CN105810257A - Pressure release condensation heat transfer system for passive nuclear power station - Google Patents
Pressure release condensation heat transfer system for passive nuclear power station Download PDFInfo
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Abstract
The invention provides a pressure release condensation heat transfer system for a passive nuclear power station. The system includes a steam header connected to a main automatic dropping valve and a closed natural circulation loop; the closed natural circulation loop includes a passive steam condensate heat exchanger, a heat transfer loop pipeline, a passive heat exchanger outside the shell and a heat transfer medium. The steam header is in a containment; the top of the steam header is provided with a steam discharge pipeline; the bottom of steam header is provided with a condensate water discharge pipeline; the heat transfer loop pipeline runs through the steam header and the containment; the passive steam condensate heat exchanger is arranged in the steam header and communicated with the heat transfer loop pipeline; the passive heat exchanger outside the shell is arranged outside the containment and communicates with the heat transfer loop pipeline; and the heat transfer medium absorbs heat from the passive steam condensate heat exchanger and transfers the heat to the passive heat exchanger outside the shell through the heat transfer loop pipeline, thereby establishing the closed natural circulation to facilitate continuous removal of core waste heat produced by core residue fission in the case of an accident.
Description
Technical field
The present invention relates to a kind of heat-exchange system, in particular to a kind of passive nuclear power station pressure release condensation heat exchange system.
Background technology
The nuclear power of safety is the clean energy resource of a kind of high-energy source density, to preserving the ecological environment, readjust the energy structure and ensure that energy security has important effect.But once safety problem occurs in nuclear power station, then staff, nearby residents and ecological environment etc. can be brought huge threat.For this nuclear plant safety problem be people apply nuclear power time must the problem that considers of emphasis.Current nuclear power station tends to adopt non-passive safety technical finesse accident.So-called non-passive safety technology refers to and utilizes natural agent to complete various refrigerating function in the situation of having an accident, and the driving force etc. that wherein natural agent can be produced by gravity, pressure accumulation gas pressure, Natural Circulation produces, it is not necessary to pump and external power source.Therefore, while improve nuclear plant safety reliability, it is greatly simplified the security system of nuclear power station of knowing clearly.
The passive nuclear power station of prior art includes primary heat transport system and the reactor core cooling system (will be described in detail) communicated therewith in specific embodiment part, the reactor core waste heat that reactor core cooling system produces for taking away reactor core remnants in primary heat transport system to fission when having an accident.
It is emphasized that in the prior art, main automatic dropping valve has maximum circulation discharge area, accounts for major portion by its steam produced to residual heat of nuclear core in the primary heat transport system of discharge in containment.This will cause problems with: 1) in containment, pressure will increase, affect the pressure releasing of primary heat transport system in turn, postpone the startup of the main water supply tank gravity water filling to reactor pressure vessel, and now the first water supply tank and the second water supply tank empty substantially, reactor core dangerous period that to be in accident liquid level minimum, pressure release now delays to add the exposed risk of reactor core.nullFor the test of prior art and analytical proof (referring to what within 1999, deliver at " NuclearEngineeringandDesign "、Author is DavidE.Bessette,MarinodiMarzo's and name be called the document of " TransitionfromdepressurizationtolongtermcoolinginAP600sc aledintegraltestfacilities ")，This transition period that main automatic dropping valve is opened between the peace note startup of main water supply tank will appear from reactor core minimum liquid level，Therefore for existing non-passive safety technology，Primary heat transport system pressure reduction after main automatic dropping valve unlatching is the distress phase paid close attention to.2) owing to the containment cooling system of passive nuclear power station is also adopted by passive mode, (cool down water flow by gravity outside such as existing AP1000 technology shell and be able to maintain that 72 hours after the outer cooling water drainage of containment is dry, emergent outside factory after assuming 72 hours electrical source of power can be provided and recover the outer cooling water of shell) the long-term natural cooling stage, steam in containment is condensed by the heat exchange mode that such as can only rely on conduction of heat and natural convection air, and containment keeps sufficient exchange capability of heat to face the challenge for a long time.3) steam condensing reflux being blown off through the pressure release of main automatic dropping valve needs a period of time to melt pit, especially outside containment, cool down deficiency cause that in shell, steam condensation there will be the reduction of melt pit liquid level not in time so that the natural circulation cooling flow-reduction of reactor core.These all will cause reactor core cooling risk.
It is desirable to provide a kind of novel passive nuclear power station pressure release condensation heat exchange system is connected with major loop hot arc through main automatic dropping valve, make through leading steam and the heat no longer gathering in containment that automatic dropping valve is blown off, can effectively reduce pressure in containment, promote that main automatic dropping valve is primary heat transport system pressure release, guarantee that main water supply tank water filling starts in time, alleviate the situation that the cooling of this distress phase reactor core is not enough；Improve post incident simultaneously and fully rely on the limitation of containment long term air cooling；If by steam rapid condensation the melt pit that refluxes, it is possible to effectively keep melt pit to flood liquid level, maintain stable reactor core natural circulation cooling flow, promote the safety of long-term cooling；Thus overcoming the deficiency that the passive safety system of current passive nuclear power station exists.
Summary of the invention
nullOne embodiment of the invention provides a kind of passive nuclear power station pressure release condensation heat exchange system，Wherein passive nuclear power station includes containment and main automatic dropping valve，Main automatic dropping valve connects with the major loop hot arc being connected on reactor pressure vessel，For the steam in the release reaction core pressure vessel when having an accident，Wherein passive nuclear power station pressure release condensation heat exchange system includes arranging the steam header connected with main automatic dropping valve and Guan Bi natural convection loop，Guan Bi natural convection loop includes passive vapor condensation heat-exchange device、Heat-exchanging loop pipeline、The outer passive heat exchanger of shell and heat transferring medium，Wherein steam header is arranged in the containment of passive nuclear power station，The top of steam header is configured with steam header discharge of steam pipeline，The bottom of steam header is configured with the steam header condensed water elimination pipeline being provided with check valve，Heat-exchanging loop pipeline runs through steam header and containment is arranged，Passive vapor condensation heat-exchange device is arranged in steam header and connects with heat-exchanging loop pipeline，The outer passive heat exchanger of shell is arranged on outside containment and connects with heat-exchanging loop pipeline，The outer passive heat exchanger of shell is arranged on higher position relative to passive vapor condensation heat-exchange device，Heat transferring medium in Guan Bi natural convection loop absorbs heat at passive vapor condensation heat-exchange device and transfers heat to the outer passive heat exchanger of shell by heat-exchanging loop pipeline，Thus at passive vapor condensation heat-exchange device、Heat-exchanging loop pipeline、Guan Bi Natural Circulation is established between the outer passive heat exchanger of shell，To continue to take away reactor core remnants to fission generation reactor core waste heat when passive nuclear power station has an accident.
