CN202549319U - Diverse safety system specially arranged for nuclear reactor - Google Patents
Diverse safety system specially arranged for nuclear reactor Download PDFInfo
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- CN202549319U CN202549319U CN2012200721463U CN201220072146U CN202549319U CN 202549319 U CN202549319 U CN 202549319U CN 2012200721463 U CN2012200721463 U CN 2012200721463U CN 201220072146 U CN201220072146 U CN 201220072146U CN 202549319 U CN202549319 U CN 202549319U
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- 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
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Abstract
The utility model aims to provide a diverse safety system specially arranged for a nuclear reactor, which comprises a loop non-dynamic waste heat discharging subsystem, a secondary side non-dynamic waste heat discharging subsystem for a steam generator for injecting water relying on gravity, a full-pressure dynamic waste heat discharging subsystem, a low-pressure non-dynamic safe injecting subsystem and a water flooding and air-cooling combined non-dynamic containment cooling subsystem, wherein all the subsystems can independently run or match with each other; complete waste heat discharging channels which are parallel, redundant and diverse in principle are established between a reactor core and a last heat pit; a main reactor system and the reactor core are quickly and efficiently cooled; the reactor can quickly enter into safe state at the initial stage of an accident; and even if one subsystem is in fault, the other subsystems still can supply a complete effective waste heat discharging function, so as to ensure the effective cooling of the reactor.
Description
Technical field
The utility model relates to the reactor safety facility, is specifically related to the engineered safety system that a kind of principle is various, the heat transfer channel is various.
Background technology
The reactor engineered safety system is the important means of protective reaction heap safety, and discharging residual heat of nuclear core is one of most important functions of engineered safety system.Under the situation of having an accident, through the input of engineered safety system, discharge residual heat of nuclear core, keep the cooling of reactor core and the cooling of containment, thereby alleviate damage sequence.Engineered safety system can be divided into active security system and non-active security system according to its operation logic.Active security system is an active system, and its operation needs power supply and pump that power is provided; The operation of passive safety system relies on measures such as Natural Circulation or segregation drive, does not need external impetus.
In two generation nuclear power plants, adopted active engineered safety system mostly; Comprise mainly that such as existing a kind of engineered safety system auxiliary feedwater system, shutdown cooling system, safety injection system (or are called emergence core stacking cool system; Comprise high, medium and low voltage safety injection subsystem), containment spray system etc.; See Fig. 1, in Fig. 1, Reference numeral 1 indicates reactor pressure vessel; Reference numeral 2 indicates voltage stabilizer; Reference numeral 3 indicates steam generator; Reference numeral 4 indicates trunk line; Reference numeral 5 indicates containment; Reference numeral 6 indicates peace and annotates case; Reference numeral 7 indicates melt pit; Reference numeral 8 indicates material-changing water tank; Reference numeral 9 indicates the emergency feedwater case; Reference numeral 10 indicates high-pressure safety injection pump; Reference numeral 11 indicates the low pressure safety injection pump; Reference numeral 12 indicates the emergency feedwater pump; Reference numeral 13 indicates spray pump.In general, under non-cut accident conditions, discharge residual heat of nuclear core through auxiliary feedwater system, shutdown cooling system successively; Under the cut accident conditions, pass through high, medium and low voltage safety injection subsystem successively to the reactor water filling, keep reactor core to continue and can cool off; A loop high temperature fluid that is discharged in the containment obtains cooling through containment spray system.
In some three generations nuclear power plant, adopted passive safety system; Passive safety system such as AP1000 nuclear power plant mainly comprises passive residual heat discharge system, non-active safety injection system (comprising high, medium and low voltage peace notes), non-passive safety shell cooling system; See Fig. 2; In Fig. 2, Reference numeral 1 indicates reactor pressure vessel; Reference numeral 2 indicates peace and annotates case; Reference numeral 3 indicates the reactor core water supply tank; Reference numeral 4 indicates built-in material-changing water tank; Reference numeral 5 indicates passive residual heat and discharges heat interchanger; Reference numeral 6 indicates automatic relief valve; Reference numeral 7 indicates containment; Reference numeral 8 indicates the containment cooling water tank; Reference numeral 9 indicates voltage stabilizer.AP1000 nuclear power plant is discharged into built-in material-changing water tank through the passive residual heat system that discharges with residual heat of nuclear core under non-cut accident conditions; Under the cut accident conditions, carry out non-active peace and annotate through reactor core water supply tank, peace notes case, built-in material-changing water tank successively; Non-passive safety shell cooling system is through the spray cooling metal containment outer wall of cooling pond, top, and the feasible interior loop steam of containment that is discharged into is in the condensation of containment inwall.
Passive safety system in the three generations nuclear power plant does not need external impetus with respect to the active security system in the two generation nuclear power plants at operational process, and its reliability is higher, helps improving the security of reactor.
