GB2521549A - Combined active and passive secondary-side reactor core heat removal apparatus - Google Patents
Combined active and passive secondary-side reactor core heat removal apparatus Download PDFInfo
- Publication number
- GB2521549A GB2521549A GB1504150.2A GB201504150A GB2521549A GB 2521549 A GB2521549 A GB 2521549A GB 201504150 A GB201504150 A GB 201504150A GB 2521549 A GB2521549 A GB 2521549A
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- GB
- United Kingdom
- Prior art keywords
- passive
- steam
- heat removal
- residual heat
- driven 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
- G21C15/182—Emergency cooling arrangements; Removing shut-down heat comprising powered means, e.g. pumps
-
- 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
-
- 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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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
Disclosed is a combined active and passive secondary-side reactor core heat removal apparatus, comprising an auxiliary water supply system and a secondary-side passive afterheat discharge system, wherein the auxiliary water supply system comprises two redundant water supply series, one end of each water supply series being connected to an auxiliary water supply tank (6), and the other end being connected to a main water supply pipe (10) of a steam generator (9); and the secondary-side passive afterheat discharge system comprises several passive afterheat discharge series, each passive afterheat discharge series comprising a passive afterheat discharge cooler (14) arranged in an emergency cooling water tank (13), the upstream steam pipeline thereof being connected to a main steam pipe (11) of the steam generator, the downstream condensed water pipeline thereof being connected to the main water supply pipe (10) of the steam generator, and a passive supplementary water tank (12) further being provided between the upstream steam pipeline and the downstream condensed water pipeline of the passive afterheat discharge cooler. The apparatus can ensure that heat from the reactor core can be removed in the long-term in an emergency situation, alleviating serious consequences from an emergency.
Description
COMBINED ACTIVE AND PASSIVE SECONDARY-SIDE REACTOR
CORE HEAT REMOVAL APPARATUS
Technical Field
The present invention relates to reactor design technology, and more particularly, to a combined active and passive secondary-side reactor core heat removal apparatus.
Description of Related Art
After a reactor is shut down, the heat generated from the core residual fission and the decay of fission products is required to be removed for a long time, otherwise coolant boiling and even severe accidents, e.g., core meltdown, may occur. In the design of conventional pressurized water reactor power plants, the way of steam generators make-up water usually is adopted by an active manner.
The active secondary-side residual heat removal system which operates in such a manner that, when the power supply is always available, auxiliary feedwater pumps are employed to drive forced circulation of secondary-side feedwater of steam generators to remove residual heat of the cores which is delivered to the ultimate heat sink. The active secondary-side residual heat removal system is characterized by high heat exchange efficiency. However, in the event of a station blackout, both the nonnal power supply and reliable power supply are lost, causing lost of the system to remove residual heat from the cores. Therefore, the active secondary-side residual heat removal system is significantly affected by the power supply reliability and, consequently, has unsatisfactory safety performance.
The conventional active secondary-side residual heat removal system adopts on a combination of steam-driven pumps and motor-driven pumps. With the development of technology, the disadvantage of steam-driven pumps becomes the more and more prominent. Focus on the prices of equipment and materials, a steam-driven feedwater pump costs 7% more than a motor-driven pump, which, when coupled with the fact that a steam-driven feedwater pump together with its associated systems occupies land area twice as large as that of a motor-driven feedwater pump and is at least three times higher than that of a motor-driven pump, causes the capital cost of a steam-driven feedwater pump to be more than twice that of a motor-driven pump. Furthermore, the maintenance cost of a motor-driven feedwater pump is only 25% that of a steam-driven feedwater pump.
The passive technology is developed in l980s and is typically used in the third-generation nuclear power plants due to its economy, simplicity and high reliability which have contributed to significant improvement of the inherent safety of cores. The representative reactor types in this respect are API000 and APR-1400. The AP 1000 third-generation nuclear power plants imported by China have been equipped with passive residual heat removal systems in which the coolant in the primary circuit is cooled down thereby removing heat of the cores.
