CN202887750U - Advanced secondary side reactor core heat leading-out device - Google Patents
Advanced secondary side reactor core heat leading-out device Download PDFInfo
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- CN202887750U CN202887750U CN2012205044093U CN201220504409U CN202887750U CN 202887750 U CN202887750 U CN 202887750U CN 2012205044093 U CN2012205044093 U CN 2012205044093U CN 201220504409 U CN201220504409 U CN 201220504409U CN 202887750 U CN202887750 U CN 202887750U
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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
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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Abstract
The utility model belongs to the reactor design technology and in particular relates to an advanced secondary side reactor core heat leading-out device. The device comprises a passive subsystem and an active subsystem, wherein the passive subsystem comprises a plurality of passive waste heat removal series; each passive waste heat removal series comprises a passive waste heat removal cooler put in an accident cooling water tank; an upstream steam pipeline of the passive waste heat removal cooler is connected with a main steam pipeline of a steam generator and a downstream condensate pipeline thereof is connected with a main water supply pipeline of the steam generator; a passive water supplementing tank is also arranged between the upstream steam pipeline and downstream condensate pipeline of the passive waste heat removal cooler; the active subsystem comprises two redundant water supply series; and one end of each water supply series is connected with the accident cooling water tank of the passive subsystem and the other end thereof is connected with the main water supply pipeline of the steam generator. The device can ensure long-term lead-out of the reactor core heat under accident conditions and relieve the serious accident consequences.
Description
Technical field
The utility model belongs to the reactor designing technique, is specifically related to a kind of advanced person's secondary side reactor core heat let-off gear(stand).
Background technology
After the reactor shutdown, because the heat that the fission of the residue of reactor core and fission product decay produce still needs discharge within a very long time, otherwise can cause the major accident of cooling medium boiling even core meltdown.In traditional PWR nuclear power plant design, usually adopt active mode to the steam generator moisturizing.Be active secondary side residual heat removal system, active secondary side residual heat removal system is in the situation that the power supply supply is secure, drives the steam generator secondary side feedwater by auxiliary feed water pump and carries out forced circulation, residual heat of nuclear core is derived, and deliver to ultimate heat sink.Active secondary side residual heat removal system heat exchange efficiency is high, but when station blackout occurs, normal power source and simultaneously forfeiture of reliable source of power power supply, system discharges the function of residual heat of nuclear core with regard to forfeiture.So it is larger that active secondary side residual heat removal system is affected by power supply reliability, poor stability.
The scheme that tradition active secondary side residual heat removal system adopts pneumatic pump to combine with electrodynamic pump, along with the continuous progress of technology, pneumatic pump shows its shortcoming and defect gradually.Single from the equipment and materials price analysis, the steam feed pump investment cost just exceeds electrically driven feed pump investment cost 7%, if considering steam feed pump and related system floor area thereof approximately is 2 times of electrically driven feed pump again, taking up room is 3 times of electrodynamic pump highly at least, and the steam feed pump investment cost exceeds more than 1 times than electrically driven feed pump investment cost; The maintenance cost of electrically driven feed pump only is 25% of steam feed pump in addition.
Passive technology is the new technology that grows up the eighties in 20th century, is characterized in economical, simple and reliable property is high, and the inherent safety of reactor is improved greatly, usually is applied to the generation Ⅲ nuclear power station.Typical Representative heap type is AP1000, APR-1400.The generation Ⅲ nuclear power station AP1000 that China introduces is provided with Heat Discharging System of Chinese, this system is by cooling off a circuit cools agent, the heat of reactor core is derived, as shown in Figure 1, among the figure, 1 is steam generator, 2 is reactor pressure vessel, 3 is the built-in material-changing water tank of containment, and 4 is the passive residual heat removal heat exchanger, and 5 is voltage stabilizer.When non-LOCA event, the passive residual heat removal heat exchanger 4 discharge residual heat of nuclear core of will meeting an urgent need.This heat exchanger is connected to the C type tube bank on the tube sheet by one group and is arranged in top (entrance) and bottom (outlet) end socket forms.The source line of heat exchanger is connected with reactor coolant loop heat pipe section, discharge pipe is connected with the cold chamber of the low head of steam generator 1, and they have formed the natural convection loop of a passive residual heat removal with reactor coolant loop heat pipe section and cold leg.