In addition; Application number is that the one Chinese patent application of 201020227239.X discloses a kind of security system that is used to guarantee nuclear plant safety; It mainly comprises peace notes subsystem and containment cooling subsystem; The setting of its peace notes subsystem and the safety injection system of AP1000 are basic identical, and the containment cooling subsystem is to carry out the containment cooling through the spray pond being set at the containment inner top and in the containment bottom melt pit endothermic water tank being set.
Application number is that 201110118541.0 Chinese patent discloses a kind of reactor safety system; Its principal character is that inside and outside two-layer containment is set; Between two-layer containment, store chilled water; Under the accident conditions, chilled water injection pressure container, heap chamber, steam generator or be sprayed onto in the containment are cooled off.
Application number is that 201110037705.7 one Chinese patent application discloses a kind of nuclear power station non-active and the engineered safety system that actively combines, and it comprises that mainly non-active high pressure reactor core water supply tank, peace annotate case, low pressure safety injection pump, material-changing water tank, secondary side passive residual heat discharge heat exchanger, steam condensate (SC) case, containment spray system, non-active heap chamber waterflood system etc.The cooling in its reactor core and a loop is to discharge heat exchanger through the steam generator secondary side passive residual heat residual heat of nuclear core is discharged in the containment; Safety injection system comprises the high, medium and low voltage peace to be annotated, and it is active that wherein high, middle pressure peace is annotated right and wrong, and it is active that the low pressure peace is annotated; Containment cooling system is active.
Engineered safety system in above-mentioned three patented claims is the various combination scheme of the various reactor core types of cooling and the containment type of cooling; Its main low-temperature receiver is in the containment or the outer chilled water that stores of containment; But reality is not set up from reactor core and is discharged channel to ultimate heat sink passive residual heat (environment), permanently effective; Therefore the infinitely operation of continuous and effective of this type systematic can not be through the long-term safety of non-enabling fashion maintenance reactor.
The utility model content
The purpose of the utility model is to provide a kind of diversified engineered safety system that is used for nuclear reactor; Between reactor core and ultimate heat sink, set up multiple redundancy arranged side by side, the various complete waste heat discharge channel of principle; And have and continue the ability that waste heat is discharged in unlimited operation, the security that further improves reactor.
For realizing the diversified engineered safety system that is used for nuclear reactor of said purpose; Be characterized in; Comprise that a loop passive residual heat is discharged subsystem, dependence gravity injects the steam generator secondary side passive residual heat that feeds water and discharges the non-passive safety shell cooling subsystem that the active waste heat of subsystem, total head is discharged subsystem, the non-active peace notes of low pressure subsystem, water logging and air-cooled combination; Wherein
This steam generator secondary side passive residual heat is discharged subsystem and is comprised steam generator and non-active feed-tank; This non-active feed-tank is arranged on outside the containment; Respectively corresponding feed pipe and the steam pipe through pipeline and valve and steam generator secondary side in its bottom and the top complete loop of formation of connecting; This non-active feed-tank absolute altitude is higher than the position of steam generator; Feedwater in the non-active feed-tank can absorb the heat of the reactor coolant that is transmitted by primary side of steam generator through the secondary side of gravity steam in jection generator, thus cooled reactor;
The active waste heat of this total head is discharged subsystem and is arranged in the containment; Comprise ebullator, heat interchanger; Through pipeline and valve the entrance and exit of heat interchanger, ebullator, pressure vessel is concatenated into the closed cycle loop; This loop stream designs for total head through pipeline and equipment, and promptly design pressure is identical with the reactor main system;
The non-active peace of this low pressure is annotated subsystem and is arranged in the containment; Comprise automatic dropping valve, built-in low-temperature receiver and safety injection pipeline; Automatically dropping valve is connected the outlet of pressure vessel; Built-in low-temperature receiver is connected to the inlet of pressure vessel through safety injection pipeline and valve, and the cooling medium of capacity is housed in the built-in low-temperature receiver, and its absolute altitude is higher than pressure vessel; Cooling medium in the built-in low-temperature receiver can be injected in the said pressure vessel under action of gravity, thus cooled reactor and keep the reactor core of reactor to be in floodage;
This loop passive residual heat is discharged subsystem and is arranged in the containment; Comprise the passive residual heat discharge heat interchanger in the cooling medium that is submerged in said built-in low-temperature receiver; This passive residual heat is discharged heat interchanger and is linked to each other with the entrance and exit of pressure vessel through pipeline and valve respectively; Form the closed cycle loop, passive residual heat is discharged heat interchanger and there is density difference in the pressure vessel inner fluid, in this closed cycle loop, forms the Natural Circulation of fluid;
This water logging and the air-cooled non-passive safety shell cooling system that combines; Comprise cooling pond and air conducting cover; Containment can be flooded in the cooling pond; This air conducting cover is set outside the inner containment of cooling pond, this air conducting cover have around containment around portion and the diversion division that leads to atmosphere that is positioned at the containment over top, link into an integrated entity around portion and diversion division; The cooling pond has air intake, from the air intake of cooling pond, to the air conducting cover around the bottom of portion, constitute gas channel to diversion division again with chimney effect.
