CN202887748U - Passive heat discharge device for dealing with plant switch-off accident - Google Patents
Passive heat discharge device for dealing with plant switch-off accident Download PDFInfo
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- CN202887748U CN202887748U CN2012205036754U CN201220503675U CN202887748U CN 202887748 U CN202887748 U CN 202887748U CN 2012205036754 U CN2012205036754 U CN 2012205036754U CN 201220503675 U CN201220503675 U CN 201220503675U CN 202887748 U CN202887748 U CN 202887748U
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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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- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
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Abstract
The utility model relates to a reactor design technology and particularly relates to a passive heat discharge device for dealing with a plant switch-off accident. The passive heat discharge device for dealing with the plant switch-off accident structurally comprises a secondary side passive waste heat discharge system and a passive safe shell heat lead-out system; the secondary side passive waste heat discharge system is used for leading waste heat of a reactor core and sensible heat of components of a reactor coolant system out, so that the a reactor is kept in a safe shut-down state; and the passive safe shell heat lead-out system is used for leading heat released by the reactor core inside a safe shell out, so that the integrity of the safe shell can be kept. The secondary side passive waste heat discharge system and the passive safe shell heat lead-out system share a heat exchange water tank. The passive heat discharge device for dealing with the plant switch-off accident provided by the utility model can be used for conducting out decay heat of the reactor and heat released inside a space of the safe shell in a working condition of the plant switch-off accident, so that the melting rate of the reactor and the rate of releasing radioactive substance to an environment can be obviously reduced.
Description
Technical field
The utility model relates to the reactor designing technique, is specifically related to a kind of non-active heat release of tackling station blackout accident.
Background technology
Station blackout is defined as AC power total loss in the power plant.Tradition active nuclear power plant is because Core cooling, Decay heat removal system and containment cooling all depend on AC power, so the consequence of station blackout is more serious.The mitigation strategy of tradition active nuclear power plant station blackout comprises: when station blackout occurs, start through hydraulic testpump genset or portable diesel-driven generator, by giving the power supply of hydraulic pressure test pump, to inject the main pump shaft seal from the boron water of material-changing water tank, guarantee the integrality of shaft seal, guarantee the integrality of Main Coolant pump seal, the boric acid concentration of guaranteeing a loop, the water loading amount of keeping a loop and the discharge of assurance waste heat, and for moving the important instrument power supply that submits necessary information.This moment, turbine driven auxiliary feed-water pump provided feedwater for steam generator, derived residual heat of nuclear core by the airborne release system.The device of the reply station blackout accident of this kind active is too complicated, too relies on vapour source and diesel-driven generator.
Since the eighties in last century, the countries such as the U.S., Japan, France, Germany, Russia have carried out the research of passive technology, wherein take non-passive safety advanced nuclear plant AP1000 generation Ⅲ nuclear power unit as representative.
The Heat Discharging System of Chinese of U.S. AP1000 adopts non-enabling fashion to export to the built-in material-changing water tank of containment in lower reactor core decay heat of station blackout accident operating mode.This system is by being arranged in the passive residual heat removal heat exchanger in the material-changing water tank (IRWST), and the Natural Circulation of discharging between the heat exchanger by reactor and reactor waste reaches chilled water in the material-changing water tank with the reactor core decay heat.Only need to open any of two startup isolation valves of this system heat exchanger outlet, any of the solidifying hydrophobic pneumatic isolation valve of water reflux trough of containment of closing simultaneously two series connection can make system put into operation.4 isolation valves all have pressure gas (energy storage), accumulator (energy storage) as power source.
The Passive containment cooling system of U.S. AP1000 adopt non-enabling fashion the dissipation of heat in the containment to ultimate heat sink-atmosphere.Under the accidental conditions, air enters from shielding structures top entrance, flows through behind the decline passway again oppositely by the rising runner, takes away the heat of containment chamber wall transmission, drains into environment from chimney at last.After receiving high-2 pressure signals of containment, operation starts automatically after the accident of system, only needs to open three normal any one of closing in the isolation valve, does not need other actions to get final product start-up system.The startup of system also can be manually booted at master-control room or long-range shutdown workstation by operator.
The passive system of U.S. AP1000 can successfully manage station blackout accident, but is only applicable to passive safety system nuclear power plant.For the nuclear power plant of active engineered safeguards features, said system is difficult to satisfy the requirement of reply station blackout accident.
The utility model content
The purpose of this utility model is the defective for prior art, a kind of non-active heat release of tackling station blackout accident is provided, under the station blackout accident operating mode, derive the reactor core decay heat and be discharged into heat in the containment space, significantly reduce reactor core and melt the probability that probability and radiomaterial discharge to environment.