The utility model content
The purpose of this utility model is in order to improve the security level of nuclear power station, a kind of advanced person's secondary side reactor core heat let-off gear(stand) is provided, with actively combining with non-active technological means, guarantee the long-term derivation of reactor core heat under accident conditions, alleviate the major accident consequence.
The technical solution of the utility model is as follows: a kind of advanced person's secondary side reactor core heat let-off gear(stand), comprise non-energy subsystem and energy subsystem, wherein, described non-energy subsystem comprise several passive residual heat removals series, each passive residual heat removal series is corresponding with the steam generator of a reactor loop, comprise a passive residual heat removal refrigeratory, the upstream vapour line of passive residual heat removal refrigeratory connects the main steam line of steam generator, the solidifying water pipeline in its downstream is connected with the main feed water pipe road of steam generator, the passive residual heat removal refrigeratory places in the accident cooling water tank, also is provided with non-active water supply tank between the solidifying water pipeline of the upstream of passive residual heat removal refrigeratory vapour line and downstream; Described energy subsystem comprise the water supply series of two redundancies, and end of each series that supplies water connects the accident cooling water tank of non-energy subsystem, and the other end is connected with the main feed water pipe road of steam generator.
Further, aforesaid advanced person's secondary side reactor core heat let-off gear(stand), wherein, in two water supply series of described energy subsystem, the series that supplies water comprises the electrodynamic pump of 50% capacity of two parallel connections, and another series that supplies water comprises the pneumatic pump of 50% capacity of two parallel connections; Two electrodynamic pumps are powered by emergency power pack, and two pneumatic pumps are by the main steam pipe steam supply of steam generator main steam isolation valve upstream; After the vent pipe of two electrodynamic pumps and two pneumatic pumps is merged into a female pipe, be connected with the main feed water pipe road of each steam generator respectively.
Further, aforesaid advanced person's secondary side reactor core heat let-off gear(stand), wherein, described can subsystem every electrodynamic pump and the vent pipe of pneumatic pump on be respectively equipped with non-return valve.
Further, aforesaid advanced person's secondary side reactor core heat let-off gear(stand), wherein, in two water supply series of described energy subsystem, each series that supplies water comprises electrodynamic pump of 50% capacity of two parallel connections, four electrodynamic pumps are powered by emergency power pack; After the vent pipe of four electrodynamic pumps is merged into a female pipe, be connected with the main feed water pipe road of each steam generator respectively; Be respectively equipped with non-return valve on the vent pipe of every electrodynamic pump.
Further, aforesaid advanced person's secondary side reactor core heat let-off gear(stand), wherein, the vapour line that is connected with the main steam line of steam generator at described passive residual heat removal refrigeratory is provided with an isolation valve, the solidifying water pipeline that is connected with the main feed water pipe road of steam generator is provided with the isolation valve of two parallel connections, and the isolation valve downstream of two parallel connections arranges a non-return valve.
Further, aforesaid advanced person's secondary side reactor core heat let-off gear(stand), wherein, the pipeline that is connected with the upstream vapour line of passive residual heat removal refrigeratory at described non-active water supply tank is provided with an isolation valve, the pipeline that is connected with the solidifying water pipeline in the downstream of passive residual heat removal refrigeratory is provided with the isolation valve of two parallel connections, and the isolation valve downstream of two parallel connections arranges a non-return valve.