As shown in Fig. 1, 1 for identifies a steam generator, 2 for a reactor pressure vessel, 3 for a built-in refueling water tank of containment, 4 for a passive residual heat removal exchanger and 5 for a pressurizer. In case of an event other than LOCA, the passive residual heat removal exchanger 4 removes residual heat from cores in emergency. The heat exchanger is comprised of a group of C-shaped tube bundle connected to a tube sheet, an upper (inlet) head and a bottom (outlet) head. An inlet line of the heat exchanger is connected with a hot leg of the reactor coolant system and an outlet line of the heat exchanger is connected with a cold plenum of the lower head of the steam generator 1, all of which, plus the hot leg and cold leg of the reactor coolant system, comprises a natural circulation loop for passive residual heat removal.
Brief Summary of the Invention
The objective of the present invention is to improve the safety level of nuclear power plants by providing a combined active and passive secondary-side reactor core heat removal apparatus which allows heat from cores to be removed for a long time under emergency conditions thereby mitigating the consequence of a severe accident.
To achieve the objective described above, the present invention employs the technical solutions below: A combined active and passive secondary-side reactor core heat removal apparatus, comprising an active subsystem and a secondary-side passive residual heat removal system, wherein the active subsystem comprises two redundant water supply trains, each of which is connected to an auxiliary feedwater tank at one end and to a main feedwater piping of a steam generator at the other end; the secondary-side passive residual heat removal system comprises a plurality of passive residual heat removal trains, each of which corresponds to a steam generator for each reactor ioop and comprises one passive residual heat removal cooler, a upstream steam line of the passive residual heat removal cooler is connected to a main steam piping of the steam generator, a downstream condensate line of the passive residual heat removal cooler is connected to the main feedwater piping of the steam generator, the passive residual heat removal cooler is disposed within an emergency cooling water tank, a passive make-up water tank is disposed between the upstream steam line and the downstream condensate line of the passive residual heat removal cooler.
Further, the said combined active and passive secondary-side reactor core heat removal apparatus, wherein, of the two water supply trains of the active subsystem, one water supply train comprises two 50% capacity motor-driven pumps connected in parallel, the other water supply train comprises two 50% steam-driven pumps connected in parallel; the two motor-driven pumps are powered by an emergency power supply system, the two steam-driven pumps have steam supplied from a upstream main steam line of a main steam isolation valve of the steam generator; discharge pipes of the two motor-driven pumps and the two steam-driven pumps are combined into one header which is respectively connected to main feedwater piping of individual steam generators.
Further, the said combined active and passive secondary-side reactor core heat removal apparatus, wherein a check valve is respectively installed on a discharge pipe of each of the motor-driven pmnps and each of the steam-driven pumps of the active subsystem.
Further, the said combined active and passive secondary-side reactor core heat removal apparatus, wherein, each of the two water supply trains comprises two 50% motor-driven pumps connected in parallel, the four motor-driven pumps are powered by an emergency power supply system; discharge pipes of the four motor-driven pumps are combined into one header which is respectively connected to a main feedwater piping of individual steam generators; a check valve is respectively disposed on a discharge pipe of each of the motor-driven pumps.
Further, the said combined active and passive secondary-side reactor core heat removal apparatus, wherein one isolation valve is disposed on a steam line through which the passive residual heat removal cooler is connected to the main steam piping of the steam generator, two parallel-connected isolation valves are disposed on the condensate line connected to the main feedwater piping of the steam generator, one check valve is disposed at downstream of the two parallel-connected isolation valves.
Further, the said combined active and passive secondary-side reactor core heat removal apparatus, wherein one isolation valve is disposed on line through which the passive make-up water tank is connected to the upstream steam line of the passive residual heat removal cooler, two parallel-connected isolation valves are disposed on a line through which the passive make-up water tank is connected to the downstream condensate line of the passive residual heat removal cooler, one check valve is disposed at downstream of the two parallel-connected isolation valve.