According to the passive nuclear power station pressure release condensation heat exchange system that one embodiment of the invention provides, wherein Guan Bi natural convection loop adopts heat exchange of heat pipe principle, its heat transfer medium can be the mixture of cooling water and steam, Guan Bi natural convection loop is evacuated, when main automatic dropping valve is opened and the steam in reactor pressure vessel is discharged into steam header, the steam that main automatic dropping valve is blown off is discharged in steam header, the steam that main automatic dropping valve is blown off is through passive vapor condensation heat-exchange device, heat transfer medium in passive vapor condensation heat-exchange device is heated and forms condensed water by heat exchange, the steam header condensed water elimination pipeline of the condensed water bottom by being arranged in steam header is discharged in melt pit, thus supplementing cooling water to melt pit, ensure the stability of the long-term cool cycles of reactor core；The water that cools down closed in natural convection loop is heated formation steam when the automatic dropping valve of master is opened and when its temperature exceedes the design temperature starting the Guan Bi Natural Circulation closing natural convection loop at passive vapor condensation heat-exchange device place, steam in Guan Bi natural convection loop flows along heat-exchanging loop pipeline towards the outer passive heat exchanger of shell, heat is discharged into the atmosphere by the outer passive heat exchanger of shell, steam in Guan Bi natural convection loop forms condensed water in the outer passive heat exchanger of shell and relies on gravity to turn again to passive vapor condensation heat-exchange device after cooling, thus establishing Guan Bi Natural Circulation in Guan Bi natural convection loop, the reactor core waste heat produced so that the reactor core remnants continuing when having an accident to take away in reactor pressure vessel fission.
The passive nuclear power station pressure release condensation heat exchange system that another embodiment according to the present invention provides, wherein Guan Bi natural convection loop also includes the outer heat exchange isolating valve of shell, the outer heat exchange isolating valve of shell heat exchange medium flow direction along Guan Bi natural convection loop is arranged between passive vapor condensation heat-exchange device and the outer passive heat exchanger of shell, and the outer heat exchange isolating valve of shell is opened with main automatic dropping valve interlocking；nullWhen main automatic dropping valve is opened and the steam in reactor pressure vessel is discharged into steam header，Steam is through passive vapor condensation heat-exchange device，Heat transferring medium in passive vapor condensation heat-exchange device is heated and forms condensed water by heat exchange，Condensed water is discharged in melt pit by the steam header condensed water elimination pipeline and the check valve being arranged on steam header condensed water elimination pipeline being arranged in the bottom of steam header，In passive vapor condensation heat-exchange device, heated heat transferring medium flows along Guan Bi natural convection loop towards the outer passive heat exchanger of shell，Heat is discharged into the atmosphere by the outer passive heat exchanger of shell，In the outer passive heat exchanger of shell, the heat transferring medium after cooling relies on gravity to turn again to passive vapor condensation heat-exchange device，Thus at passive vapor condensation heat-exchange device、Heat-exchanging loop pipeline、Guan Bi Natural Circulation is established between the outer passive heat exchanger of shell and the outer heat exchange isolating valve of shell，The reactor core waste heat produced so that the reactor core remnants continuing when having an accident to take away in reactor pressure vessel fission.
The passive nuclear power station pressure release condensation heat exchange system that the embodiment above according to the present invention provides, wherein can not draining in containment via the discharge of steam pipeline at steam header top by the incoagulable gas that contains of the steam in the steam of total condensation or steam header in steam header, the heat in containment be discharged into the atmosphere by containment cooling system.
The passive nuclear power station pressure release condensation heat exchange system that the embodiment above according to the present invention provides, wherein passive nuclear power station includes primary heat transport system and the reactor core cooling system communicated therewith, the reactor core waste heat that reactor core cooling system produces for taking away reactor core remnants in primary heat transport system to fission when having an accident.
nullThe passive nuclear power station pressure release condensation heat exchange system that the embodiment above according to the present invention provides，Wherein primary heat transport system includes steam generator、U-tube、Cold section of major loop、Major loop hot arc、Main pump、Reactor pressure vessel、It is positioned at the reactor core of reactor pressure vessel、Surge line piping and manostat，Wherein U-tube is arranged in a vapor generator，The U-tube port of export is through connecting through cold section of main pump and major loop by the cold chamber compartment of steam generator bottom，Cold section of major loop connects with reactor pressure vessel，Reactor pressure vessel connects with major loop hot arc，Major loop hot arc is connected with manostat by Surge line piping and passes through the hot chamber compartment of steam generator bottom and connects with the arrival end of U-tube，Coolant enters reactor pressure vessel by cold section of major loop，Arrive the entrance of reactor core，The Q-value that reactor core produces is taken away when flowing through reactor core，Heated coolant flows through major loop hot arc，Arrive the hot chamber compartment of steam generator bottom and enter the arrival end of U-tube，Transferred heat in steam generator by U-tube and coolant outside U-tube，Coolant temperature in U-tube reduces and collects in the cold chamber compartment of steam generator bottom by the port of export of U-tube，The main pump that coolant in cold chamber compartment connects with cold cavity bottom pumps into cold section of major loop，Turn again to reactor pressure vessel，Form the enclosed cool cycles of primary heat transport system.
