of a loop system is up to 15.5Mpa, the requirements on rated bearing pressure of a containment and a pressure release part are high, a containment with larger free volume is usually adopted, prestressed steel bars are added, the chemical property of working medium water is relatively stable, and hydrogen generated by water irradiation can be compounded in the containment by using an open flame ignition mode.
As shown in fig. 1 to 3, according to an embodiment of the present invention, the passive pressurized water reactor containment pressure relief system includes at least two units, a pressure relief device 4 and a waste heat discharging device, each unit is correspondingly provided with at least one first containment 1, the first containment 1 of a unit is communicated with the first containment 1 of another unit through a pipeline, the pressure relief device 4 is arranged on the pipeline to control opening and closing of the pipeline, a preset trigger threshold of the pressure relief device 4 is positively correlated with rated design pressure of the first containment 1, the waste heat discharging device is arranged on the first containment 1 of the unit, and the waste heat discharging device is connected with the first containment 1 to discharge heat of the first containment 1. The first safety shells 1 of the two units are standby safety shells, and an accident occurs in one unit, so that the temperature and the pressure in the first safety shells 1 of the accident units rise. When the pressure of the first containment 1 of the accident unit exceeds the preset triggering threshold of the pressure relief device 4, the pressure relief device 4 triggers, high-temperature and high-pressure steam and noncondensable gas in the first containment 1 of the accident unit are discharged into the first containment 1 of the fault-free unit along the pressure gradient, the total volume of the first containment 1 is increased because the two first containment 1 are communicated, the volume change is insufficient to cause obvious change of macroscopic temperature in the large space of the containment according to an ideal gas state equation, the temperature change caused by the volume change is negligible, namely the volume is increased, the pressure is rapidly reduced, and two sets of waste heat removing devices can be simultaneously operated in the subsequent long-term cooling process, heat is respectively led out from the first containment 1 of the two sets of units, the gas phase space temperature in the first containment 1 is reduced, the steam is rapidly condensed into a liquid state, the pressure in the first containment 1 is further reduced, and the purposes of controlling the process and relieving the accident result are achieved. The first containment vessels 1 of the two units are connected to form a double containment vessel pressure relief, so that the double containment vessel pressure relief system is applicable to designed and built nuclear power plants, and the transformation has little influence on daily operation.
The passive pressurized water reactor containment pressure relief system provided by the embodiment of the invention has the advantages of flexible configuration, stable operation, low failure risk and the like.
In some embodiments, the pressure relief device 4 comprises a gate valve, a connecting rod and an accumulator tank, the gate valve is located in the pipeline, a first end of the connecting rod is connected with the gate valve, a second end of the connecting rod is connected with the accumulator tank, the gate valve is opened for pressure relief when the pressure in the first containment vessel 1 is greater than a preset trigger threshold, and the gate valve is closed when the pressure in the first containment vessel 1 is less than the preset trigger threshold.
Specifically, the accumulator tank may be filled with a large amount of nitrogen, and under normal conditions, the pressure in the first containment vessel 1 should be level with or slightly lower than the atmospheric pressure to form a negative pressure zone, which can prevent the radioactive substances from leaking out, at which time the pressure in the first containment vessel 1 is insufficient to push the gate valve, and the pressure relief device 4 remains closed. When the unit is in accident, because a large amount of steam leaks into the first containment vessel 1, the pressure and the temperature of the first containment vessel 1 are obviously increased, at the moment, the sum of the pressure in the pressure accumulation tank and the gravity of the pressure relief device 4 is smaller than the component of the pressure of the first containment vessel 1 in the vertical direction, the pressure relief device 4 triggers and opens a gate valve to perform pressure relief operation, and when the pressure in the first containment vessel 1 is reduced to be lower than a preset trigger threshold along with the progress of pressure relief and insufficient to open the gate valve, the gate valve is closed.
In some embodiments, the accumulator tank includes a sleeve, a sealing ring, and a center baffle connected to the second end of the connecting rod, the connecting rod driving the center baffle to move in the sleeve with the opening and closing of the gate valve, the sealing ring being disposed between the center baffle and the sleeve.