Described diversified engineered safety system, its further characteristics are that said non-active feed-tank is an open container, its top and atmosphere.
Described diversified engineered safety system; Its further characteristics are; In described water logging and the air-cooled non-passive safety shell cooling system that combines, the water space of cooling pond is big at the free area at the top of containment, and the water space of cooling pond is little at the free area of the latter half.
Described diversified engineered safety system, its further characteristics be, in described water logging and the air-cooled non-passive safety shell cooling system that combines, the water level of cooling pond and the face of land maintain an equal level, and containment is positioned at the degree of depth below the face of land.
Described diversified engineered safety system, its further characteristics are that in said non-active safety injection system, built-in low-temperature receiver is connected with the atmosphere of containment.
The beneficial effect of the utility model is following:
1) the utility model is a kind of new security system assembled scheme, is combined by multiple residual heat removal system, safety injection system, containment cooling system, forms systematic safeguard measure;
2) under the accident conditions,, form multiple complete waste heat and discharge channel and waste heat discharge measure, comprising from reactor core and ultimate heat sink through the independent operating or the cooperation operation of each subsystem:
A) independent operating through steam generator secondary side passive residual heat discharge system is discharged to ultimate heat sink with waste heat, and its heat is discharged channel and is: reactor core → steam generator → non-active feed-tank → environment (ultimate heat sink);
B) independent operating of the active residual heat removal system through total head is discharged to ultimate heat sink with waste heat, and its heat is discharged channel and is: reactor core → normal surplus row's heat interchanger → component cooling water system → external environment (ultimate heat sink);
C) through a loop passive residual heat discharge system and non-passive safety shell cooling system cooperation waste heat is discharged to ultimate heat sink, its heat is discharged channel and is: reactor core → passive residual heat is discharged atmospheric environment → cooling pond in heat interchanger → built-in low-temperature receiver → containment → external environment (ultimate heat sink);
D) through non-active safety injection system and non-passive safety shell cooling system cooperation waste heat is discharged to ultimate heat sink, its heat is discharged channel and is: atmospheric environment → cooling pond in reactor core → containment → environment (ultimate heat sink);
3) waste heat from the reactor core to the ultimate heat sink under the accident conditions discharges that channel has side by side, redundant, diversity, under the situation of a certain system or the inefficacy of a certain heat transfer link, still has other system that subsequent use heat transfer channel is provided.Under reactor generation cut accident conditions, the early stage a measure of accident plays a major role, and along with the startup operation of non-active safety injection system, the d measure also has the ability of discharging waste heat, and after the water filling success, the b measure also is effective in the pressure vessel; Take place can adopt a simultaneously under other accident conditionses at reactor, b, waste heat is discharged in three kinds of measures of c.This shows under various accident conditionses, to have 3 parallel various waste heats and discharge channel.
4) the utility model comprises active and passive residual heat discharge system.Under the situation that power supply can be used, active system can discharge waste heat fast and efficiently, makes reactor get into safe condition fast; Under the disabled situation of power supply, depth defense is provided by passive system; And adopt c or d measure can infinitely continue non-active discharge waste heat, guarantee the long-term safety of reactor.
The utility model helps improving the ability of reactor alleviation accident, and improves the security of reactor.
Description of drawings
Fig. 1 is a kind of existing nuclear reactor safety system principle synoptic diagram.
Fig. 2 is an another kind of existing AP1000 nuclear power plant non-passive safety shell cooling system principle schematic.
Fig. 3 is the diversified engineered safety system structural representation of the utility model.
Fig. 4 relies on gravity to inject the structural representation of the steam generator secondary side passive residual heat discharge subsystem of feedwater in the diversified engineered safety system.
Fig. 5 is the structural representation of the non-active safety injection system of low pressure.
Fig. 6 is the structural representation of the non-passive safety shell cooling subsystem of water logging and air-cooled combination.
Fig. 7 is the synoptic diagram of water-cooled pattern of the non-passive safety shell cooling subsystem of water logging and air-cooled combination.
Fig. 8 is the synoptic diagram of air-cooled pattern of the non-passive safety shell cooling subsystem of water logging and air-cooled combination.
Embodiment
As shown in Figure 3, the diversified engineered safety system of the utility model comprises 5 sub-systems: a loop passive residual heat is discharged subsystem 4, dependence gravity injects the steam generator secondary side passive residual heat that feeds water and discharges the non-passive safety shell cooling subsystem 9 that the active waste heat of subsystem 6, total head is discharged non-active peace notes subsystem 5, water logging and the air-cooled combination of subsystem 3, low pressure.
Following elder generation describes the non-passive safety shell cooling subsystem 9 that the steam generator secondary side passive residual heat is discharged subsystem 6, non-active peace notes subsystem 5 and water logging and air-cooled combination respectively.