nullThe passive nuclear power station pressure release condensation heat exchange system that the embodiment above according to the present invention provides，Wherein reactor core cooling system includes the first water supply tank、Second water supply tank、Main water supply tank、It is arranged in the passive residual heat removal heat exchanger of main water supply tank、Level Four Automatic Depressurization System、Melt pit、Melt pit filter screen、Melt pit reflux pipe and be arranged on the explosive valve on melt pit reflux pipe，First water supply tank、Second water supply tank、Main water supply tank is respectively through corresponding connecting line and is arranged on check valve on each connecting line and is connected with reactor pressure vessel by direct reaction heap peace note pipe，First water supply tank top is connected by cold with major loop section of pressure-equalizing line，So that the pressure in the first water supply tank keeps consistent with the pressure of primary heat transport system，Level Four Automatic Depressurization System includes the automatic dropping valve of the first order、The automatic dropping valve in the second level、The automatic dropping valve of the third level and main automatic dropping valve，The automatic dropping valve of the first order、The automatic dropping valve in the second level、The arrival end of the automatic dropping valve of the third level is connected on manostat with parallel way and the automatic dropping valve of the first order、The automatic dropping valve in the second level、The port of export of the automatic dropping valve of the third level is connected on main water supply tank with parallel way，Main automatic dropping valve connects with major loop hot arc，Cold with major loop section of passive residual heat removal heat exchanger and major loop hot arc connect，Natural Circulation is established between cold section of passive residual heat removal heat exchanger and major loop and major loop hot arc，Reactor pressure vessel is arranged in melt pit，Cooling water in melt pit passes through melt pit reflux pipe、Melt pit filter screen is connected with reactor pressure vessel by direct safety injection pipe with being arranged on melt pit reflux pipe borehole blasting valve.
Passive nuclear power station pressure release condensation heat exchange system according to the present invention has the advantage that 1) can by outside reactor core Residual heat removal containment, effectively reduce the pressurized effect that in containment, steam is assembled, decrease the load of containment cooling system simultaneously, be advantageously implemented cooling down outside shell after water gravity flow drains of containment and rely on cross-ventilated long-term cooling.2) decrease discharge of steam in containment, reduce the back pressure of main automatic dropping valve discharge, be conducive to accelerating to reduce the pressure in pressure vessel, it is ensured that main water supply tank puts into and sustained water injection in time, so that reactor core is in safer flooding and the state of cooling.3) adopt passive vapor condensation heat-exchange device that the steam that main automatic dropping valve gives off is carried out condensation and become condensed water, condensed water returns melt pit by the condensed water elimination pipeline bottom steam box, cooling water is supplemented, it is ensured that long-term melt pit recirculation cooling carries out sustainedly and stably to melt pit.4) the passive nuclear power station pressure release condensation heat exchange system set up is completely isolated with reactor core medium, decreases the risk that radioactivity leaks outside.5) do not change existing passive core cooling system structure, and the passive nuclear power station pressure release condensation heat exchange system of the present invention adopts passive mode, rely on natural agent to drive, keep original passive design concept.
Accompanying drawing explanation
The above and other aspect of the present invention is discussed in detail, in accompanying drawing below in conjunction with accompanying drawing:
Fig. 1 is the passive PIPING OF MAIN LOOPS IN NUCLEAR POWER STATION system schematic of prior art.
Fig. 2 is the sketch of the passive nuclear power station reactor core cooling system of prior art.
Fig. 3 is the sketch of the long-term cool cycles process of melt pit of the passive nuclear power station reactor core cooling system of prior art.
Fig. 4 is the schematic diagram of the passive pressure release condensation heat exchange system according to an embodiment of the invention.
Fig. 5 is the schematic diagram of passive pressure release condensation heat exchange system according to another implementation of the invention.
Parts and label list
| 1 | Reactor core |
| 2 | Reactor pressure vessel |
| 3 | Cold section of major loop |
| 4 | Major loop hot arc |
| 5 | U-tube |
| 6 | Steam generator |
| 7 | The cold chamber compartment of steam generator |
| 8 | The hot chamber compartment of steam generator |
| 9 | Main pump |
| 10 | Surge line piping |
| 11 | Manostat |
| 12 | Main steam pipe |
| 13 | Main steam isolation valve |
| 14 | Passive residual heat removal heat exchanger |
| 15 | First water supply tank |
| 16 | Second water supply tank |
| 17 | Main water supply tank |
| 18 | Direct safety injection pipe |
| 19 | Pressure-equalizing line |
| 20 | The automatic dropping valve of the first order |
| 21 | The automatic dropping valve in the second level |
| 22 | The automatic dropping valve of the third level |
| 23 | Main automatic dropping valve |
| 24 | Melt pit filter screen |
| 25 | Containment |
| 26 | Steam header |
| 27 | Passive vapor condensation heat-exchange device |
| 30 | The outer passive heat exchanger of shell |
| 31 | Heat-exchanging loop pipeline |
| 32 | The outer heat exchange isolating valve of shell |
| 29,51-53 | Check valve |
| 54-55 | Explosive valve |
| 56 | Stop valve |
| 60 | Bubbler |
| 100 | First connecting line |
| 102 | Second connecting line |
| 104 | 3rd connecting line |
| 105 | Melt pit |
| 106 | Melt pit reflux pipe |
| 108 | Steam header discharge of steam pipeline |
| 110 | Steam header condensed water elimination pipeline |
Detailed description of the invention
Fig. 1-Fig. 5 and following description describe the optional embodiment of the present invention to instruct how those of ordinary skill in the art implement and reproduce the present invention.In order to instruct technical solution of the present invention, simplify or eliminated some conventional aspects.It should be understood by one skilled in the art that the modification being derived from these embodiments or replace and will be within the scope of the present invention.It should be understood by one skilled in the art that following characteristics can combine to be formed multiple modification of the present invention in every way.Thus, the invention is not limited in following optional embodiment, and only limited by claim and their equivalent.
Coolant can be such as cooling water in this article.Other coolants being adapted at nuclear power plant system use of refrigerating function can be realized also within the scope of the invention.