Specifically, the center baffle slides relative telescopic inner wall, and the center baffle is connected with the second end of connecting rod, and the connecting rod drive center baffle removes in order to change the size of sleeve inner space in the sleeve, and when the volume of gas in the sleeve was a bit, along with the removal gas volume reduction of center baffle, the balanced position of center baffle is finally realized in the gas pressure increase, and the sealing washer setting can guarantee sealed effect on the center baffle.
In some embodiments, as shown in fig. 2, a second containment vessel 2 is provided between the first containment vessel 1 of one unit and the first containment vessel 1 of another unit, and the second containment vessel 2 is in communication with the first containment vessels 1 of both units via a pipeline.
Specifically, the first containment 1 of the two units is connected through the second containment 2, the second containment 2 may be an empty containment, after an accident occurs in one unit, the temperature and pressure in the first containment 1 of the accident unit rise, after the pressure in the first containment 1 of the accident unit exceeds the threshold of the pressure relief device 4, the pressure relief device 4 triggers to discharge the high-temperature, high-pressure steam and non-condensable gas in the first containment 1 of the accident unit into the second containment 2 along the pressure gradient, and since the total volume of the containment increases, the change in volume is insufficient to cause a significant change in macroscopic temperature in the large containment space according to the ideal gas state equation, the temperature change due to the change in volume is negligible, i.e. the volume increases, the pressure rapidly decreases, and in the subsequent long-term cooling process, it is optionally determined whether the steam is discharged from the second containment 2 into the first containment 1 of the faultless unit.
In some embodiments, as shown in fig. 3, the passive pressurized water reactor containment pressure relief system further includes a third containment vessel 3, wherein a plurality of first containment vessels 1 and second containment vessels 2 are distributed in a ring shape with the third containment vessel 3 as a center, the second containment vessels 2 are distributed in a staggered manner with respect to the first containment vessel 1, the first containment vessel 1 is connected with two adjacent second containment vessels 2 through a pipeline, and the plurality of second containment vessels 2 are connected with the third containment vessel 3 through a pipeline.
Specifically, the plurality of first containment vessels 1 form an annular array, a third containment vessel 3 is arranged in the middle of the annular array as a public containment vessel for storing and cooling inflammable and explosive gases such as high temperature, high pressure, hydrogen and the like, the second containment vessel 2 is spaced from the first containment vessel 1, and power generation equipment such as a reactor, a steam turbine and the like and safety-related equipment and systems only can be installed in the second containment vessel 2 and the third containment vessel 3. After an accident occurs in one unit, the temperature and pressure in the first containment 1 of the accident unit rise, after the pressure of the first containment 1 of the accident unit exceeds the threshold value of the pressure relief device 4, the pressure relief device 4 triggers, high-temperature and high-pressure steam and non-condensable gases in the first containment 1 of the accident unit are discharged into the second containment 2 along a pressure gradient, and as the total volume of the containment increases, the volume change is insufficient to cause significant change of macroscopic temperature in a large space of the containment according to an ideal gas state equation, so that the temperature change caused by the volume change is negligible, namely the volume increases, the pressure rapidly decreases, and whether the steam is discharged into the third containment 3 from the second containment 2 is determined according to circumstances in the subsequent long-term cooling process. Even if the first containment vessels 1 are in accident, the high-temperature gas can be discharged into the second containment vessel 2 and the third containment vessel 3 to ensure the safety of the nuclear power plant. Preferably, the third containment 3 is used for backup in normal operating conditions of the nuclear power plant, only in case of accident.
In some embodiments, as shown in fig. 2, the triggering threshold of the pressure relief device 4 on the conduit in communication with the second containment vessel 2 is 50% of the rated design pressure of the first containment vessel 1.
Specifically, the pressure relief device 4 adopts a passive trigger design, the pressure of the accumulator tank is equivalent to a preset trigger threshold, and the engineering margin is increased by 10%.