As shown in Figure 4, the steam generator secondary side passive residual heat is discharged subsystem 6 and is comprised non-active feed-tank 26 and steam generator 24.Steam generator 24 reactor Main Coolants 22 and reactor core 21 composition loops, to take away the reactor core heat, reactor Main Coolant 22 contacts with steam generator 24 through pipeline 23, to carry out heat interchange.Steam generator 24, non-active feed-tank 26, sprinkler 27 constitute the heat-exchange working medium flow circuits through pipeline, non-active feed-tank 26 and with it the working medium in the residual heat removal system of UNICOM be water, also can replace with other feasible working medium.It is that steam generator with reactor is as afterheat heat exchanger that the steam generator secondary side passive residual heat is discharged subsystem 6; The import and export of steam generator 24 are connected respectively on the main feed water pipe road 29 and main steam line 28 of reactor, utilize main steam line 28 and main feed water pipe road 29 near the part of the steam generator part as this system.
After reactor has an accident, can discharge the waste heat of reactor core through this system, detailed process is following:
The reactor shutdown that has an accident, the isolation valve between main steam line 28 and the steam turbine cuts out, and isolates main steam line, so that main steam line 28 only plays the effect of the part of residual heat removal system.Same main feed water isolating valve is closed, and isolates main feed water pipe road 29, so that main feed water pipe road 29 only plays the effect of the part of residual heat removal system.
Reactor Main Coolant 22 reactor core 21 of flowing through; Take away the reactor core heat; And get in the steam generator 24, the heat-transfer pipe through steam generator 24 is with the heat transferred secondary side, and secondary side (for example is a water with the working medium in the main feed water pipe road 29; Also can be other working medium that are suitable for) produce steam, and be sprayed in the non-active feed-tank 26 by sprinkler 27 by the pipeline (comprising part main steam line 28) of residual heat removal system.
Working medium in the non-active feed-tank 26 is taken away the heat of primary side of steam generator Main Coolant once more because segregation drive gets into steam generator 24 through piping, flows out steam generator 24, gets into non-active feed-tank 26 through sprinkler 27.
Sustained delivery along with heat; Temperature in the non-active feed-tank 26 slowly raises; Pressure keeps atmospheric pressure, and the water source start vaporizer in the non-active feed-tank 26 also reduces gradually, forms circulation until its gravity deficiency to drive residual heat removal system; Arrive this, the reactor waste that residual heat removal system was accomplished in one period is efficiently discharged.
As shown in Figure 5, non-active peace is annotated subsystem 5 and is arranged in the containment 51 of reactor, comprises pressure-release valve group (dropping valve automatically) 53, built-in low-temperature receiver 55 and safety injection pipeline 57.Pressure-release valve group 53 constitutes Automatic Depressurization System with sprinkler 54, and Automatic Depressurization System can also comprise signal pickup assembly and other devices that automatic triggering pressure-release valve group is opened.Pressure-release valve group 53 is connected between the outlet and sprinkler 54 of reactor pressure vessel 52, and sprinkler 54 is immersed in the built-in low-temperature receiver 55, and the cooling medium of capacity is housed in the built-in low-temperature receiver 55.The bottom of built-in low-temperature receiver 55 connects safety injection pipeline 57, and safety injection pipeline 57 is connected to the inlet of reactor pressure vessel 52.The interface that built-in low-temperature receiver 55 connects safety injection pipeline 57 is provided with filter screen 56, and also is provided with recycle filter screen 59 in the safety injection pipeline 57.In addition; Aforementioned connection is realized by relevant pipeline and valve; Several pipelines (for example two) draw from reactor pressure vessel, through the combination (the for example combination of solenoid valve and non-return valve, the perhaps combination of explosive valve and non-return valve) of a series of valve parallel connections and/or series connection.Containment 1 is a pressure resistant vessel, can bear than the higher pressure of conventional security shell (such as 0～3MPa); Containment contains in the system other facility except that containment external refrigeration system.
The position of built-in low-temperature receiver 55 is high will to be higher than reactor pressure vessel 52.
When reactor generation forfeiture cooling medium accident, both after the cut accident, the cooling mediums in the reactor pressure vessel 52 spurted to containment 51 inside through cut, and the liquid levels in the reactor pressure vessel 52 reduce, the pressure reduction, and the pressure in the containment 51 raise.
When the liquid level in the reactor pressure vessel 52 drops to a certain degree; Trigger the start signal of pressure-release valve group 53; The triggering of the start signal of pressure-release valve group 53 (being valve opening) does not rely on external power source (for example depending on pressure); Reactor pressure vessel 52 helps to reduce pressure through pressure-release valve group 53, and the gaseous state of reactor pressure vessel 52 (having operative liquid) cooling medium is sprayed in the built-in low-temperature receiver 55 by sprinkler 54 through the valve and the pipeline of pressure-release valve group 53.