The beneficial effects of the utility model are as follows:
(1) adopts the heat of actively discharging reactor core with the non-secondary side waste heat export plan that actively combines, the security that has improved reactor;
(2) System Assurance is active under accident conditions discharges residual heat of nuclear core efficiently, and under accident conditions long-term non-active discharge residual heat of nuclear core, improve traditional active nuclear power plant to the dependence of safe level power supply, improve the security of power plant;
(3) the accident cooling water tank is set as the resource of water supply of energy subsystem and non-energy subsystem, has integrated the water source configuration, simplified system's setting, saved construction costs;
(4) owing to adopting passive system, can satisfy system multifarious requirement is set, thereby can adopt electrodynamic pump to replace pneumatic pump, not only save substantial contribution in investment cost and maintenance cost, the floor area that also reduces in addition is for layout provides more favourable condition;
(5) greatly reduce the people because of the possibility of error;
(6) the reactor core probability of damage can significantly be reduced and a large amount of radioactivity discharges probability to environment.
Description of drawings
Fig. 1 is the Heat Discharging System of Chinese structural representation of AP1000 in the prior art;
Fig. 2 is the structural representation of advanced person's secondary side reactor core heat let-off gear(stand).
Embodiment
Advanced person's provided by the utility model secondary side reactor core heat let-off gear(stand) in the situation that nuclear power station has an accident, when main water supply facilities can not use, by active mode, relies on the energy subsystem, and the heat in the reactor core is derived.In the situation that station blackout accident and the forfeiture of energy subsystem pneumatic pump occur, non-energy subsystem automatic switching enter operation, and set up stable two-phase natural circulation, a simultaneously circuit cools agent also forms stable natural circulation, and finally the natural circulation by a loop and secondary circuit is delivered to accident cooling water tank as ultimate heat sink with the reactor core heat.
Can subsystem be in the situation that power supply is secure, forcing by feed pump derives residual heat of nuclear core, and non-active design is the density difference that utilizes secondary circuit and the cold and hot working medium of cooling circuit, and the vertical potential difference of cold and hot working medium, sets up Natural Circulation.Adopt actively can tackle under design basis accident and the major accident with the non-scheme that actively combines and lead to water depletion, keep the long-term derivation of reactor core heat.
Non-energy subsystem comprise several passive residual heat removals series, each passive residual heat removal series is corresponding with the steam generator of a reactor loop, comprise a passive residual heat removal refrigeratory, the upstream vapour line of passive residual heat removal refrigeratory connects the main steam line of steam generator, the solidifying water pipeline in its downstream is connected with the main feed water pipe road of steam generator, the passive residual heat removal refrigeratory places in the accident cooling water tank, also is provided with non-active water supply tank between the solidifying water pipeline of the upstream of passive residual heat removal refrigeratory vapour line and downstream.Can subsystem comprise that the water supply of two redundancies is serial, end of each series that supplies water connects the accident cooling water tank of all non-energy subsystem, and the other end is connected with the main feed water pipe road of steam generator.Two series that supply water of energy subsystem can be fetched water from the accident cooling water tank of several passive residual heat removal series respectively.
Adopt is the trend of advanced nuclear power plant design with the security level that the non-secondary side residual heat removal system that actively combines improves nuclear power plant actively, the utility model can guarantee the long-term derivation of reactor core heat under accident conditions, guarantee the integrality of reactor core, alleviated the major accident consequence.
Below in conjunction with drawings and Examples the utility model is described in detail.