Fig. 1 illustrates the primary heat transport system of current passive nuclear power station.nullAs shown in Figure 1，The primary heat transport system of current passive nuclear power station includes steam generator 6、U-tube 5、Major loop cold section 3、Major loop hot arc 4、Main pump 9、Reactor pressure vessel 2、It is positioned at the reactor core 1 of reactor pressure vessel 2、Surge line piping 10 and manostat 11，Wherein U-tube 5 is arranged in steam generator 6，The U-tube port of export is pooled to the cold chamber compartment 7 of steam generator bottom，Cold chamber compartment 7 is connected for cold with major loop section 3 by main pump 9，Major loop connects with reactor pressure vessel 2 for cold section 3，Reactor pressure vessel 2 also connects with major loop hot arc 4，Major loop hot arc 4 is connected with manostat 11 by Surge line piping 10 and passes through the hot chamber compartment 8 of steam generator bottom and connects with the arrival end of U-tube 5，Coolant enters reactor pressure vessel 2 for cold section 3 by major loop，Arrive the entrance of reactor core 1，The Q-value that reactor core produces is taken away when flowing through reactor core 1，Heated coolant (such as temperature is about 321 DEG C) flows through major loop hot arc 4，Arrive the hot chamber compartment 8 of steam generator bottom and enter the arrival end of U-tube 5，The coolant in steam generator 6 and outside U-tube 5 is transferred heat to by U-tube 5，Coolant temperature in U-tube 5 reduces (such as coolant temperature is 280 DEG C) and collects in the cold chamber compartment 7 of steam generator bottom by the port of export of U-tube，In cold chamber compartment, the coolant of 7 pumps into major loop cold section 3 by main pump 9，Turn again to reactor pressure vessel 2，Form the enclosed cool cycles of primary heat transport system.In Fig. 1, arrow F1 is the coolant flow direction that temperature is relatively low, and arrow F2 is that the coolant that temperature is higher flows to.
For the pressure of stable primary heat transport system, major loop hot arc 4 is connected with manostat 11 by Surge line piping 10, is saturated solution and saturated vapor (such as cooling water saturation liquid and saturated vapor), meets the voltage stabilizing requirement of primary heat transport system in manostat 11.Manostat 11 is for maintaining properly functioning high pressure conditions (such as about 15.5MPa) by the pressure of primary heat transport system so that during reactor core 1 reaction in normal operation, the coolant in reactor pressure vessel 2 does not have boiling.The cooling water of reacted heap reactor core 1 heating is when flowing through U-tube 5, transfer heat to the cooling water in steam generator 6 and outside U-tube 5, the cooling water evaporation in steam generator 6 is made to form steam, in steam generator 6, steam passes through main steam pipe 12, it is fed to steam turbine (not shown in figure 1) by normally opened main steam isolation valve 13, drive steam turbine generates electricity, thus the heat that reactor core produces is changed into electric energy.
But; when there is minor break accident in primary heat transport system; although reactor core stopped reaction; but reactor core remnants fission is still continuing; still produce a large amount of waste heat (being such as equivalent to the 1%-6% of normal power); shut down main steam isolation valve 13 simultaneously due to the main pump 9 of now primary heat transport system to close, it is impossible to normally take away reactor core waste heat.Thus, if not starting passive nuclear power station reactor core cooling system, then reactor core will melt and develop into serious accident by overtemperature.
Fig. 2 is the sketch of the passive nuclear power station reactor core cooling system of prior art.The author published by Atomic Energy Press for example, with reference to 2010 be Ouyang give, sincere lattice of woods etc. and name be called the document of " non-passive safety advanced pressurized water reactor nuclear power technology ".As in figure 2 it is shown, the reactor core cooling system of prior art includes the first single storage of water supply tank 15(the cooling water of about 70 tons), the second single storage of water supply tank 16(have the cooling water of about 57 tons and the gas of about 5MPa), main water supply tank 17(storage have the water of about 2100 tons), be arranged in the passive residual heat removal heat exchanger 14 of main water supply tank 17 and bubbler 60, level Four Automatic Depressurization System, melt pit 105, melt pit filter screen 24, melt pit reflux pipe 106 and the explosive valve 55 being arranged on melt pit reflux pipe.First water supply tank the 15, second water supply tank 16, main water supply tank 17 are respectively through first connecting line the 100, second connecting line the 102, the 3rd connecting line 104 and be arranged on the check valve 51-53 on each connecting line and connected with reactor pressure vessel 2 by direct reaction heap peace note pipe 18, wherein the first connecting line 100 can be provided with stop valve 56,3rd connecting line 104 can be provided with explosive valve 54, stop valve 56 and explosive valve 54 and all be used for preventing the improper injection of water tank inner cooling water.nullFirst water supply tank top is connected for cold with major loop section 3 by pressure-equalizing line 19，So that the pressure in the first water supply tank 15 keeps consistent with the pressure of primary heat transport system，Level Four Automatic Depressurization System includes the automatic dropping valve 20 of the first order、The automatic dropping valve 21 in the second level、The automatic dropping valve of the third level 22 and main automatic dropping valve 23，The automatic dropping valve 20 of the first order、The automatic dropping valve 21 in the second level、The arrival end of the automatic dropping valve of the third level 22 is connected on manostat 11 with parallel way and by automatic for first order dropping valve 20、The automatic dropping valve 21 in the second level、The port of export of the automatic dropping valve of the third level 22 is connected to parallel way on the bubbler 60 being positioned in main water supply tank 17，Main automatic dropping valve 23 connects with major loop hot arc 4，Cold with major loop section of 3(is not shown for passive residual heat removal heat exchanger 14) and major loop hot arc 4 connect，Coolant density difference is relied on to establish Natural Circulation between passive residual heat removal heat exchanger 14 and major loop cold section 3 and major loop hot arc 4.Reactor pressure vessel 2 is arranged in melt pit 105, and the cooling water in melt pit 105 connects by melt pit reflux pipe 106, melt pit filter screen 24 and the explosive valve 55 being arranged in melt pit reflux pipe and by direct safety injection pipe 18 with reactor pressure vessel 2.