When the pressure in the reactor pressure vessel 52 and containment 51 pressure inside reach in a basic balance (such as 1.5MPa); Cooling medium in the built-in low-temperature receiver 55 is owing to exist the driving of gravity; To get into safety injection pipeline 57 through screen pack 56; And be injected in the reactor pressure vessel 52 through safety injection pipeline 57, be that reactor core replenishes cooling medium.Valve 58 on the safety injection pipeline 57 in safety injection process, does not rely on the driving of external power source at this moment by certain unblanking (such as certain low liquid level of reactor pressure vessel).
Along with the continuation of spurting; Pressure and temperature in the containment 51 raises, and containment 51 is provided with external refrigeration facility (such as modes such as outside spray, pond formula submergence, heat pipe for thermal conductivity) 50, and containment 51 is cooled off; Take away heat in the containment 1 to ultimate heat sink, be containment 51 decrease temperature and pressure.
Along with the carrying out of safety injection, the cooling medium in the built-in low-temperature receiver 55 is fewer and feweri, and the cooling mediums in the reactor pressure vessel 52 are heated as gaseous state by reactor core and spurt in the containment 51; Because the external refrigeration of containment 51, the cooling medium of these gaseous states is condensed into liquid state again, and through recycle filter screen 59; Get into safety injection pipeline 57 once more, be injected in the reactor pressure vessel 52, thereby form circulation; Realization is non-fully active, guarantees reactor core cooling over a long time, as long as the initial cooling medium loading amount of reactor pressure vessel 52 is enough; It is not exposed all the time that reactor core can keep, thereby guarantee can not take place the reactor core damage.
Embodiment shown in Figure 5 can through simple equipment and system, successfully carry out safety injection and additional cooling medium to reactor pressure vessel under the situation that does not rely on external power, guarantee the safety of reactor core, has good feasibility and reliability.
Fig. 6, Fig. 7 and the non-passive safety shell cooling subsystem 9 for water logging and air-cooled combination shown in Figure 8; In an embodiment of the utility model; Like Fig. 6, Fig. 7 and shown in Figure 8; In an embodiment of the utility model, non-passive safety shell cooling subsystem comprises metal containment container 92, cooling pond 93 and air conducting cover 95.Metal containment container (being containment) 92 is submerged under normal standby status in the external refrigeration pond 93 fully, and pond 93 is the hot traps of the decay heat of containment under accident conditions.In pond 93, outside the metal containment container 92, air conducting cover 95 is set; Air conducting cover 95 have around containment 92 around portion 951 and the diversion division with air out 99 952 that is positioned at containment 92 over top; Link into an integrated entity with diversion division 952 around portion 951; Cooling pond 93 has air intake 96, from the air intake 96 of cooling pond, to air conducting cover 95 around the bottom of portion 951, constitute gas channel to diversion division 952 again with chimney effect.
Further, the water level 94 of cooling pond 93 maintains an equal level with the face of land 97, and metal containment container 92 is positioned at the face of land 97 following certain depths; Therefore; Cooling pond 93 is bigger in the water storage cross section at metal containment container 92 tops, can store more chilled water and make the water-cooled pattern continue the long period, and containment 92 is in floodage fully in this process; Therefore heat interchanging area is big, helps conducting heat; Cooling pond 93 is merely the ring cavity between the wall in metal containment container 92 and pond 93 in the latter half; Therefore; The live storage cross section of pond 93 the latter halfs is little, and moisture storage capacity is little, below the water level in the pond 93 drops to metal containment container 92 tops after; Decline of water table speed by evaporation causes is faster, helps accelerating from the switching of water-cooled to air-cooled pattern.Because evaporation and after water level is lower than kuppe 95 bottoms, form gas decline and rising runner 911,922 naturally, diabatic process switches to air-cooled pattern by the water-cooled pattern automatically when the water in the pond 93.Design makes that the heat removal capacity of containment cooling system is consistent with the attenuation law of decay heat like this; Be the stronger exchange capability of heat of the bigger needs of accident initial stage decay heat power; So adopt the water-cooled pattern, and post incident reactor core decay heat power is less, adopts air-cooled pattern to meet the demands.
Heat conduction, the evaporation outside the metal containment container 92 or the air Natural Circulation of the steam condensation under accident conditions in the dependence metal containment container 92, the wall of metal containment container 92; Three non-active processes are transmitted continuously the heat in the containment 92 are discharged to the ultimate heat sink outside the containment 92, thereby keep the integrality of containment.
In addition; Because containment 92 locates below ground level; This also helps strengthening biological shielding and reduces the release of radiomaterial to environment, and can prevent effectively that outside disaster or artificial destruction incident are to the influence of reactor (destroy like flood, aircraft impact, terrorist etc.).
Fig. 6 is an example with PWR nuclear power plant generation main coolant system cut accident to the containment cooling subsystem that can be used as presurized water reactor embodiment illustrated in fig. 8 below, sets forth running and the implementation process of this embodiment.