The technical solution of the utility model is as follows: a kind of non-active heat release of tackling station blackout accident, comprise Passive residual heat removal system and passive containment thermal conduction system, wherein, described Passive residual heat removal system comprises the two-way vapour line that is connected with the main steam line of steam generator, first via vapour line is discharged refrigeratory with emergent waste heat and is connected, the the second road vapour line is connected with the emergence compensating water case, described emergent waste heat is discharged refrigeratory and is arranged in the heat-exchanging water tank of containment outside, the outlet conduit that emergent waste heat is discharged refrigeratory is combined into a solidifying waterpipe with the injection pipeline that the emergence compensating water case exports, and is connected with the main feed water pipe road of the steam generator of below; Described passive containment thermal conduction system comprises heat interchanger or the heat exchanger package that is arranged on containment inside, and described heat interchanger or heat exchanger package are connected with the heat-exchanging water tank that is arranged on the containment outside with the decline pipeline by the rising pipeline; Passive residual heat removal system and passive containment thermal conduction system share same heat-exchanging water tank, and the height of heat-exchanging water tank is higher than the height of heat interchanger or heat exchanger package.
Further, the non-active heat release of aforesaid reply station blackout accident, wherein, upper all setting the at the described two-way vapour line that is connected with the main steam line of steam generator often driven electronic isolation valve, and the outlet conduit of discharging refrigeratory at emergent waste heat arranges the normally-closed pneumatic isolation valve.
Further, the non-active heat release of aforesaid reply station blackout accident, wherein, the injection pipeline that exports at described emergence compensating water case is provided with the normally-closed pneumatic isolation valve.
Further, the non-active heat release of aforesaid reply station blackout accident, wherein, described emergence compensating water case is arranged on the outside of containment.
Further, the non-active heat release of aforesaid reply station blackout accident, wherein, be provided with steam-water separator in the heat-exchanging water tank of containment outside, the rising pipeline of the heat interchanger of described passive containment thermal conduction system or heat exchanger package is connected with steam-water separator.
Further, the non-active heat release of aforesaid reply station blackout accident wherein, is respectively equipped with isolation valve at rising pipeline and the decline pipeline of described passive containment thermal conduction system.
Further, the non-active heat release of aforesaid reply station blackout accident, wherein, described heat-exchanging water tank is the reinforced concrete structure of sealing, and is provided with stainless steel lining.
The beneficial effects of the utility model are as follows: the utility model combines Passive residual heat removal system (PRS) and passive containment thermal conduction system (PCS) and deals with the nuclear power station station blackout accident, can effectively tackle the incomplete accident sequence of a loop or secondary circuit that superposes take station blackout as origination event, the PRS system is used for deriving the sensible heat of residual heat of nuclear core and each equipment of reactor coolant loop, makes reactor maintain the safe shutdown state; Pcs system is used for deriving reactor core and is discharged into the interior heat of containment, keeps the integrality of containment.Therefore, the mode that the PRS system combines with pcs system is tackled station blackout accident and is more had superiority than separately PRS system or pcs system being set, simultaneously, it also is the best of breed scheme of reply nuclear power station station blackout accident, PRS system and pcs system can share same heat-exchanging water tank, simplified system equipment, the water yield of heat-exchanging water tank can be guaranteed need not operator's operation and realize 72 hours the non-active operation of system.
Description of drawings
Fig. 1 is system architecture schematic diagram of the present utility model.
Among the figure, the injection pipeline 8. emergent waste heats of 1. steam generator 2. main steam lines 3. main feed water pipe roads 4. first via vapour lines, 5. the second road vapour lines, 6. emergence compensating water casees, 7. water supply tanks outlet are discharged refrigeratory 9. heat-exchanging water tanks 10. solidifying waterpipe 11. electronic isolation valve 12. pneumatic isolation valve 13. pneumatic isolation valve 14. heat interchanger or heat exchanger package 15. rising pipelines 16. decline pipelines 17. steam-water separators 18. isolation valves 19. isolation valves 20. electronic isolation valves
Embodiment
The non-active heat release of reply station blackout accident provided by the utility model, station blackout accident occurs after, Passive residual heat removal system (PRS) is used for deriving the sensible heat of residual heat of nuclear core and each equipment of reactor coolant loop, makes reactor maintain the safe shutdown state; Passive containment thermal conduction system (PCS) is used for deriving reactor core and is discharged into the interior heat of containment, keeps the integrality of containment.Passive residual heat removal system (PRS) and passive containment thermal conduction system (PCS) share heat-exchanging water tank.
