CN102867548A - Active and passive combined secondary side reactor core heat derivation device - Google Patents
Active and passive combined secondary side reactor core heat derivation device Download PDFInfo
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- CN102867548A CN102867548A CN2012103704106A CN201210370410A CN102867548A CN 102867548 A CN102867548 A CN 102867548A CN 2012103704106 A CN2012103704106 A CN 2012103704106A CN 201210370410 A CN201210370410 A CN 201210370410A CN 102867548 A CN102867548 A CN 102867548A
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/18—Emergency cooling arrangements; Removing shut-down heat
- G21C15/182—Emergency cooling arrangements; Removing shut-down heat comprising powered means, e.g. pumps
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/18—Emergency cooling arrangements; Removing shut-down heat
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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 invention belongs to a reactor design technology, and in particular relates to an active and passive combined secondary side reactor core heat derivation device. The device comprises an auxiliary water supply system and a secondary side passive residual heat exhaust system, wherein the auxiliary water supply system comprises two redundant water supply series, one end of each water supply series is connected with an auxiliary water supply tank, and the other end of each water supply series is connected with a main water supply pipeline of a steam generator; the secondary side passive residual heat exhaust system comprises a plurality of passive residual heat exhaust series, each passive residual heat exhaust series comprises a passive residual heat exhaust cooler arranged in an accident cooling water tank, the upstream steam pipeline of each passive residual heat exhaust series is connected with a main steam pipeline of the steam generator, and the downstream steam pipeline of each passive residual heat exhaust series is connected with a main water supply pipeline of the steam generator; and a passive water make-up tank is arranged between the upstream steam pipeline and the downstream condensate pipeline of the passive residual heat exhaust cooler. According to the active and passive combined secondary side reactor core heat derivation device, reactor core heat in an accident situation can be conducted out in long term, and serious accident results can be relieved.
Description
Technical field
The invention belongs to the reactor designing technique, be specifically related to a kind of actively with the non-secondary side reactor core heat let-off gear(stand) that actively combines.
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.
Summary of the invention
The objective of the invention is in order to improve the security level of nuclear power station, a kind of active and the non-secondary side reactor core heat let-off gear(stand) that actively combines are provided, guarantee the long-term derivation of reactor core heat under accident conditions, alleviation major accident consequence.
Technical scheme of the present invention is as follows: a kind of actively with the non-secondary side reactor core heat let-off gear(stand) that actively combines, comprise auxiliary feedwater system and Passive residual heat removal system, wherein, described auxiliary feedwater system comprises the water supply series of two redundancies, one end of each series that supplies water connects auxiliary feed-water tank, and the other end is connected with the main feed water pipe road of steam generator; Described Passive residual heat removal system comprises several passive residual heat removal 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.
Further, aforesaid actively with the non-secondary side reactor core heat let-off gear(stand) that actively combines, wherein, in two water supply series of described auxiliary feedwater system, 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 actively with the non-secondary side reactor core heat let-off gear(stand) that actively combines, wherein, be respectively equipped with non-return valve on every electrodynamic pump of described auxiliary feedwater system and the vent pipe of pneumatic pump.
Further, aforesaid actively with the non-secondary side reactor core heat let-off gear(stand) that actively combines, wherein, in two water supply series of described auxiliary feedwater system, 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; Be respectively equipped with non-return valve on the vent pipe of every electrodynamic pump.
Further, aforesaid actively with the non-secondary side reactor core heat let-off gear(stand) that actively combines, 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 actively with the non-secondary side reactor core heat let-off gear(stand) that actively combines, 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.
Beneficial effect of the present invention is 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) 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;
(4) greatly reduce the people because of the possibility of error;
(5) 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 structural representation active and the non-secondary side reactor core heat let-off gear(stand) that actively combines.
Embodiment
Active and the non-secondary side reactor core heat let-off gear(stand) that actively combines provided by the present invention, in the situation that nuclear power station has an accident, when main water supply facilities can not use, by active mode, the dependence auxiliary feedwater system was derived the heat in the reactor core.In the situation that station blackout accident and the forfeiture of auxiliary feedwater system pneumatic pump occur, non-active secondary side residual heat removal system puts into operation automatically, 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.
Active system is in the situation that power supply is secure, and forcing by auxiliary feed water 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 active scheme with non-active combination can tackle under design basis accident and the major accident main to water depletion, keep the long-term derivation of reactor core heat.
Active auxiliary feedwater system comprises the water supply series of two redundancies, and an end of each series that supplies water connects auxiliary feed-water tank, and the other end is connected with the main feed water pipe road of steam generator.Passive residual heat removal system comprises several passive residual heat removal 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.
Adopting 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, guarantees the long-term derivation of reactor core heat under accident conditions, has guaranteed the integrality of reactor core, alleviates the major accident consequence.
Below in conjunction with drawings and Examples the present invention is described in detail.