When primary pipe rupture's accident takes place in PWR nuclear power plant; Pressure vessel 91 has main coolant system cut 98; One circuit cools agent (steam) of HTHP is discharged in the containment 92; The temperature and pressure that will cause gas in the containment 92 rises, if there is not the cooling provision of continuous and effective, containment 92 internal pressures possibly surpass design limit and destroyed.Owing to adopt embodiment shown in Figure 3, can obviously alleviate such accident, under above-mentioned accident conditions, the concrete response of step of this embodiment is following.
1) as shown in Figure 4; Because metal containment 92 is submerged under normal standby status in the cooling pond 93 fully; In the accident starting stage; The high-temperature steam that is discharged in the containment 92 will be directly in containment 92 inwall condensations, thereby keep the surge pressure of gas in the containment 92 to be lower than design limit.
2) continue along with what conduct heat, the water temperature in the cooling pond 93 raises, gradually evaporation.Because the design pressure of metal containment 92 is greater than the atmospheric pressure in the cooling pond 93; Therefore the saturation temperature of steam is higher than external refrigeration water saturation temperature all the time in the containment 92; Thereby form stable diabatic process, promptly the heat in the containment is discharged through the heat conduction of containment 92 internal condensations, metal containment 92, the continuous transmission of three non-active processes of water evaporation of containment 92 outer walls.
3) along with the evaporation gradually of water in the cooling pond 93, the water yield reduces, and water level reduces, and cooling power is progressively lost in the pond.After water level was lower than air conducting cover 95 bottoms, air flow channel formed automatically, and diabatic process automatically switches to air-cooled pattern, and set up new steady heat transfer process automatically.As shown in Figure 5; Air-flow flows according to the direction shown in the arrow; Form rising runner 922 and decline runner 911 (promptly from the cooling pond 93 air intake 96, to air conducting cover 95 around portion 951, the air out 99 to diversion division 952 constitutes the gas channel with chimney effect again); Gas in the rising runner 922 is owing to be heated and density is lower than the gas in the decline runner 911, and under the effect of density difference (being chimney effect), the cooling air in the environment continues from the cooling pond 93 air intake 96 and gets into; Through decline runner 911, again through rising runner 922 and cool off metal containment 92 outer walls, discharge from the air out of air conducting cover 95 then.This diabatic process also right and wrong is active, and is the nature switching from water-cooled to air-cooled switching, does not need external signal, does not need other controlling units, does not also need human intervention.Under air-cooled pattern, the heat in the containment is taken out of through the steam condensation of containment 92 inwalls, the heat conduction of metal containment 92, the continuous transmission of three non-active processes of air Natural Circulation of containment 92 outer walls.
4) since this moment decay heat power be reduced to enough for a short time, rely on the air Natural Circulation can keep the cooling of containment.Air-cooled pattern can indefinite duration continuous service, do not need external impetus, do not need human intervention yet.
The non-passive safety shell cooling subsystem 9 that steam generator secondary side passive residual heat discharge subsystem 6, non-active peace are annotated subsystem 5 and water logging and air-cooled combination in Fig. 3 shows in a simplified manner.The non-active water tank 26 that waste heat is discharged subsystem 6 links to each other with steam generator 24 secondary sides through water-supply line, vapour line respectively.Non-return valve 62 is set on the water-supply line linkage section, and fluid can only unidirectionally pass through.On the vapour line linkage section, relief valve 61 is set.Under accident conditions; Valve according to enabling signal is closed on the pipeline 28,29 is isolated the reactor secondary circuit system; And open valve 61; With discharge of steam to the non-active water tank 26 of steam generator secondary side, non-return valve 62 is opened automatically, and non-active water tank 26 is communicated with the secondary side of steam generator 24.The water of non-active water tank 26 relies on gravity steam in jection generator 24, and the back evaporation of being heated forms steam and discharges, and simultaneously heat is taken out of.Non-active safety injection system 5 links to each other with pressure vessel 10 through source line collector 8, discharge pipe collector 7.On source line linkage section (safety injection pipeline), valve 58 is set, dropping valve group 53 is set on the discharge pipe linkage section.Under accident conditions; Open dropping valve group 53 according to enabling signal, carry out the active fast pressure relief, after the cooling system in the pressure vessel 10 is unified circuit pressure and containment 92 internal pressure balances; Valve 58 is opened automatically; Cooling medium (water) in the built-in low-temperature receiver 54 relies on gravity to get into pressure vessel 10, discharges from dropping valve group 53 after the refrigerant evaporates in the pressure vessel 10, thus the cooling reactor core.One circuit cools agent forfeiture accident conditions take place at reactor in the non-passive safety shell cooling system 9 of water logging and air-cooled combination; And after an above-mentioned loop passive residual heat discharge system 4 or 5 startups of non-active safety injection system; Residual heat of nuclear core is discharged in the containment 92; To cause that the temperature in the containment 92 rises, owing to containment 92 is submerged in the external refrigeration pond 93, so the heats in the containment 93 transmit outside trend containment 92.Water in the pond 93 evaporates by heat, and after water level was lower than air conducting cover 95 bottoms, containment 92 coolings automatically switched to air-cooled pattern, but air-cooled pattern continuous service in indefinite duration.