The system that traditional nuclear power plant carries out security function finishes by active equipment, parts, so the realization of security function relies on the safe level power supply after the accident.In case factory's internal/external power forfeiture, security function can't realize.The non-active heat release of reply station blackout can be discharged residual heat of nuclear core and the heat that is discharged in the containment under the beyond design basis accident operating mode of station blackout.When station blackout occurs when, start through hydraulic testpump genset or portable diesel-driven generator, by giving the power supply of hydraulic pressure test pump, to inject the main pump shaft seal from the boron water of material-changing water tank, guarantee the integrality of shaft seal, guarantee the integrality of Main Coolant pump seal, the boric acid concentration of guaranteeing a loop, the water loading amount of keeping a loop and the discharge of assurance waste heat, and for moving the important instrument power supply that submits necessary information.This moment, turbine driven auxiliary feed-water pump provided feedwater for steam generator, derived residual heat of nuclear core by the airborne release system; If turbine driven auxiliary feed-water pump lost efficacy, in the situation that a loop and secondary circuit are complete, can adopt Passive residual heat removal system (PRS), derive the sensible heat of residual heat of nuclear core and each equipment of reactor coolant loop, at the appointed time reactor be maintained safe condition.Therefore the PRS system can successfully manage station blackout accident, but the PRS system can not tackle the incomplete accident sequence of a loop or secondary circuit that superposes take station blackout as origination event, and therefore passive containment thermal conduction system (PCS) need to be set tackles this accident sequence.If a loop or secondary circuit are imperfect, thermal release can adopt pcs system in the containment space, the containment pressure and temperature is reduced to acceptable level, to keep the integrality of containment.More have superiority than separately PRS system or pcs system being set so the mode that the PRS system combines with pcs system is tackled station blackout accident, the mode that the PRS system combines with pcs system can be tackled station blackout and the accident sequence take station blackout as origination event.In addition, PRS system and pcs system can share heat-exchanging water tank, and the water yield of heat-exchanging water tank can be guaranteed need not operator's operation and realize 72 hours the non-active operation of system.
The PRS system discharges refrigeratory by the emergent waste heat in the heat-exchanging water tank heat of steam generator secondary side is exported to heat-exchanging water tank.Start under the failure accidents operating mode at station blackout accident stack auxiliary feedwater system pneumatic pump, because main pump is stopped transport, reactor coolant loop utilizes system in the temperature difference and the difference in height of reactor part and steam generator part, has certain natural-circulation capacity, the heat of reactor to the steam generator transmission, is finished the Natural Circulation in reactor coolant loop.
The vapour line of PRS system is connected on the main steam line.Vapour line is divided into two branch roads, discharges refrigeratory with emergent waste heat for one and links to each other, and another links to each other with the emergence compensating water case, all arranges on the two-way vapour line and often drives electronic isolation valve, and emergent waste heat is discharged refrigeratory and is arranged in the heat-exchanging water tank bottom.The injection pipeline that emergent waste heat is discharged cooler outlet pipeline and the outlet of emergence compensating water case is combined into a solidifying waterpipe, links to each other with the steam generator feedwater piping.The unit normal operation period, the electronic isolation valve on the PRS system jet chimney keeps often opening, and the pneumatic isolation valve on the solidifying waterpipe keeps normal and closes, and emergent waste heat is discharged the cooler tube side and is full of water.After system's input signal sends, isolation valve on the solidifying waterpipe is opened, system puts into operation, the water that emergent waste heat is discharged the cooler tube side injects steam generator secondary side under Action of Gravity Field, become steam after being heated by residual heat of nuclear core, steam enters emergent waste heat through the PRS jet chimney and discharges the cooler tube side, carry out exchange heat with the chilled water in the heat-exchanging water tank, steam is condensed into water after with the heat transferred chilled water, condensate water returns steam generator secondary side under action of gravitation, thereby finishes the Natural Circulation of steam-solidifying water loop.Each PRS series arranges an emergence compensating water case, and its top links to each other with the jet chimney of PRS system, and the bottom links to each other with the solidifying waterpipe of PRS system.When the PRS system put into operation, the isolation valve that water supply tank injects on the pipeline was pressed unblanking, and the water steam injection generator secondary side in the emergence compensating water case is with the forfeiture of compensation steam generator secondary side steam and the contraction of water volume.
Pcs system utilizes the heat exchanger package of layout in the containment and the high temperature air in the containment to carry out condensation, convection current and radiant heat transfer, the heat of high temperature air heats up in the chilled water absorption safety shell of heat interchanger, density reduces, form density difference with the water of cold leg, finish Natural Circulation, at containment peripheral hardware displacement boiler, ultimate heat sink is atmosphere, by flowing of water in the Tube Sheet of Heat Exchanger, continuously the heat in the containment is taken to outside the containment, to realize constantly non-passive safety shell heat discharge under beyond design basis accident and the major accident operating mode.