Embodiment
As shown in Figure 2, can subsystem there be the water supply of two redundancies serial, in a kind of concrete embodiment, can comprises electrodynamic pump subsystem and pneumatic pump subsystem, and the valve relevant with pump suction pipe and vent pipe etc.Wherein, the series that supplies water comprises the electrodynamic pump 6 of 50% capacity of two parallel connections, and another series that supplies water comprises pneumatic pump 7 of 50% capacity of two parallel connections, is respectively equipped with non-return valve on the vent pipe of every electrodynamic pump and pneumatic pump; Two electrodynamic pumps 6 are by the emergency power pack power supply, and two pneumatic pumps 7 are by the main steam pipe steam supply of steam generator main steam isolation valve upstream; After the vent pipe of two electrodynamic pumps 6 and two pneumatic pumps 7 is merged into a female pipe, can be connected with the main feed water pipe road of many steam generators respectively.Feed pump can absorb water the accident cooling water tank of subsystem from non-.In the situation that lose main feedwater, water pump can provide enough flows, to derive residual heat of nuclear core, prevents that cooling medium from releasing with the steam generator tube sheet exposed by pressurizer relief valve.
When main feed system has an accident, can subsystem put into operation, supply water to steam generator, the heat of reactor coolant loop is passed to secondary coolant circuit system by steam generator, and secondary coolant circuit system enters condenser by the steam turbine bypass system or cools off discharged to atmosphere.Derive like this residual heat of nuclear core, until reactor coolant loop reaches the operating mode that normal residual heat removal system can put into operation.
In the another kind of embodiment of energy subsystem, two pneumatic pumps are substituted with electrodynamic pump, be the electrodynamic pump that each series that supplies water comprises 50% capacity of two parallel connections, four electrodynamic pumps are powered by emergency power pack, are respectively equipped with non-return valve on the vent pipe of every electrodynamic pump; After the vent pipe of four electrodynamic pumps is merged into a female pipe, can be connected with the main feed water pipe road of many steam generators respectively.This mode can obviously reduce investment and the maintenance cost of equipment, and reduces the floor area of system.Can why can adopt electrodynamic pump to substitute pneumatic pump in the subsystem, realize the reduction of cost, mainly be that the system that guaranteed arranges multifarious requirement because the combination of non-energy subsystem arranges.
Non-energy subsystem comprise several passive residual heat removals series, the steam generator secondary side of each loop of reactor arranges a passive residual heat removal series, each series comprises a passive residual heat removal refrigeratory 13, the upstream vapour line of passive residual heat removal refrigeratory 13 connects the main steam line 10 of steam generator 8, the solidifying water pipeline in its downstream is connected with the main feed water pipe road 9 of steam generator 8, passive residual heat removal refrigeratory 13 places in the accident cooling water tank 12, also is provided with non-active water supply tank 11 between the solidifying water pipeline of the upstream of passive residual heat removal refrigeratory 13 vapour line and downstream.
Occuring under station blackout accident and the energy subsystem pneumatic pump series inefficacy operating mode, non-can subsystem putting into operation, under the prerequisite of the fuel design limit value that is no more than regulation and coolant pressure boundary design condition, derive the heat accumulation of residual heat of nuclear core and each equipment of reactor coolant loop, in 72 hours, reactor maintained safe shutdown state.
Vapour line links to each other with passive residual heat removal refrigeratory 13 inlet connection mouths, and passive residual heat removal refrigeratory 13 is arranged in the accident cooling water tank 12.During whole service, require passive residual heat removal refrigeratory 13 to be immersed in the water, do not allow to expose.Solidifying water pipe is drawn by the passive residual heat removal cooler outlet, and solidifying pipe outlet links to each other with the auxiliary feedwater pipeline with the main feed water pipe road of steam generator.Be provided with the pneumatic isolation valve in normal pass of two parallel connections on the solidifying waterpipe, isolation during the realization system reserve, solidifying water pipeline can be communicated with smoothly when guaranteeing simultaneously to drop in the needs system, and the downstream arranges a non-return valve, to prevent that the steam generator feedwater is by solidifying waterpipe by-pass flow.