The advantageous effects of the present invention are as follows: (I) The adoption of a combination of active and passive secondary-side residual heat removal solution to remove heat generated by cores results in increased safety of reactors; (2) The system not only allows active efficient removal of residual heat from cores under emergency conditions, but also allows long-term passive removal of residual heat from cores under emergency conditions, thus mitigating the reliance of conventional active nuclear power plants on safety-class power supply system and resulting in increased safety of power plants; (3) The use of a passive system allows more system arrangement modes, making it possible to employ motor-driven pumps instead of steam-driven pump.
This can not only reduce a lot of money spent on investment and maintenance of the system, but also reduce the occupied space of the system, creating more desirable condition for the system arrangement; (4) The possibility of human factors is greatly reduced; (5) The probability of core damage as well as release of larger amount of radioactivity to the environment can be significantly reduced.
Brief Description of the Several Views of the Drawings Fig. 1 shows a structural schematic diagram of a prior-art passive residual heat removal system of AP 1000; and Fig.2 shows a structural schematic diagram of a combined active and passive secondary-side reactor core heat removal apparatus.
Detailed Description of the Invention
In case a nuclear power plant suffers from an accident which leads to malfunction of the main feedwater facilities, the combined active and passive secondary-side reactor core heat removal apparatus in the present invention can rely upon the active subsystem to remove the heat from the cores in an active manner In the event of a station blackout where the steam-driven pumps of the active subsystem are lost, the passive secondary-side residual heat removal system is automatically put into service to establish stable two-phase natural circulation flow and stable natural circulation flow of the primary coolant is also established.
As a result, the natural circulation flow of both the primary circuit and secondary circuit transfers the heat from cores to the emergency cooling water tank of the ultimate heat sink.
Depend on the reliability of the power supply, an active subsystem operates in such a manner that feedwater pumps are employed to force residual heat to be removed from cores. In contrast, in case of a passive design, the density difference between the cold and hot working medium in the secondary circuit and cooling circuit as well as the vertical elevation difference between the cold and hot working medium allow a natural circulation to be established. The use of a combined active and passive solution can deal with the situation where the main feedwater system is lost during design basis accident and severe accident and maintain long-term removal of the heat from cores.
* The the active subsystem comprises two redundant water supply trains, each of which is connected to an auxiliary feedwater tank at one end and to a main feedwater piping of a steam generator at the other end; the secondary-side passive residual heat removal system comprises a plurality of passive residual heat removal trains, each of which corresponds to a steam generator of a reactor ioop and comprises one passive residual heat removal cooler, a upstream steam line of the passive residual heat removal cooler is connected to a main steam piping of the steam generator, a downstream condensate line of the passive residual heat removal cooler is connected to the main feedwater piping of the steam generator, the passive residual heat removal cooler is disposed within an emergency cooling water tank, a passive make-up water tank is disposed between the upstream steam line and the downstream condensate line of the passive residual heat removal cooler.
The use of combined active and passive secondary-side residual heat removal system to improve the safety level of nuclear power plants is the trend in design of advanced nuclear power plants. It enables long-term removal of the heat from cores in the event of accidents, ensuring the integrity of cores and mitigating the consequence of severe accidents.
Below is a detailed description of the present invention in connection with the accompanying drawings and the preferred embodiments.
Embodiments: As shown in Fig.2, an active subsystem comprises two redundant water supply trains. In one preferred embodiment, the active subsystem may comprise a motor-driven pump subsystem and a steam-driven pump subsystem as well as the valves associated with the suction piping and discharge piping of the pumps. One water supply train comprises two parallel-connected 50% capacity motor-driven pumps 7 and the other water supply train comprises two parallel-connected 50% capacity steam-driven pumps 8. A check valve is respectively disposed on the discharge piping of each of the motor-driven pumps and steam-driven pumps.
The two motor-driven pumps 7 are powered by an emergency power supply system.