Reference numeral identical among Reference numeral in Fig. 3 and Fig. 4 to Fig. 8 indicates identical composition.
Continuation is with reference to Fig. 3, and a loop passive residual heat is discharged subsystem 4 and comprised passive residual heat discharge heat interchanger 41, relevant connection pipeline and valve.Passive residual heat is discharged heat interchanger 41 and is linked to each other with the entrance and exit of pressure vessel 10 through source line collector 8, discharge pipe collector 7 respectively.Non-return valve 43 is set on the source line linkage section, and fluid can only unidirectionally pass through.On the discharge pipe linkage section, isolation valve 42 is set.Under accident conditions; Open isolation valve 42 according to enabling signal; One loop HTHP cooling medium gets into heat interchanger 41; Between source line, discharge pipe, form density difference after cooling medium in the heat interchanger 41 is cooled, and make non-return valve 43 open automatically, make passive residual heat discharge heat interchanger 41 and be communicated with formation enclosed heat transfer cycle loop with pressure vessel 10.Heat interchanger 41 is cooled off by the cooling medium in the low-temperature receiver 54 (for example water).
Continuation is with reference to Fig. 3, and the active waste heat of total head is discharged subsystem 3 and comprised ebullator 30, heat interchanger 31 and respective lines and valve.Heat interchanger 31 directly links to each other with the entrance and exit of pressure vessel 10 through source line collector 8, discharge pipe collector 7 with ebullator 30, and non-return valve 33 is set on the source line linkage section, and fluid can only unidirectionally pass through.On the discharge pipe linkage section, isolation valve 32 is set.Under accident conditions, open isolation valve 32 according to enabling signal, and start ebullator 30, form enclosed forced circulation loop.Heat interchanger 30 cools off through component cooling water system.The design pressure of normal residual heat removal system 3 is identical with a loop design pressure, can under condition of high voltage, move.No matter the cooling medium in the pressure vessel is in any pressure working condition, subsystem 3 all can put into operation immediately, cooled reactor rapidly and efficiently.
Be example with common pressurized water reactor below and combine accompanying drawing 3 that the principle of work of the utility model exemplarily is described.
Pressurized water reactor is when normal operation, and the reactor core heat passes to secondary circuit through the forced circulation of a circuit cools agent system in steam generator 24.Under accident conditions, conservative think that this heat transfer channel is unavailable, need the engineered safety system of the utility model that extra, the channel that conducts heat reliably is provided, residual heat of nuclear core is discharged into the outer ultimate heat sink of containment 92.
The accident conditions of pressurized water reactor can be summarized and is divided into a circuit cools agent forfeiture accident (LOCA) and other accidents (non-LOCA), introduces the response and the implementation process of above-mentioned security system under these two types of accident conditions below respectively.
A) taking place under the non-LOCA accident conditions, can discharge residual heat of nuclear core 3 and come heat extraction through a loop passive residual heat discharge system 4, steam generator secondary side passive residual heat discharge system 6, normal residual heat removal system respectively.But these three kinds of system's parallel runnings also can singlely move, and each subsystem can both guarantee effective cooling of reactor core.Under the parallel running pattern, three kinds of subsystems start simultaneously, if three kinds of subsystems are all available, can cool off reactor core fast so; Under operational mode successively; According to the depth defense principle; Can discharge residual heat of nuclear core through normal residual heat removal system 3 if power supply can be used so,, can cool off reactor core through the Natural Circulation of a loop passive residual heat discharge system 4 so if power supply is unavailable; If this system had also lost efficacy, can discharge system 6 through the steam generator secondary side passive residual heat so and come cooled reactor.These systems parallel or successively operational mode can be provided with as required.
B) taking place under the LOCA accident conditions; If still more, discharge the operation of system 4, steam generator secondary side passive residual heat discharge system 6, normal residual heat removal system 3 through a loop passive residual heat and still can discharge residual heat of nuclear core in accident initial stage one circuit cools agent loading amount.If a circuit cools agent loading amount has been lower than certain limitation; Then open pressure-release valve 53 and carry out the active release; Thereby make non-active safety injection system 5 drop into, and, make water level rising in the pressure vessel 10 through gravity water filling in pressure vessel (supposing that water is the cooling medium in the low-temperature receiver 54).If power supply can be used, after water level rose, normal residual heat removal system 3 can put into operation so, thus the cooling reactor core; If power supply is unavailable, the water that are injected in the pressure vessel 10 are heated discharge vaporization in containment 92, through the water filling that do not stop and the open type diabatic process of steam discharge residual heat of nuclear core are taken out of.
Under non-LOCA accident conditions; Discharge system 4 perhaps under the LOCA accident conditions if started a loop passive residual heat; Residual heat of nuclear core is discharged in the containment; To cause that the temperature and pressure in the containment rises, non-passive safety shell cooling system 9 drops into automatically, and residual heat of nuclear core passes to external refrigeration pond 93 or ambient atmosphere through metal containment 92 automatically.Thereby the temperature and pressure of keeping containment 92 is no more than design limit, the integrality of protection containment.