The vapour line that is connected with the main steam line 10 of steam generator 8 at described passive residual heat removal refrigeratory 13 is provided with an electronic isolation valve, the unit normal operation period, electronic isolation valve on system's vapour line keeps often opening, pneumatic isolation valve on the solidifying water pipeline keeps normal and closes, and passive residual heat removal cooler tube side is full of water.After system's input signal sends, pneumatic isolation valve on the solidifying water pipeline is opened, system puts into operation, water in the passive residual heat removal cooler tube injects steam generator secondary side under Action of Gravity Field, become steam after being heated by residual heat of nuclear core, steam enters in the passive residual heat removal cooler tube, carry out exchange heat with the chilled water in the accident cooling 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.Water in the accident cooling water tank is owing to continuing reduced by thermal evaporation, and its water capacity can guarantee system's continuous service 72 hours.
Each series arranges a non-active water supply tank 11, its top links to each other with the upstream vapour line of passive residual heat removal refrigeratory 13 by an isolation valve, and the bottom links to each other with the solidifying water pipeline in the downstream of passive residual heat removal refrigeratory with a non-return valve by two isolation valves that are arranged in parallel.When system put into operation, the water steam injection generator secondary side in the non-active water supply tank was with the forfeiture of compensation steam generator secondary side steam and the contraction of water volume.
Under station blackout accident stack energy subsystem pneumatic pump failure accidents operating mode, because main pump is stopped transport, non-energy subsystem utilize system in the temperature difference and the difference in height of reactor part and steam generator part, has certain natural-circulation capacity, with the heat of reactor to the steam generator transmission, finish the Natural Circulation in reactor coolant loop, derive residual heat of nuclear core, ensure the safety of reactor core.
The utility model combines active system and passive system, has improved on the whole the security of nuclear power station under the accident conditions.Simultaneously, the structure of system is optimized design, the accident cooling water tank has been integrated the water source configuration as can subsystem and non-resource of water supply that can subsystem, has simplified system's setting, has saved construction costs.In addition, owing to having adopted passive system, can satisfy system multifarious requirement is set, can subsystem can improve accordingly design, replace pneumatic pump with electrodynamic pump, on investment cost and maintenance cost, can save substantial contribution, and reduce floor area, for system layout provides more favourable condition.
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. an advanced person secondary side reactor core heat let-off gear(stand), it is characterized in that: comprise non-energy subsystem and energy subsystem, described non-energy subsystem comprise several passive residual heat removals series, each passive residual heat removal series is corresponding with the steam generator of a reactor loop, comprise a passive residual heat removal refrigeratory (13), the upstream vapour line of passive residual heat removal refrigeratory (13) connects the main steam line (10) of steam generator (8), the solidifying water pipeline in its downstream is connected with the main feed water pipe road (9) of steam generator (8), passive residual heat removal refrigeratory (13) places in the accident cooling water tank (12), also is provided with non-active water supply tank (11) between the solidifying water pipeline of upstream vapour line and downstream of passive residual heat removal refrigeratory (13); Described energy subsystem comprise the water supply series of two redundancies, and end of each series that supplies water connects the accident cooling water tank (12) of non-energy subsystem, and the other end is connected with the main feed water pipe road (9) of steam generator.
2. advanced person's as claimed in claim 1 secondary side reactor core heat let-off gear(stand), it is characterized in that: in two water supply series of described energy subsystem, the series that supplies water comprises the electrodynamic pump (6) of 50% capacity of two parallel connections, and another series that supplies water comprises the pneumatic pump (7) of 50% capacity of two parallel connections; Two electrodynamic pumps (6) are by the emergency power pack power supply, and two pneumatic pumps (7) are by the main steam pipe steam supply of steam generator main steam isolation valve upstream; After the vent pipe of two electrodynamic pumps and two pneumatic pumps is merged into a female pipe, be connected with the main feed water pipe road of each steam generator respectively.
3. advanced person's as claimed in claim 2 secondary side reactor core heat let-off gear(stand) is characterized in that: described can subsystem every electrodynamic pump and the vent pipe of pneumatic pump on be respectively equipped with non-return valve.