The two steam-driven pumps 8 have steam supplied through a main steam line at upstream of a main steam isolation valve of the steam generator; the discharge pipes of the two motor-driven pumps 7 and two steam-driven pumps 8 are combined into one header which is respectively connected to the main feedwater piping of a plurality of steam generators. An auxiliary feedwater pump sucks water from an auxiliary feedwater tank. In case the main feedwater system is lost, the water pump is able to supply a sufficient flow to remove the residual heat from cores and prevent leakage of coolant from pressurizer and exposure of tube sheet of the steam generator.
In case the main feedwater system fails, the the active subsystem is put into service to supply water to the steam generator. The heat from the reactor coolant system is transferred through the steam generator to the secondary circuit system, which, in turn, discharges steam into the condenser through the turbine bypass or to atmosphere for cooling down. In this way, the residual heat from cores is removed until the reactor coolant system meets the operating condition where the normal residual heat removal system can be put into service.
In another mode of implementing the active subsystem, the two steam-driven pumps are replaced with motor-driven pumps, i.e., each of the water supply train comprises two parallel-connected SO% capacity motor-driven pumps. The four motor-driven pumps are powered by an emergency power supply A check valve is respectively disposed on the discharge pipe of each of the motor-driven pumps.
The discharge pipes of the four motor-driven pumps are combined into one header which may be respectively connected to the main feedwater piping of a plurality of steam generators. This can considerably decrease the capital and maintenance costs of the equipment and reduce the land occupation of the system. The reason why the steam-driven pumps can be replaced with motor-driven pumps in the active subsystem to reduce the costs mainly lies in the configuration of the combined active and passive secondary-side residual hcat removal system which allows more system arrangement modes to be employed.
The secondary-side passive residual heat removal system comprises a plurality of passive residual heat removal trains. The secondary side of the steam generator of each reactor loop is provided with one passive residual heat removal train which comprises one passive residual heat removal cooler 14. The upstream steam fine of the passive residual heat removal cooler 14 is connected to the main steam piping 11 of the steam generator 9 and the downstream condensate line of the passive residual heat removal cooler 14 is connected to the main feedwater piping of the steam generator 9. The passive residual heat removal cooler 14 is disposed in the accident cooling water tank 13. The passive make-up water tank 12 is disposed between the upstream steam line and the downstream condensate line of the passive residual heat removal cooler 14.
In the event of a plant blackout and failure of the steam-driven pump trains of the active subsystem, the passive secondary-side residual heat removal system is put into service to remove the residual heat of cores and storage heat of various pieces of equipment in the reactor coolant system on the premise that the specified fuel design limits and the coolant pressure boundary design conditions are not exceeded, thus maintaining the reactor at safe shutdown condition within 72 hours.
The steam line is connected to the inlet nozzle of the passive residual heat removal cooler 14 which is disposed in the accident cooling water tank 13.
During the entire operation, the passive residual heat removal cooler 14 is required to be immersed into water rather than exposed outside. The condensate piping is led from the outlet of the passive residual heat removal cooler and the outlet of the condensate piping is connected to both the main feedwater piping and auxiliary feedwater piping of the steam generator. Two parallel-connected normally-closed air-operated isolation valves are disposed on the condensate piping such that the system can be isolated while it is in standby and the condensate piping can restore operation readily when the system is put into service. One check valve is disposed at downstream of the condensate piping to prevent feedwater to the steam generator from being bypassed through the condensate piping.
One motor-driven isolation valve is disposed on the steam line through which the passive residual heat removal cooler 14 is connected to the main steam piping II of the steam generator 9. During normal operation of the unit, the motor-driven isolation valve on the steam line remains normally open while the air-operated isolation valve on the condensate piping remains normally closed, and the tube side of the passive residual heat removal cooler is filled with wateL After the switching-in signal of the system is issued, the air-operated isolation valve on the condensate piping is opened and the system is put into service. Water inside the tubes of the passive residual heat removal cooler is filled into the secondary side of the steam generator under the effect of gravity where it is heated to steam by residual heat from the cores. The steam is delivered to the tubes of the passive residual heat removal cooler to exchange heat with the cooling water inside the accident cooling water tank. As a result, the steam transfers heat to the cooling water and is condensed into water and the resulting condensate is returned back to the secondary side of the steam generator under the effect of gravity, thus completing a natural circulation of the steam-condensate loop. The amount of water in the emergency cooling water tank is reduced due to evaporation as it is heated continuously; nevertheless, the water amount is sufficient to ensure 72 hours of continuous operation of the system.