Usual minor break accident process includes five typical stages: 1) underheat blowdown phase；2) the saturated Natural Circulation stage；3) dropping valve triggers buck stage automatically；4) the main water supply tank gravity safety injection stage；And 5) long-term melt pit recirculation cooling stage.
At underheat blowdown phase, the cooling water in primary heat transport system spurts from cut to containment, and the pressure in reactor pressure vessel 2 declines.Cooling water in primary heat transport system reduces, and causes that the water level in manostat 11 reduces, and will trigger shutdown and safety signal, reactor core 1 stopped reaction, and main pump 9 is shut down, and the main steam isolation valve 13 on the main steam pipe 12 of steam generator 6 outlet is closed.Stop valve 56 is opened simultaneously, and passive residual heat removal heat exchanger 14 and the first water supply tank 15 rely on natural driving force to put into operation.
In the saturated blowdown Natural Circulation stage, the Pressure Drop in reactor pressure vessel 2 is low to moderate primary heat transport system saturation pressure (as 7.6MPa), Gas-liquid two-phase flow occurs in reactor pressure vessel 2.Coolant density difference is relied on to establish Natural Circulation between passive residual heat removal heat exchanger 14, major loop hot arc 4 and major loop cold section 3.Meanwhile, the first water supply tank 15 relies on gravity connect pipeline 100 and the check valve 51 being disposed thereon via first and inject cooling water by direct safety injection pipeline 18 in reactor pressure vessel 2.
Automatic blood pressure lowering triggers buck stage and refers to when water level is reduced to the first level set value in the first water supply tank 15 (such as the liquid level of 75% volume in corresponding to the first water supply tank 15), the automatic dropping valve 20 of the first order will be triggered, after the time delay set, open the automatic dropping valve in the second level 21 and the automatic dropping valve 22 of the third level successively.The triggering of the automatic dropping valve of the first order 20, the automatic dropping valve in the second level 21 and the automatic dropping valve of the third level 22 causes that the pressure in reactor pressure vessel 2 accelerates to decline (as rapidly dropped to about 0.5MPa from about 7.6MPa), when primary heat transport system pressure is lower than the pressure accumulation gas pressure in the second water supply tank 16 (such as the about 5MPa of pressure accumulation nitrogen pressure), the cooling water in the second water supply tank 16 connects pipeline 102 and the check valve 52 being disposed thereon through second and injects cooling water by direct safety injection pipeline 18 to reactor pressure vessel under gas pressure drives.When, after the second water supply tank 16 emptying, the first water supply tank 15 continues to inject cooling water to reactor pressure vessel.When the water level decreasing in the first water supply tank 15 to the second level set value (such as the liquid level of 25% volume in corresponding to the first water supply tank 15), by main for triggering automatic dropping valve 23, will further decrease the pressure in reactor pressure vessel 2 (as being further reduced to less than about 0.1MPa) from about 0.5MPa.
The main water supply tank 17 gravity safety injection stage refers to when the pressure in reactor pressure vessel 2 is discharged by main automatic dropping valve 23 and is reduced to close to atmospheric pressure, cooling water in main water supply tank 17 (is had about 10m liquid level, corresponding to about 0.1MPa pressure head) and relies on gravity and via the 3rd connecting line 104 and the check valve 53 being disposed therein and injected to reactor pressure vessel 2 by direct safety injection pipeline 18 and cool down water.When the water level in main water supply tank is reduced to three-tank the first level set value (such as the overall height liquid level of main water supply tank 40%), main water supply tank 17 is by the explosive valve 55 before unlatching melt pit filter screen 24, main water supply tank 17 utilizes gravity to discharge water and cleans melt pit filter screen, it is prevented that the backflow of imminent melt pit blocks at melt pit filter screen place.When in melt pit liquid level raise due to UNICOM's water filling of main water supply tank 17 reach melt pit liquid level concordant with the liquid level of main water supply tank 17 time, the cooling of melt pit long-term recirculation will be set up.
Fig. 3 is the sketch of the long-term cool cycles process of melt pit of the passive nuclear power station reactor core cooling system of prior art.Can be described as: pass through in melt pit filter screen 24, melt pit reflux pipeline 106 and the explosive valve 55 piii reactor pressure vessel 2 that is arranged on melt pit reflux pipeline under the effect of the driving force that the cooling water collected in melt pit is formed at density contrast, more than reactor core, thermogenetic steam discharges to containment through main automatic dropping valve 23, establish Natural Circulation, and the steam in containment is cooled down by containment cooling system, condensed water to melt pit, supplements cooling water to melt pit at containment internal reflux.By such endless form, reactor core waste heat is passed to as the ambient atmosphere outside the containment of ultimate heat sink, keep reactor core to continue to cool down, it is prevented that reactor core overtemperature melts and develops even more serious accident.
It is desirable to provide a kind of passive nuclear power station pressure release condensation heat exchange system, to overcome the deficiency of passive nuclear power station reactor core cooling system in prior art.
Fig. 1 is the PIPING OF MAIN LOOPS IN NUCLEAR POWER STATION system schematic of prior art.Fig. 4 is the schematic diagram of the passive pressure release condensation heat exchange system according to an embodiment of the invention.As shown in Figure 1 and Figure 4, passive nuclear power station includes containment 25 and main automatic dropping valve 23, and main automatic dropping valve 23 connects with the major loop hot arc 4 being connected on reactor pressure vessel, for the steam in release reaction core pressure vessel when having an accident.