Pcs system comprises one or one group of heat interchanger, a steam-water separator, a heat-exchanging water tank, is separately positioned on an electronic isolation valve between the valve operation of containment outside, the pneumatic valve of two parallel connections.Heat interchanger is arranged on the interior circumference of containment; Heat-exchanging water tank is the stainless steel-lined equipment of reinforced concrete structure, is arranged in the annular building thing of double containment outside.
Below in conjunction with the drawings and specific embodiments the utility model is described in detail.
As shown in Figure 1, the non-active heat release of the reply station blackout accident that the utility model provides comprises Passive residual heat removal system (PRS) and passive containment thermal conduction system (PCS), described Passive residual heat removal system (PRS) comprises the two-way vapour line that is connected with the main steam line 2 of steam generator 1, first via vapour line 4 is discharged refrigeratory 8 with emergent waste heat and is connected, the the second road vapour line 5 is connected with emergence compensating water case 6, emergence compensating water case 6 is arranged on the outside of containment, described emergent waste heat is discharged refrigeratory 8 and is arranged in the heat-exchanging water tank 9 of containment outside, heat-exchanging water tank 9 is the reinforced concrete structure of sealing, and be provided with stainless steel lining, the outlet conduit that emergent waste heat is discharged refrigeratory 8 is combined into a solidifying waterpipe 10 with the injection pipeline 7 that the emergence compensating water case exports, and is connected with the main feed water pipe road 3 of the steam generator 1 of below; Described passive containment thermal conduction system (PCS) comprises heat interchanger or the heat exchanger package 14 that is arranged on containment inside, and described heat interchanger or heat exchanger package 14 are connected with the heat-exchanging water tank 9 that is arranged on the containment outside with decline pipeline 16 by rising pipeline 15; PRS system and pcs system share same heat-exchanging water tank 9, and the height of heat-exchanging water tank 9 is higher than the height of heat interchanger or heat exchanger package 14.
On described and two-way vapour line that the main steam line 2 of steam generator 1 is connected, all arrange and often drive electronic isolation valve 11,20, the outlet conduit of discharging refrigeratory 8 at emergent waste heat arranges normally-closed pneumatic isolation valve 12, and the injection pipeline 7 that exports at described emergence compensating water case 6 is provided with pneumatic isolation valve 13.The unit normal operation period, the electronic isolation valve 11 of PRS system keeps often opening, and the pneumatic isolation valve 12 on the outlet conduit of emergent waste heat discharge refrigeratory keeps normal and closes, and emergent waste heat discharge refrigeratory 8 pipe sides are full of water.After system's input signal sends, pneumatic isolation valve 12 on the solidifying waterpipe 10 is opened, system puts into operation, the water that emergent waste heat is discharged refrigeratory 8 pipe sides injects steam generator secondary side under Action of Gravity Field, become steam after being heated by residual heat of nuclear core, steam enters emergent waste heat through the PRS jet chimney and discharges refrigeratory 8 pipe sides, carry out exchange heat with the chilled water of 9 li of heat-exchanging water tanks, steam is condensed into water after with the heat transferred chilled water, condensate water returns steam generator secondary side under action of gravitation, thereby finishes the Natural Circulation of steam-solidifying water loop.When the PRS system put into operation, the isolation valve 13 that emergence compensating water case 6 injects on the pipeline was pressed unblanking, and the water steam injection generator secondary side in the emergence compensating water case 6 is with the forfeiture of compensation steam generator secondary side steam and the contraction of water volume.
Be provided with steam-water separator 17 in the heat-exchanging water tank 9 of containment outside, the rising pipeline 15 of the heat interchanger of pcs system or heat exchanger package 14 is connected with steam-water separator 17.Be respectively equipped with isolation valve 18,19 on the rising pipeline 15 of pcs system and the decline pipeline 16.Automatically open or at the manually opened pneumatic isolation valve 19 of master-control room, system puts into operation by signal controlling.
The utility model utilizes that Passive residual heat removal system (PRS) and passive containment thermal conduction system (PCS) are common under the station blackout accident operating mode derives the reactor core decay heat and be discharged into heat in the containment space.Adopt non-active design concept, can tackle station blackout accident.Design concept of the present utility model is simple, clear, advanced, can significantly reduce the probability (LERF) that reactor core thawing probability (CDF) and radiomaterial discharge to environment.