In some embodiments, as shown in fig. 2 and 3, check valves are provided on the lines between the first containment 1 and the adjacent second containment 2 and on the lines between the second containment 2 and the third containment 3.
Specifically, the check valve adopts a shaft seal or air seal design, and under the condition that external energy is not input to change the flowing direction, the flowing direction of air flow is that the first safety shell 1 flows to the second safety shell 2, and the second safety shell 2 flows to the third safety shell 3.
In some embodiments, as shown in fig. 2 and 3, the elevation of the second and/or third containment vessels 2, 3 is 5-15 m below the height of the first containment vessel 1.
Specifically, the first containment 1 is a normal operation containment, and the second containment 2 and the third containment 3 are lower in elevation than the first containment 1 to enable the containment to be distinguished, with external cooling of the second containment 2 and the third containment 3 being directly performed as necessary.
In some embodiments, the waste heat removal means are also provided on the second containment 2 and the third containment 3.
Specifically, the waste heat discharging device can cool the second containment 2 and the third containment 3, and ensure that the heat of the reactor can be smoothly led out even under the accident working condition.
In some embodiments, the second containment vessel 2 and the third containment vessel 3 are directly cooled, the cooling mode includes high-pressure fluid convection flushing, and cooling water such as seawater, fresh water and the like is directly submerged, so that even under accident conditions, heat of the reactor can be smoothly led out, and heat exchange with a final heat trap is smooth.
In some embodiments, the preset trigger threshold of the pressure relief device 4 is 75% of the rated design pressure of the first safety housing 1.
Specifically, the pressure relief device 4 adopts a passive trigger design, the pressure of the accumulator tank is equivalent to a preset trigger threshold, and the engineering margin is increased by 10%.
In the description of the present invention, it should be understood that the terms "center", "longitudinal", "lateral", "length", "width", "thickness", "upper", "lower", "front", "rear", "left", "right", "vertical", "horizontal", "top", "bottom", "inner", "outer", "clockwise", "counterclockwise", "axial", "radial", "circumferential", etc. indicate orientations or positional relationships based on the orientations or positional relationships shown in the drawings are merely for convenience in describing the present invention and simplifying the description, and do not indicate or imply that the device or element being referred to must have a specific orientation, be configured and operated in a specific orientation, and therefore should not be construed as limiting the present invention.
Furthermore, the terms "first," "second," and the like, are used for descriptive purposes only and are not to be construed as indicating or implying a relative importance or implicitly indicating the number of technical features indicated. Thus, a feature defining "a first" or "a second" may explicitly or implicitly include at least one such feature. In the description of the present invention, the meaning of "plurality" means at least two, for example, two, three, etc., unless specifically defined otherwise.
In the present invention, unless explicitly specified and limited otherwise, the terms "mounted," "connected," "secured," and the like are to be construed broadly, and may be, for example, fixedly connected, detachably connected, or integrally formed; may be mechanically connected, may be electrically connected or may be in communication with each other; either directly or indirectly, through intermediaries, or both, may be in communication with each other or in interaction with each other, unless expressly defined otherwise. The specific meaning of the above terms in the present invention can be understood by those of ordinary skill in the art according to the specific circumstances.
In the present invention, unless expressly stated or limited otherwise, a first feature "up" or "down" a second feature may be the first and second features in direct contact, or the first and second features in indirect contact via an intervening medium. Moreover, a first feature being "above," "over" and "on" a second feature may be a first feature being directly above or obliquely above the second feature, or simply indicating that the first feature is level higher than the second feature. The first feature being "under", "below" and "beneath" the second feature may be the first feature being directly under or obliquely below the second feature, or simply indicating that the first feature is less level than the second feature.
For purposes of this disclosure, the terms "one embodiment," "some embodiments," "example," "a particular example," or "some examples," etc., mean that a particular feature, structure, material, or characteristic described in connection with the embodiment or example is included in at least one embodiment or example of the invention. In this specification, schematic representations of the above terms are not necessarily directed to the same embodiment or example. Furthermore, the particular features, structures, materials, or characteristics described may be combined in any suitable manner in any one or more embodiments or examples. Furthermore, the different embodiments or examples described in this specification and the features of the different embodiments or examples may be combined and combined by those skilled in the art without contradiction.