Fig. 4 is the schematic diagram of the passive pressure release condensation heat exchange system according to an embodiment of the invention.nullAs shown in Figure 4，Passive nuclear power station pressure release condensation heat exchange system includes the steam header 26 and the Guan Bi natural convection loop that connect with main automatic dropping valve 23，Guan Bi natural convection loop includes passive vapor condensation heat-exchange device 27、Heat-exchanging loop pipeline 31、The outer passive heat exchanger 30 of shell、The outer heat exchange isolating valve 32 of shell and heat transfer medium，Wherein steam header 26 is arranged in the containment 25 of passive nuclear power station，The top of steam header is configured with steam header discharge of steam pipeline 108，The bottom of steam header is configured with the steam header condensed water elimination pipeline 110 being provided with check valve 29，Heat-exchanging loop pipeline 31 runs through steam header 26 and containment 25 is arranged，Passive vapor condensation heat-exchange device 27 is arranged in steam header 26 and connects with heat-exchanging loop pipeline 31，The outer passive heat exchanger 30 of shell is arranged on outside containment 25 and connects with heat-exchanging loop pipeline 31，The outer passive heat exchanger 30 of shell is arranged on higher position relative to passive vapor condensation heat-exchange device 27，The outer heat exchange isolating valve 32 of shell heat transfer medium (such as cooling water) flow direction along Guan Bi natural convection loop is arranged between passive vapor condensation heat-exchange device 27 and the outer passive heat exchanger 30 of shell，The outer heat exchange isolating valve 32 of shell is opened with main automatic dropping valve 23 interlocking.
When main automatic dropping valve 23 is opened and the steam in reactor pressure vessel 2 is discharged into steam header 26, the steam that main automatic dropping valve 23 is blown off is discharged in steam header 26 along the direction pointed by arrow F3, steam is through passive vapor condensation heat-exchange device 27, heat transfer medium in passive vapor condensation heat-exchange device is heated and forms condensed water by heat exchange, condensed water is discharged in melt pit 105 by the steam header condensed water elimination pipeline 110 and the check valve 29 being arranged on steam header condensed water elimination pipeline being arranged in the bottom of steam header, thus supplementing cooling water to melt pit 105, ensure the stability of the long-term cool cycles of reactor core.
In passive vapor condensation heat-exchange device 27, heated heat transfer medium flows along heat-exchanging loop pipeline 31 towards the outer passive heat exchanger 30 of shell, heat is discharged into the atmosphere by the outer passive heat exchanger 30 of shell, in the outer passive heat exchanger of shell, the heat transfer medium after cooling relies on gravity to turn again to passive vapor condensation heat-exchange device 27, thus at passive vapor condensation heat-exchange device 27, heat-exchanging loop pipeline 31, the outer passive heat exchanger 30 of shell, Guan Bi Natural Circulation is established between the outer heat exchange isolating valve 32 of shell, the reactor core waste heat produced so that the reactor core remnants continuing when having an accident to take away in reactor pressure vessel fission.
Can not drain in containment via the discharge of steam pipeline 108 at steam header top by the gas of incoagulability that contains of the steam in the steam of total condensation or steam header in steam header 26, in containment 25, carried out condensation by containment cooling system again and form condensed water, condensed water falls into melt pit, and supplement cooling water to melt pit 105, maintain melt pit and flood liquid level absolute altitude, it is ensured that the stability of the long-term cool cycles of reactor core.Heat in containment is discharged in the ambient atmosphere outside containment by containment cooling system.
Fig. 1 is the PIPING OF MAIN LOOPS IN NUCLEAR POWER STATION system schematic of prior art.Fig. 5 is the schematic diagram of passive pressure release condensation heat exchange system according to another implementation of the invention.As shown in Figure 1 and Figure 5, passive nuclear power station includes containment 25 and main automatic dropping valve 23, and main automatic dropping valve 23 connects with the major loop hot arc 4 being connected on reactor pressure vessel, for the steam in release reaction core pressure vessel when having an accident.
Fig. 5 is the schematic diagram of passive pressure release condensation heat exchange system according to another implementation of the invention.nullAs shown in Figure 5，Passive nuclear power station pressure release condensation heat exchange system includes the steam header 26 and the Guan Bi natural convection loop that connect with main automatic dropping valve 23，Guan Bi natural convection loop includes passive vapor condensation heat-exchange device 27、Heat-exchanging loop pipeline 31、The outer passive heat exchanger 30 of shell and heat transfer medium，Wherein steam header 26 is arranged in the containment 25 of passive nuclear power station，The top of steam header is configured with steam header discharge of steam pipeline 108，The bottom of steam header is configured with the steam header condensed water elimination pipeline 110 being provided with check valve 29，Heat-exchanging loop pipeline 31 runs through steam header 26 and containment 25 is arranged，Passive vapor condensation heat-exchange device 27 is arranged in steam header 26 and connects with heat-exchanging loop pipeline 31，The outer passive heat exchanger 30 of shell is arranged on outside containment 25 and connects with heat-exchanging loop pipeline 31.In this embodiment shown in Fig. 5, when the heat transfer medium in Guan Bi natural convection loop is the mixture including cooling water and steam (can contain antifreezing agent if desired), Guan Bi natural convection loop is evacuated (being such as 0.475 absolute atmosphere).
When main automatic dropping valve 23 is opened and the steam in reactor pressure vessel 2 is discharged into steam header 26, the steam that main automatic dropping valve 23 is blown off is discharged in steam header 26 along the direction pointed by arrow F3, steam is through passive vapor condensation heat-exchange device 27, heat transfer medium in passive vapor condensation heat-exchange device (is such as cooled down water, antifreezing agent can be contained if desired) it is heated and forms condensed water by heat exchange, condensed water is discharged in melt pit 105 by the steam header condensed water elimination pipeline 110 and the check valve 29 being arranged on steam header condensed water elimination pipeline being arranged in the bottom of steam header, thus supplementing cooling water to melt pit 105, ensure the stability of the long-term cool cycles of reactor core.
nullCooling water in Guan Bi natural convection loop is heated at passive vapor condensation heat-exchange device 27 place when main automatic dropping valve 23 is opened and when its temperature exceedes design temperature (being such as 80 degrees Celsius) starting the Guan Bi Natural Circulation closing natural convection loop forms steam，Steam in Guan Bi natural convection loop flows along heat-exchanging loop pipeline 31 towards the outer passive heat exchanger 30 of shell，Heat is discharged into the atmosphere by the outer passive heat exchanger 30 of shell，Steam in Guan Bi natural convection loop forms condensed water in the outer passive heat exchanger 30 of shell and relies on gravity to turn again to passive vapor condensation heat-exchange device 27 after cooling，Thus establishing Guan Bi Natural Circulation in Guan Bi natural convection loop，The reactor core waste heat produced so that the reactor core remnants continuing when having an accident to take away in reactor pressure vessel fission.