Obviously, those skilled in the art can carry out various changes and modification to the utility model and not break away from spirit and scope of the present utility model.Like this, if of the present utility model these are revised and modification belongs within the scope of the utility model claim and equivalent technology thereof, then the utility model also is intended to comprise these changes and modification interior.
Claims (7)
1. non-active heat release of tackling station blackout accident, comprise Passive residual heat removal system and passive containment thermal conduction system, described Passive residual heat removal system comprises the two-way vapour line that is connected with the main steam line (2) of steam generator (1), first via vapour line (4) is discharged refrigeratory (8) with emergent waste heat and is connected, the the second road vapour line (5) is connected with emergence compensating water case (6), it is characterized in that: described emergent waste heat is discharged refrigeratory (8) and is arranged in the heat-exchanging water tank (9) of containment outside, the outlet conduit that emergent waste heat is discharged refrigeratory (8) is combined into a solidifying waterpipe (10) with the injection pipeline (7) that the emergence compensating water case exports, and is connected with the main feed water pipe road (3) of the steam generator (1) of below; Described passive containment thermal conduction system comprises heat interchanger or the heat exchanger package (14) that is arranged on containment inside, and described heat interchanger or heat exchanger package (14) are connected with the heat-exchanging water tank that is arranged on the containment outside (9) with decline pipeline (16) by rising pipeline (15); Passive residual heat removal system and passive containment thermal conduction system share same heat-exchanging water tank (9), and the height of heat-exchanging water tank (9) is higher than the height of heat interchanger or heat exchanger package (14).
2. the non-active heat release of reply station blackout accident as claimed in claim 1, it is characterized in that: all arrange on described and two-way vapour line that the main steam line (2) of steam generator (1) is connected and often drive electronic isolation valve (11,20), the outlet conduit of discharging refrigeratory (8) at emergent waste heat arranges normally-closed pneumatic isolation valve (12).
3. the non-active heat release of reply station blackout accident as claimed in claim 1 or 2 is characterized in that: the injection pipeline (7) in described emergence compensating water case (6) outlet is provided with normally-closed pneumatic isolation valve (13).
4. the non-active heat release of reply station blackout accident as claimed in claim 3, it is characterized in that: described emergence compensating water case (6) is arranged on the outside of containment.
5. the non-active heat release of reply station blackout accident as claimed in claim 1, it is characterized in that: be provided with steam-water separator (17) in the heat-exchanging water tank (9) of containment outside, the rising pipeline (15) of the heat interchanger of described passive containment thermal conduction system or heat exchanger package (14) is connected with steam-water separator (17).
6. such as the non-active heat release of claim 1 or 5 described reply station blackout accidents, it is characterized in that: rising pipeline (15) and decline pipeline (16) at described passive containment thermal conduction system are respectively equipped with isolation valve (18,19).
7. the non-active heat release of reply station blackout accident as claimed in claim 1 is characterized in that: described heat-exchanging water tank (9) is the reinforced concrete structure of sealing, and is provided with stainless steel lining.
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| Application Number | Priority Date | Filing Date | Title |
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| CN2012205036754U CN202887748U (en) | 2012-08-20 | 2012-09-27 | Passive heat discharge device for dealing with plant switch-off accident |
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| CN201220413286.2 | 2012-08-20 | ||
| CN201220413286 | 2012-08-20 | ||
| CN2012205036754U CN202887748U (en) | 2012-08-20 | 2012-09-27 | Passive heat discharge device for dealing with plant switch-off accident |
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| CN202887748U true CN202887748U (en) | 2013-04-17 |
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| CN2012103751198A Pending CN102867550A (en) | 2012-08-20 | 2012-09-27 | Passive heat removal device for dealing with station blackout accident |
| CN2012205036754U Expired - Lifetime CN202887748U (en) | 2012-08-20 | 2012-09-27 | Passive heat discharge device for dealing with plant switch-off accident |
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| CN102867550A (en) * | 2012-08-20 | 2013-01-09 | 中国核电工程有限公司 | Passive heat removal device for dealing with station blackout accident |
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- 2012-09-27 CN CN2012103751198A patent/CN102867550A/en active Pending
- 2012-09-27 CN CN2012205036754U patent/CN202887748U/en not_active Expired - Lifetime
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102867550A (en) * | 2012-08-20 | 2013-01-09 | 中国核电工程有限公司 | Passive heat removal device for dealing with station blackout accident |
| CN114822886A (en) * | 2022-04-22 | 2022-07-29 | 核电运行研究(上海)有限公司 | Passive air cooling system applied to containment heat exchange water tank |
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| Publication number | Publication date |
|---|---|
| CN102867550A (en) | 2013-01-09 |
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