Embodiment shown in Figure 3 is a kind of security system assembled scheme, under accident conditions, the waste heat discharge process of each sub-systems be separate and principle various.
The waste heat from the reactor core to the ultimate heat sink under the accident conditions is discharged channel and is had diversity, under the situation of a certain system or the inefficacy of a certain heat transfer link, still has other system that effective heat transfer channel is provided.These waste heats are discharged channel can be expressed as following process:
A) reactor core (in pressure vessel 10) → passive residual heat is discharged heat interchanger 41 → low-temperature receiver, 54 → containment, 92 → external refrigeration pond 93 → environment (ultimate heat sink);
B) reactor core → steam generator 24 → non-active water tank 26 → environment (ultimate heat sink);
C) reactor core → normal surplus row's heat interchanger 31 → component cooling water system → environment (ultimate heat sink);
D) reactor core → containment 92 → external refrigeration pond 93 → environment (ultimate heat sink);
In the above-mentioned diabatic process, a, c, d can indefinite duration continuous service.
Claims (5)
1. the diversified engineered safety system that is used for nuclear reactor; It is characterized in that; Comprise that a loop passive residual heat is discharged subsystem, dependence gravity injects the steam generator secondary side passive residual heat that feeds water and discharges the non-passive safety shell cooling subsystem that the active waste heat of subsystem, total head is discharged subsystem, the non-active peace notes of low pressure subsystem, water logging and air-cooled combination; Wherein
This steam generator secondary side passive residual heat is discharged subsystem and is comprised steam generator and non-active feed-tank; This non-active feed-tank is arranged on outside the containment; Respectively corresponding feed pipe and the steam pipe through pipeline and valve and steam generator secondary side in its bottom and the top complete loop of formation of connecting; This non-active feed-tank absolute altitude is higher than the position of steam generator; Feedwater in the non-active feed-tank can absorb the heat of the reactor coolant that is transmitted by primary side of steam generator through the secondary side of gravity steam in jection generator, thus cooled reactor;
The active waste heat of this total head is discharged subsystem and is arranged in the containment; Comprise ebullator, heat interchanger; Through pipeline and valve the entrance and exit of heat interchanger, ebullator, pressure vessel is concatenated into the closed cycle loop; This loop stream designs for total head through pipeline and equipment, and promptly design pressure is identical with the reactor main system;
The non-active peace of this low pressure is annotated subsystem and is arranged in the containment; Comprise automatic dropping valve, built-in low-temperature receiver and safety injection pipeline; Automatically dropping valve is connected the outlet of pressure vessel; Built-in low-temperature receiver is connected to the inlet of pressure vessel through safety injection pipeline and valve, and the cooling medium of capacity is housed in the built-in low-temperature receiver, and its absolute altitude is higher than pressure vessel; Cooling medium in the built-in low-temperature receiver can be injected in the said pressure vessel under action of gravity, thus cooled reactor and keep the reactor core of reactor to be in floodage;
This loop passive residual heat is discharged subsystem and is arranged in the containment; Comprise the passive residual heat discharge heat interchanger in the cooling medium that is submerged in said built-in low-temperature receiver; This passive residual heat is discharged heat interchanger and is linked to each other with the entrance and exit of pressure vessel through pipeline and valve respectively; Form the closed cycle loop, passive residual heat is discharged heat interchanger and there is density difference in the pressure vessel inner fluid, in this closed cycle loop, forms the Natural Circulation of fluid;
This water logging and the air-cooled non-passive safety shell cooling system that combines; Comprise cooling pond and air conducting cover; Containment can be flooded in the cooling pond; This air conducting cover is set outside the inner containment of cooling pond, this air conducting cover have around containment around portion and the diversion division that leads to atmosphere that is positioned at the containment over top, link into an integrated entity around portion and diversion division; The cooling pond has air intake, from the air intake of cooling pond, to the air conducting cover around the bottom of portion, constitute gas channel to diversion division again with chimney effect.
2. diversified engineered safety system as claimed in claim 1 is characterized in that, said non-active feed-tank is an open container, its top and atmosphere.
3. diversified engineered safety system as claimed in claim 1; It is characterized in that; In described water logging and the air-cooled non-passive safety shell cooling system that combines; The water space of cooling pond is big at the free area at the top of containment, and the water space of cooling pond is little at the free area of the latter half.
4. diversified engineered safety system as claimed in claim 1 is characterized in that, in described water logging and the air-cooled non-passive safety shell cooling system that combines, the water level of cooling pond and the face of land maintain an equal level, and containment is positioned at the degree of depth below the face of land.
5. diversified engineered safety system as claimed in claim 1 is characterized in that, in said non-active safety injection system, built-in low-temperature receiver is connected with the atmosphere of containment.
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