Can not drain in containment via the discharge of steam pipeline 108 at steam header top by the gas of incoagulability that contains of the steam in the steam of total condensation or steam header in steam header 26, condensed in containment 25 by containment cooling system again, condensed water falls into melt pit, and supplement cooling water to melt pit 105, maintain melt pit and flood liquid level absolute altitude, it is ensured that the stability of the long-term cool cycles of reactor core.Heat in containment is discharged in the ambient atmosphere outside containment by containment cooling system.
It is pointed out that in the such as embodiment shown in Fig. 5 and Fig. 4, in order to ensure the mode that discharge of steam and condensate water discharging timely, discharge pipe line 108 and flowing line 110 can adopt many pipelines in parallel.Additionally, discharge pipe line 108 and flowing line 110 also can adopt other possible embodiments, and this also will in protection scope of the present invention.
It is to be noted, in the such as embodiment shown in Fig. 5 and Fig. 4, passive nuclear power station pressure release condensation heat exchange system for guaranteeing the present invention can normal operation, the passive nuclear power station pressure release condensation heat exchange system of the present invention can adopt the conventional design of antifreeze, incoagulable gas (such as air) aerofluxus etc., and they are not repeated herein as prior art.The mode of the Natural Circulation heat exchange relative to Fig. 4, it is stably rapid that the Natural Circulation heat exchange mode of Fig. 5 has heat conduction by gravity heat pipe heat exchanger principle, and the outer cooler of shell is without the special high-order advantage disposing requirement.For the thermal discharge efficiency of the outer passive heat exchanger of stiffened shell, the hyperbolic-type air cooling tower form of existing mature technology can be adopted.
Passive nuclear power station pressure release condensation heat exchange system according to the present invention has the advantage that 1) can by outside reactor core Residual heat removal containment, effectively reduce the pressurized effect that in containment, steam is assembled, decrease the load of containment cooling system simultaneously, be advantageously implemented cooling down outside shell after water gravity flow drains of containment and rely on cross-ventilated long-term cooling.2) adopt passive vapor condensation heat-exchange device that the steam that main automatic dropping valve gives off is carried out condensation and become condensed water, condensed water returns melt pit by the condensed water elimination pipeline bottom steam box, cooling water is supplemented, it is ensured that long-term melt pit recirculation cooling carries out sustainedly and stably to melt pit.3) decrease discharge of steam in containment, reduce the back pressure of main automatic dropping valve discharge, be conducive to accelerating to reduce the pressure in pressure vessel, it is ensured that main water supply tank puts into and sustained water injection in time, so that reactor core is in safer flooding and the state of cooling.4) the passive nuclear power station pressure release condensation heat exchange system set up is completely isolated with reactor core medium, decreases the risk that radioactivity leaks outside.5) do not change existing passive core cooling system structure, and the passive nuclear power station pressure release condensation heat exchange system of the present invention adopts passive mode, rely on natural agent to drive, keep original passive design concept.
Claims (7)
- null1. a passive nuclear power station pressure release condensation heat exchange system，Wherein passive nuclear power station includes containment and main automatic dropping valve，Main automatic dropping valve connects with the major loop hot arc being connected on reactor pressure vessel，For the steam in the release reaction core pressure vessel when having an accident，It is characterized in that，Passive nuclear power station pressure release condensation heat exchange system includes the steam header and the Guan Bi natural convection loop that are arranged to connect with main automatic dropping valve，Guan Bi natural convection loop includes passive vapor condensation heat-exchange device、Heat-exchanging loop pipeline、The outer passive heat exchanger of shell and heat transferring medium，Wherein steam header is arranged in the containment of passive nuclear power station，The top of steam header is configured with steam header discharge of steam pipeline，The bottom of steam header is configured with the steam header condensed water elimination pipeline being provided with check valve，Heat-exchanging loop pipeline runs through steam header and containment is arranged，Passive vapor condensation heat-exchange device is arranged in steam header and connects with heat-exchanging loop pipeline，The outer passive heat exchanger of shell is arranged on outside containment and connects with heat-exchanging loop pipeline，The outer passive heat exchanger of shell is arranged on higher position relative to passive vapor condensation heat-exchange device，Heat transferring medium in Guan Bi natural convection loop absorbs heat at passive vapor condensation heat-exchange device and transfers heat to the outer passive heat exchanger of shell by heat-exchanging loop pipeline，Thus at passive vapor condensation heat-exchange device、Heat-exchanging loop pipeline、Guan Bi Natural Circulation is established between the outer passive heat exchanger of shell，To continue to take away reactor core remnants to fission generation reactor core waste heat when passive nuclear power station has an accident.
- null2. passive nuclear power station pressure release condensation heat exchange system as claimed in claim 1，It is characterized in that，The mixture that heat transfer medium is cooling water and steam in Guan Bi natural convection loop，Guan Bi natural convection loop is evacuated，When main automatic dropping valve is opened and the steam in reactor pressure vessel is discharged into steam header，The steam that main automatic dropping valve is blown off is discharged in steam header，The steam that main automatic dropping valve is blown off is through passive vapor condensation heat-exchange device，Heat transfer medium in passive vapor condensation heat-exchange device is heated and forms condensed water by heat exchange，Condensed water is discharged in melt pit by the steam header condensed water elimination pipeline and the check valve being arranged on steam header condensed water elimination pipeline being arranged in the bottom of steam header，Thus supplementing cooling water to melt pit，Ensure the stability of the long-term cool cycles of reactor core；The water that cools down closed in natural convection loop is heated formation steam when the automatic dropping valve of master is opened and when its temperature exceedes the design temperature starting the Guan Bi Natural Circulation closing natural convection loop at passive vapor condensation heat-exchange device place, steam in Guan Bi natural convection loop flows along heat-exchanging loop pipeline towards the outer passive heat exchanger of shell, heat is discharged into the atmosphere by the outer passive heat exchanger of shell, steam in Guan Bi natural convection loop forms condensed water in the outer passive heat exchanger of shell and relies on gravity to turn again to passive vapor condensation heat-exchange device after cooling, thus establishing Guan Bi Natural Circulation in Guan Bi natural convection loop, the reactor core waste heat produced so that the reactor core remnants continuing when having an accident to take away in reactor pressure vessel fission.