Embodiment
As shown in Figure 2, auxiliary feedwater system has the water supply series of two redundancies, in a kind of concrete embodiment, can comprise 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 7 of 50% capacity of two parallel connections, and another series that supplies water comprises pneumatic pump 8 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 7 are by the emergency power pack power supply, and two pneumatic pumps 8 are by the main steam pipe steam supply of steam generator main steam isolation valve upstream; After the vent pipe of two electrodynamic pumps 7 and two pneumatic pumps 8 is merged into a female pipe, can be connected with the main feed water pipe road of many steam generators respectively.Auxiliary feed water pump absorbs water from auxiliary feed-water tank.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, auxiliary feedwater system puts 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 auxiliary feedwater system, 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.Why can adopt electrodynamic pump to substitute pneumatic pump in the auxiliary feedwater system, realize the reduction of cost, mainly be that the system that guaranteed arranges multifarious requirement because the combination of Passive residual heat removal system arranges.
Passive residual heat removal system comprises several passive residual heat removal 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 14, the upstream vapour line of passive residual heat removal refrigeratory 14 connects the main steam line 11 of steam generator 9, the solidifying water pipeline in its downstream is connected with the main feed water pipe road 10 of steam generator 9, passive residual heat removal refrigeratory 14 places in the accident cooling water tank 13, also is provided with non-active water supply tank 12 between the solidifying water pipeline of the upstream of passive residual heat removal refrigeratory 14 vapour line and downstream.
Occuring under station blackout accident and the auxiliary feedwater system pneumatic pump series inefficacy operating mode, non-active secondary side residual heat removal system puts 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 14 inlet connection mouths, and passive residual heat removal refrigeratory 14 is arranged in the accident cooling water tank 13.During whole service, require passive residual heat removal refrigeratory 14 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 11 of steam generator 9 at described passive residual heat removal refrigeratory 14 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 12, its top links to each other with the upstream vapour line of passive residual heat removal refrigeratory 14 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 auxiliary feedwater system pneumatic pump failure accidents operating mode, because main pump is stopped transport, non-active secondary side residual heat removal system utilizes 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 present invention combines active auxiliary feedwater system and non-active secondary side residual heat removal system, has improved on the whole the security of nuclear power station under the accident conditions.Simultaneously, owing to having adopted passive system, can satisfy system multifarious requirement is set, auxiliary feedwater system can improve design accordingly, 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 present invention and not break away from the spirit and scope of the present invention.Like this, if of the present invention these are revised and modification belongs within the scope of claim of the present invention and equivalent technology thereof, then the present invention also is intended to comprise these changes and modification interior.
Claims (7)
- One kind actively with the non-secondary side reactor core heat let-off gear(stand) that actively combines, it is characterized in that: comprise auxiliary feedwater system and Passive residual heat removal system, described auxiliary feedwater system comprises the water supply series of two redundancies, one end of each series that supplies water connects auxiliary feed-water tank (6), and the other end is connected with the main feed water pipe road (10) of steam generator; Described Passive residual heat removal system comprises several passive residual heat removal series, each passive residual heat removal series is corresponding with the steam generator of a reactor loop, comprise a passive residual heat removal refrigeratory (14), the upstream vapour line of passive residual heat removal refrigeratory (14) connects the main steam line (11) of steam generator (9), the solidifying water pipeline in its downstream is connected with the main feed water pipe road (10) of steam generator (9), passive residual heat removal refrigeratory (14) places in the accident cooling water tank (13), also is provided with non-active water supply tank (12) between the solidifying water pipeline of upstream vapour line and downstream of passive residual heat removal refrigeratory (14).
- As claimed in claim 1 actively with the non-secondary side reactor core heat let-off gear(stand) that actively combines, it is characterized in that: in two water supply series of described auxiliary feedwater system, the series that supplies water comprises the electrodynamic pump (7) of 50% capacity of two parallel connections, and another series that supplies water comprises the pneumatic pump (8) of 50% capacity of two parallel connections; Two electrodynamic pumps (7) are by the emergency power pack power supply, and two pneumatic pumps (8) 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.
- As claimed in claim 2 actively with the non-secondary side reactor core heat let-off gear(stand) that actively combines, it is characterized in that: be respectively equipped with non-return valve on every electrodynamic pump of described auxiliary feedwater system and the vent pipe of pneumatic pump.
- As claimed in claim 1 actively with the non-secondary side reactor core heat let-off gear(stand) that actively combines, it is characterized in that: in two water supply series of described auxiliary feedwater system, 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.
- As claimed in claim 4 actively with the non-secondary side reactor core heat let-off gear(stand) that actively combines, it is characterized in that: be respectively equipped with non-return valve on the vent pipe of every electrodynamic pump of described auxiliary feedwater system.