4. advanced person's as claimed in claim 1 secondary side reactor core heat let-off gear(stand), it is characterized in that: in two water supply series of described energy subsystem, each series that supplies water comprises the electrodynamic pump of 50% capacity of two parallel connections, and four electrodynamic pumps are powered by emergency power pack; After the vent pipe of four electrodynamic pumps is merged into a female pipe, be connected with the main feed water pipe road of each steam generator respectively.
5. advanced person's as claimed in claim 4 secondary side reactor core heat let-off gear(stand) is characterized in that: be respectively equipped with non-return valve on the vent pipe of every electrodynamic pump of described energy subsystem.
6. advanced person's as claimed in claim 1 secondary side reactor core heat let-off gear(stand), it is characterized in that: be provided with an isolation valve at described passive residual heat removal refrigeratory (13) with the vapour line that the main steam line (10) of steam generator is connected, the solidifying water pipeline that is connected with the main feed water pipe road (9) of steam generator is provided with the isolation valve of two parallel connections, and the isolation valve downstream of two parallel connections arranges a non-return valve.
7. advanced person's as claimed in claim 1 secondary side reactor core heat let-off gear(stand), it is characterized in that: be provided with an isolation valve at described non-active water supply tank (11) with the pipeline that the upstream vapour line of passive residual heat removal refrigeratory (13) is connected, the pipeline that is connected with the solidifying water pipeline in the downstream of passive residual heat removal refrigeratory (13) is provided with the isolation valve of two parallel connections, and the isolation valve downstream of two parallel connections arranges a non-return valve.
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| CN2012205044093U CN202887750U (en) | 2012-09-27 | 2012-09-27 | Advanced secondary side reactor core heat leading-out device |
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| CN2012205044093U CN202887750U (en) | 2012-09-27 | 2012-09-27 | Advanced secondary side reactor core heat leading-out device |
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Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102903402A (en) * | 2012-09-27 | 2013-01-30 | 中国核电工程有限公司 | Advanced secondary side core heat lead-out device |
| WO2014048289A1 (en) * | 2012-09-27 | 2014-04-03 | 中国核电工程有限公司 | Combined active and passive secondary-side reactor core heat removal apparatus |
| CN105070327A (en) * | 2015-08-31 | 2015-11-18 | 上海核工程研究设计院 | Nuclear power station secondary side long-term waste heat removal system |
| CN117095840A (en) * | 2023-06-16 | 2023-11-21 | 哈尔滨工程大学 | Self-supporting passive waste heat discharging system of floating nuclear power station |
-
2012
- 2012-09-27 CN CN2012205044093U patent/CN202887750U/en not_active Expired - Lifetime
Cited By (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102903402A (en) * | 2012-09-27 | 2013-01-30 | 中国核电工程有限公司 | Advanced secondary side core heat lead-out device |
| WO2014048289A1 (en) * | 2012-09-27 | 2014-04-03 | 中国核电工程有限公司 | Combined active and passive secondary-side reactor core heat removal apparatus |
| GB2521549A (en) * | 2012-09-27 | 2015-06-24 | China Nuclear Power Eng Co Ltd | Combined active and passive secondary-side reactor core heat removal apparatus |
| GB2521549B (en) * | 2012-09-27 | 2018-08-08 | China Nuclear Power Eng Co Ltd | Combined active and passive secondary-side reactor core heat removal apparatus |
| CN105070327A (en) * | 2015-08-31 | 2015-11-18 | 上海核工程研究设计院 | Nuclear power station secondary side long-term waste heat removal system |
| CN117095840A (en) * | 2023-06-16 | 2023-11-21 | 哈尔滨工程大学 | Self-supporting passive waste heat discharging system of floating nuclear power station |
| CN117095840B (en) * | 2023-06-16 | 2024-05-10 | 哈尔滨工程大学 | Self-supporting passive waste heat discharging system of floating nuclear power station |
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Granted publication date: 20130417 |