- 3. passive nuclear power station pressure release condensation heat exchange system as claimed in claim 1, it is characterized in that, Guan Bi natural convection loop also includes the outer heat exchange isolating valve of shell, the outer heat exchange isolating valve of shell heat exchange medium flow direction along Guan Bi natural convection loop is arranged between passive vapor condensation heat-exchange device and the outer passive heat exchanger of shell, and the outer heat exchange isolating valve of shell is opened with main automatic dropping valve interlocking；nullWhen main automatic dropping valve is opened and the steam in reactor pressure vessel is discharged into steam header，Steam is through passive vapor condensation heat-exchange device，Heat transferring medium in passive vapor condensation heat-exchange device is heated and forms condensed water by heat exchange，Condensed water is discharged in melt pit by the steam header condensed water elimination pipeline and the check valve being arranged on steam header condensed water elimination pipeline being arranged in the bottom of steam header，In passive vapor condensation heat-exchange device, heated heat transferring medium flows along Guan Bi natural convection loop towards the outer passive heat exchanger of shell，Heat is discharged into the atmosphere by the outer passive heat exchanger of shell，In the outer passive heat exchanger of shell, the heat transferring medium after cooling relies on gravity to turn again to passive vapor condensation heat-exchange device，Thus at passive vapor condensation heat-exchange device、Heat-exchanging loop pipeline、Guan Bi Natural Circulation is established between the outer passive heat exchanger of shell and the outer heat exchange isolating valve of shell，The reactor core waste heat produced so that the reactor core remnants continuing when having an accident to take away in reactor pressure vessel fission.
- 4. passive nuclear power station pressure release condensation heat exchange system as claimed in claim 1, it is characterized in that, can not draining in containment via the discharge of steam pipeline at steam header top by the gas of incoagulability that contains of the steam in the steam of total condensation or steam header in steam header, the heat in containment be discharged into the atmosphere by containment cooling system.
- 5. passive nuclear power station pressure release condensation heat exchange system as claimed in claim 1, it is characterized in that, passive nuclear power station includes primary heat transport system and the reactor core cooling system communicated therewith, the reactor core waste heat that reactor core cooling system produces for taking away reactor core remnants in primary heat transport system to fission when having an accident.
- null6. passive nuclear power station pressure release condensation heat exchange system as claimed in claim 5，It is characterized in that，Primary heat transport system includes steam generator、U-tube、Cold section of major loop、Major loop hot arc、Main pump、Reactor pressure vessel、It is positioned at the reactor core of reactor pressure vessel、Surge line piping and manostat，Wherein U-tube is arranged in a vapor generator，The U-tube port of export is through connecting through cold section of main pump and major loop by the cold chamber compartment of steam generator bottom，Cold section of major loop connects with reactor pressure vessel，Reactor pressure vessel connects with major loop hot arc，Major loop hot arc is connected with manostat by Surge line piping and passes through the hot chamber compartment of steam generator bottom and connects with the arrival end of U-tube，Coolant enters reactor pressure vessel by cold section of major loop，Arrive the entrance of reactor core，The Q-value that reactor core produces is taken away when flowing through reactor core，Heated coolant flows through major loop hot arc，Arrive the hot chamber compartment of steam generator bottom and enter the arrival end of U-tube，Transferred heat in steam generator by U-tube and coolant outside U-tube，Coolant temperature in U-tube reduces and collects in the cold chamber compartment of steam generator bottom by the port of export of U-tube，The main pump that coolant in cold chamber compartment connects with cold cavity bottom pumps into cold section of major loop，Turn again to reactor pressure vessel，Form the enclosed cool cycles of primary heat transport system.
- null7. passive nuclear power station pressure release condensation heat exchange system as claimed in claim 5，It is characterized in that，Reactor core cooling system includes the first water supply tank、Second water supply tank、Main water supply tank、It is arranged in the passive residual heat removal heat exchanger of main water supply tank、Level Four Automatic Depressurization System、Melt pit、Melt pit filter screen、Melt pit reflux pipe and be arranged on the explosive valve on melt pit reflux pipe，First water supply tank、Second water supply tank、Main water supply tank is respectively through corresponding connecting line and is arranged on check valve on each connecting line and is connected with reactor pressure vessel by direct reaction heap peace note pipe，First water supply tank top is connected by cold with major loop section of pressure-equalizing line，So that the pressure in the first water supply tank keeps consistent with the pressure of primary heat transport system，Level Four Automatic Depressurization System includes the automatic dropping valve of the first order、The automatic dropping valve in the second level、The automatic dropping valve of the third level and main automatic dropping valve，The automatic dropping valve of the first order、The automatic dropping valve in the second level、The arrival end of the automatic dropping valve of the third level is connected on manostat with parallel way and the automatic dropping valve of the first order、The automatic dropping valve in the second level、The port of export of the automatic dropping valve of the third level is connected on main water supply tank with parallel way，Main automatic dropping valve connects with major loop hot arc，Cold with major loop section of passive residual heat removal heat exchanger and major loop hot arc connect，Natural Circulation is established between cold section of passive residual heat removal heat exchanger and major loop and major loop hot arc，Reactor pressure vessel is arranged in melt pit，Cooling water in melt pit passes through melt pit reflux pipe、Melt pit filter screen is connected with reactor pressure vessel by direct safety injection pipe with being arranged on melt pit reflux pipe borehole blasting valve.
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