- As claimed in claim 1 actively with the non-secondary side reactor core heat let-off gear(stand) that actively combines, it is characterized in that: be provided with an isolation valve at described passive residual heat removal refrigeratory (14) with the vapour line that the main steam line (11) of steam generator is connected, the solidifying water pipeline that is connected with the main feed water pipe road (10) 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.
- As claimed in claim 1 actively with the non-secondary side reactor core heat let-off gear(stand) that actively combines, it is characterized in that: be provided with an isolation valve at described non-active water supply tank (12) with the pipeline that the upstream vapour line of passive residual heat removal refrigeratory (14) is connected, the pipeline that is connected with the solidifying water pipeline in the downstream of passive residual heat removal refrigeratory (14) is provided with the isolation valve of two parallel connections, and the isolation valve downstream of two parallel connections arranges a non-return valve.
Priority Applications (5)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| MYPI2015700866A MY187908A (en) | 2012-09-27 | 2012-09-27 | Combined active and passive secondary-side reactor core heat removal apparatus |
| CN2012103704106A CN102867548A (en) | 2012-09-27 | 2012-09-27 | Active and passive combined secondary side reactor core heat derivation device |
| GB1504150.2A GB2521549B (en) | 2012-09-27 | 2013-09-24 | Combined active and passive secondary-side reactor core heat removal apparatus |
| PCT/CN2013/084038 WO2014048289A1 (en) | 2012-09-27 | 2013-09-24 | Combined active and passive secondary-side reactor core heat removal apparatus |
| ZA2015/02770A ZA201502770B (en) | 2012-09-27 | 2015-04-23 | Combined active and passive secondary-side reactor core heat removal apparatus |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2012103704106A CN102867548A (en) | 2012-09-27 | 2012-09-27 | Active and passive combined secondary side reactor core heat derivation device |
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| Publication Number | Publication Date |
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| CN102867548A true CN102867548A (en) | 2013-01-09 |
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Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
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| CN2012103704106A Pending CN102867548A (en) | 2012-09-27 | 2012-09-27 | Active and passive combined secondary side reactor core heat derivation device |
Country Status (5)
| Country | Link |
|---|---|
| CN (1) | CN102867548A (en) |
| GB (1) | GB2521549B (en) |
| MY (1) | MY187908A (en) |
| WO (1) | WO2014048289A1 (en) |
| ZA (1) | ZA201502770B (en) |
Cited By (12)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103267423A (en) * | 2013-05-10 | 2013-08-28 | 中国核电工程有限公司 | Heat exchanger in nuclear power plant containment vessel |
| 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 |
| CN103810930A (en) * | 2014-02-18 | 2014-05-21 | 中国核动力研究设计院 | Thermal hydraulic feature experimental simulation device for secondary side passive residual heat removal system |
| CN104464846A (en) * | 2014-12-03 | 2015-03-25 | 中广核工程有限公司 | Passive high-order emergency cooling water supply system for nuclear power plant |
| 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 |
| CN105957567A (en) * | 2016-05-06 | 2016-09-21 | 中国核动力研究设计院 | Steam generator secondary side passive residual heat removal system |
| CN106653109A (en) * | 2016-12-30 | 2017-05-10 | 福建福清核电有限公司 | Experimental research device for secondary side passive residual heat removal system (PRS) |
| CN111128414A (en) * | 2019-12-31 | 2020-05-08 | 中国核动力研究设计院 | Active and passive combined safety system and method for nuclear power plant |
| CN111785400A (en) * | 2020-06-24 | 2020-10-16 | 武汉润德工程技术有限公司 | Self-oscillation passive waste heat discharging device and method |
| WO2021213415A1 (en) * | 2020-04-24 | 2021-10-28 | 上海核工程研究设计院有限公司 | Reactor secondary side passive residual 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 |
| WO2023231358A1 (en) * | 2022-06-02 | 2023-12-07 | 中广核研究院有限公司 | Double-loop small pressurized water reactor emergency residual heat removal system |
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| Publication number | Priority date | Publication date | Assignee | Title |
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| CN111370153B (en) * | 2020-03-09 | 2022-07-29 | 苏州热工研究院有限公司 | Passive pulse cooling method and system for nuclear power plant |
| CN113793705B (en) * | 2021-08-16 | 2023-03-07 | 西安交通大学 | Experimental device and method for passive emergency waste heat removal system of lead-bismuth fast reactor |
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- 2013-09-24 GB GB1504150.2A patent/GB2521549B/en active Active
- 2013-09-24 WO PCT/CN2013/084038 patent/WO2014048289A1/en active Application Filing
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Also Published As
| Publication number | Publication date |
|---|---|
| GB201504150D0 (en) | 2015-04-29 |
| MY187908A (en) | 2021-10-28 |
| GB2521549A (en) | 2015-06-24 |
| GB2521549B (en) | 2018-08-08 |
| ZA201502770B (en) | 2016-02-24 |
| GB2521549A8 (en) | 2018-07-18 |
| WO2014048289A1 (en) | 2014-04-03 |
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