Each train comprises one passive make-up water tank 1 2 which has its upper end connected to upstream steam line of the passive residual heat removal cooler 14 through one isolation valve and has its lower end connected to the downstream condensate piping of the passive residual heat removal cooler through two parallel-connected isolation valves and one check valve. Once the system is put into service, water in the passive make-up water tank is filled into the I0 secondary-side of the steam generator to compensate the steam loss and water volume contraction at secondary-side of the steam generator.
In the event of a station blackout in conjunction with the failure of the steam-driven pumps of the active subsystem, in spite of shutdown of the main pump, the temperature difference and elevation difference between the reactor and steam generator creates a certain natural circulation capability for the passive secondary-side residual heat removal system, which causes the reactor heat to be transferred to the steam generator. This results in the natural circulation of the reactor coolant circuit being established, removing residual heat of the cores and securing safety of the cores.
The present invention provides a combination of the active subsystem and the passive secondary-side residual heat removal system which contributes to overall increase of nuclear power plants. Furthermore, the use of a passive system allows more system arrangement modes. Correspondingly, it becomes possible to modify the design of the active subsystem, which not only reduces a lot of money spent on investment and maintenance of the system, but also reduces the occupied land of the system, creating more desirable condition for the system arrangement.
The above disclosure is related to the detailed technical contents and inventive features thereof People skilled in this field may proceed with a variety of modifications and replacements based on the disclosures and suggestions of the invention as described without departing from the characteristics thereof Nevertheless, although such modifications and replacements are not frilly disclosed in the above descriptions, they have substantially been covered in the following claims as appended.
Claims (7)
- Claims 1. A combined active and passive secondary-side reactor core heat removal apparatus, comprising an active subsystem and a secondary-side passive residual heat removal system, the active subsystem comprising two redundant water supply trains, each of which being connected to an auxiliary feedwater tank (6) at one end and to a main feedwater piping (10) of a steam generator at the other end; the secondary-side passive residual heat removal system comprising a plurality of passive residual heat removal trains, each of which corresponding to a steam generator for each reactor ioop and comprising one passive residual heat removal cooler (14), a upstream steam line of the passive residual heat removal cooler (14) being connected to a main steam piping (11) of a steam generator (9), a downstream condensate line of the passive residual heat removal cooler being connected to a main feedwater piping (10) of the steam generator (9), the passive residual heat removal cooler (14) being disposed within an emergency cooling water tank (13), a passive make-up water tank (12) being disposed between the upstream steam line and the downstream condensate line of the passive residual heat removal cooler (14).
- 2. The combined active and passive secondary-side reactor core heat removal apparatus as claimed in claim 1, wherein, of the two water supply trains of the active subsystem, one water supply train comprises two parallel-connected 50% capacity motor-driven pumps (7), the other water supply train comprises two parallel-connected 50% steam-driven pumps (8); the two motor-driven pumps (7) are powered by an emergency power supply system, the two steam-driven pumps (8) have steam supplied from a upstream main steam line of a main steam isolation valve of the steam generator; discharge pipes of the two motor-driven pumps and * the two steam-driven pumps are combined into one header which is respectively connected to a main feedwater piping of individual steam generators.
- 3. The combined active and passive secondary-side reactor core heat removal apparatus as claimed in claim 2, wherein a check valve is respectively disposed on a discharge pipe of each of the motor-driven pumps and each of the steam-driven pumps of the active subsystem.