While embodiments of the present invention have been shown and described above, it should be understood that the above embodiments are illustrative and not to be construed as limiting the invention, and that variations, modifications, alternatives, and variations of the above embodiments may be made by those skilled in the art without departing from the scope of the invention.
Claims (10)
1. An passive pressurized water reactor containment pressure relief system, comprising:
At least two units, each unit is correspondingly provided with at least one first containment, and the containment of each unit is communicated with the first containment of the other unit through a pipeline;
the pressure relief device is arranged on the pipeline to control the opening and closing of the pipeline, and a preset trigger threshold value of the pressure relief device is positively related to the rated design pressure of the first containment;
the waste heat discharging device is arranged on the first safety shell of the unit and is connected with the first safety shell to lead out heat of the first safety shell.
2. The passive pressurized water reactor containment pressure relief system of claim 1, wherein the pressure relief device comprises a gate valve, a connecting rod and a pressure accumulation tank, wherein the gate valve is positioned in the pipeline, a first end of the connecting rod is connected with the gate valve, a second end of the connecting rod is connected with the pressure accumulation tank, the gate valve is opened for pressure relief when the pressure in the first containment is greater than a preset trigger threshold, and the gate valve is closed when the pressure in the first containment is less than the preset trigger threshold.
3. The passive pressurized water reactor containment pressure relief system of claim 2, wherein the accumulator tank comprises a sleeve, a seal ring, and a center baffle, the center baffle is connected to the second end of the connecting rod, the connecting rod moves the center baffle within the sleeve as the gate valve opens and closes, and the seal ring is disposed between the center baffle and the sleeve.
4. The passive pressurized water reactor containment pressure relief system of claim 1, wherein a second containment is disposed between a first containment of said unit and a first containment of another said unit, said second containment being in communication with the first containment of both said units via a pipeline.
5. The passive pressurized water reactor containment vessel pressure relief system of claim 4, further comprising a third containment vessel, wherein a plurality of said first containment vessels and said second containment vessels are distributed in a ring shape centered on said third containment vessel, said second containment vessels are distributed in a staggered manner with respect to said first containment vessel, said first containment vessel is connected to two adjacent second containment vessels by a pipeline, and a plurality of said second containment vessels are connected to said third containment vessel by a pipeline.
6. The passive pressurized water reactor containment pressure relief system of claim 5, wherein a trigger threshold of said pressure relief device on a conduit in communication with said second containment vessel is 50% of a rated design pressure of said first containment vessel.
7. The passive pressurized water reactor containment pressure relief system of claim 5, wherein a check valve is disposed on a line between said first containment and an adjacent said second containment and on a line between said second containment and said third containment.
8. The passive pressurized water reactor containment pressure relief system of claim 5, wherein the elevation of said second containment and/or third containment is 5-15 m below the height of said first containment.
9. The passive pressurized water reactor containment pressure relief system of claim 5, wherein said waste heat removal device is further disposed on said second containment and said third containment.
10. The passive pressurized water reactor containment pressure relief system of claim 4, wherein the preset trigger threshold of the pressure relief device is 75% of the rated design pressure of the first containment.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202211312703.9A CN117976261A (en) | 2022-10-25 | 2022-10-25 | Passive pressurized water reactor containment pressure relief system |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202211312703.9A CN117976261A (en) | 2022-10-25 | 2022-10-25 | Passive pressurized water reactor containment pressure relief system |
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| CN117976261A true CN117976261A (en) | 2024-05-03 |
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| CN202211312703.9A Pending CN117976261A (en) | 2022-10-25 | 2022-10-25 | Passive pressurized water reactor containment pressure relief system |
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- 2022-10-25 CN CN202211312703.9A patent/CN117976261A/en active Pending
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