- 4. The combined active and passive secondary-side reactor core heat removal apparatus as claimed in claim 1, wherein, of the two water supply trains of the active subsystem, each water supply train comprises two 50% motor-driven pumps connected in parallel, the four motor-driven pumps are powered by an emergency power supply system; discharge pipes of the four motor-driven pumps are combined into one header which is respectively connected to a main feedwater piping of individual steam generators.
- 5. The combined active and passive secondary-side reactor core heat removal apparatus as claimed in claim 4, wherein a check valve is respectively disposed on a discharge pipe of each of the motor-driven pumps.
- 6. The combined active and passive secondary-side reactor core heat removal apparatus as claimed in claim 1, wherein one isolation valve is disposed on a steam line through which the passive residual heat removal cooler (14) is connected to the main steam piping (11) of the steam generator, two parallel-connected isolation valves are disposed on a condensate line connected to the main feedwater piping (10) of the steam generator, one check valve is disposed at downstream of the two parallel-connected isolation valves.
- 7. The combined active and passive secondary-side reactor core heat removal apparatus as claimed in claim 1, wherein one isolation valve is disposed on a line through which the passive make-up water tank (12) is connected to the upstream steam line of the passive residual heat removal cooler (14), two parallel-connected isolation valves are disposed on a line through which the passive make-up water tank (12) is connected to the downstream condensate line of the passive residual heat removal cooler (14), one check valve is disposed at downstream of the two parallel-connected isolation valve.
Applications Claiming Priority (2)
| 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 |
| PCT/CN2013/084038 WO2014048289A1 (en) | 2012-09-27 | 2013-09-24 | Combined active and passive secondary-side reactor core heat removal apparatus |
Publications (4)
| Publication Number | Publication Date |
|---|---|
| GB201504150D0 GB201504150D0 (en) | 2015-04-29 |
| GB2521549A true GB2521549A (en) | 2015-06-24 |
| GB2521549A8 GB2521549A8 (en) | 2018-07-18 |
| GB2521549B GB2521549B (en) | 2018-08-08 |
Family
ID=47446360
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| GB1504150.2A Active GB2521549B (en) | 2012-09-27 | 2013-09-24 | Combined active and passive secondary-side reactor core heat removal apparatus |
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) |
Families Citing this family (14)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| MY187908A (en) * | 2012-09-27 | 2021-10-28 | China Nuclear Power Eng Co Ltd | Combined active and passive secondary-side reactor core heat removal apparatus |
| 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 |
| 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 |
| CN105957567B (en) * | 2016-05-06 | 2018-03-06 | 中国核动力研究设计院 | A kind of steam generator secondary side Heat Discharging System of Chinese |
| 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) |
| CN111128414B (en) * | 2019-12-31 | 2022-07-26 | 中国核动力研究设计院 | Active and passive combined safety system and method for nuclear power plant |
| 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 |
| CN111430050B (en) * | 2020-04-24 | 2024-06-18 | 上海核工程研究设计院股份有限公司 | Passive residual heat removal system for secondary side of reactor and use method |
| CN111785400B (en) * | 2020-06-24 | 2022-02-08 | 武汉润德工程技术有限公司 | Self-oscillation passive waste heat discharging device and method |
| 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 |
| CN115083631A (en) * | 2022-06-02 | 2022-09-20 | 中广核研究院有限公司 | Emergent waste heat discharge system of small-size pressurized water reactor of double loop |
| 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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- 2012-09-27 MY MYPI2015700866A patent/MY187908A/en unknown
- 2012-09-27 CN CN2012103704106A patent/CN102867548A/en active Pending
-
2013
- 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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2015
- 2015-04-23 ZA ZA2015/02770A patent/ZA201502770B/en unknown
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Also Published As
| Publication number | Publication date |
|---|---|
| WO2014048289A1 (en) | 2014-04-03 |
| GB201504150D0 (en) | 2015-04-29 |
| GB2521549A8 (en) | 2018-07-18 |
| CN102867548A (en) | 2013-01-09 |
| GB2521549B (en) | 2018-08-08 |
| ZA201502770B (en) | 2016-02-24 |
| MY187908A (en) | 2021-10-28 |
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