CN103377733A - Complete passive waste heat discharge system for post-accident reactor cores of large PWR (pressurized water reactor) nuclear power plants - Google Patents
Complete passive waste heat discharge system for post-accident reactor cores of large PWR (pressurized water reactor) nuclear power plants Download PDFInfo
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- CN103377733A CN103377733A CN2012101273685A CN201210127368A CN103377733A CN 103377733 A CN103377733 A CN 103377733A CN 2012101273685 A CN2012101273685 A CN 2012101273685A CN 201210127368 A CN201210127368 A CN 201210127368A CN 103377733 A CN103377733 A CN 103377733A
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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
Abstract
The invention provides a complete passive waste heat discharge system for post-accident reactor cores of large PWR (pressurized water reactor) nuclear power plants. A top air flow channel of a shielding workshop is provided with a chimney, containment cooling water tanks are arranged around the chimney, and containment cooling water pipes are arranged in each containment cooling water tank; a cooling water distribution plate is arranged in the shielding workshop and above the top of a containment. A meshed groove is formed in the inner wall of the vertical section of the containment; multiple rows of fins are fixed on the inner wall and/or the outer wall of the vertical section and/or the dome of the containment; multiple rows of heat exchange fans are fixed on the inner wall of the vertical section and/or the dome of the containment. The upper part of the side wall of the shielding workshop is provided with a through air inlet. An air guide plate is arranged on the inner side of the shielding workshop and the outer side of the containment. According to the system, the heat transfer capacity of the steel containment is enhanced, and the air cooling capacity of the steel containment is enhanced; through changing an air flow channel between the steel containment and the shielding workshop into a streamlined design, the air resistance is reduced.
Description
Technical field
The present invention relates to presurized water reactor For Power Station With The Pressurized Water Reactor engineered safety system field, relate to particularly the complete Heat Discharging System of Chinese of reactor core after a kind of For Power Station With The Pressurized Water Reactor accident.
Background technology
On March 11st, 2011, the global nuclear accident of shock has occured in Fukushima, Japan, the one of the main reasons that causes nuclear accident is exactly under the beyond design basis accident of this earthquake and tsunami, the MarkI unit that the GE company that Fukushima has produces can't be realized effective residual heat of nuclear core discharge, cause at last core meltdown, produce a large amount of hydrogen, indirectly make the containment superpressure, simultaneously since by force the injection seawater cool off, cause a large amount of radiomaterials to leak.After the Fukushima event, Nuclear Safety mechanism and industry member have had stronger demand to the long-term non-active cooling power of nuclear power plant.Japan atomic energy association from 12 summarizes Lessons, thought deeply countermeasure and proposed suggestion.These lessons and suggestion have very important meaning to the security that improves For Power Station With The Pressurized Water Reactor (comprising non-active For Power Station With The Pressurized Water Reactor) in the world wide.In therein the 4th the whole cooling mediums lesson of forfeiture, clear and definite proposition consider non-active natural circulation cooling mode, all can discharge residual heat of nuclear core in any occasion.The lesson of these preciousnesses and suggestion have important directive significance for promoting existing nuclear power technology.According to lesson and the suggestion of Fukushima, one inherently safe in design, and having passive residual heat derives for a long time the For Power Station With The Pressurized Water Reactor of ability and more can cover Fukushima class beyond design basis accident.
When reactor is counter make trouble thus after, as long as can guarantee 3 just can realization response the safety of heap, first: reactive control; Second: contain radioactivity; The the 3rd: the discharge of waste heat.For large pressurized water reactor, can realize for front 2, but thirdly also can realize without any a kind of For Power Station With The Pressurized Water Reactor in the world at present.
Summary of the invention
The object of the present invention is to provide the complete Heat Discharging System of Chinese of reactor core after a kind of For Power Station With The Pressurized Water Reactor accident of the long-term fully passive residual heat removal that can realize residual heat of nuclear core.
Realize the technical scheme of the object of the invention: the complete Heat Discharging System of Chinese of reactor core after a kind of For Power Station With The Pressurized Water Reactor accident, wherein steel containment vessel is arranged in the shielding factory building, top air flow channel at the shielding factory building arranges chimney, and chimney extends upward shielding factory building top; Top at the shielding factory building is outer, chimney the containment cooling water tank is set on every side, some containment cooling water pipes are arranged in the containment cooling water tank; In the shielding factory building, the over top of containment and chimney below the chilled water distribution plate is set; The water inlet of above-mentioned some containment cooling water pipes is connected with containment cooling water tank bottom, and its water delivering orifice extends downward the chilled water distribution plate in the shielding factory building; It is characterized in that:
Vertical section inwall at containment is furnished with netted groove;
And/or---be fixed with some row's fins at vertical section of containment and/or inwall and/or the outer wall of dome;
And/or---be fixed with some row's heat exchange fans at vertical section of containment and/or the inwall of dome.
The complete Heat Discharging System of Chinese of reactor core after aforesaid a kind of For Power Station With The Pressurized Water Reactor accident, its described some row's heat exchange fans can be fixed on some row's fins of containment inwall setting.
The complete Heat Discharging System of Chinese of reactor core after aforesaid a kind of For Power Station With The Pressurized Water Reactor accident, its described netted groove is connected to form by the vertical precipitation groove in some roads and the some roads groove that tilts to catchment; Vertically the width of precipitation groove is at 10～100mm, and the width of the groove that tilts to catchment is at 10～100mm, and the angle of inclination is at 20 °～80 °; Vertically the degree of depth of precipitation groove is 1mm～10mm, and the degree of depth of the groove that tilts to catchment is 1mm～10m; Described fin material is identical with steel containment vessel, is welded on the interior and/or outer wall of containment; Fin is along the radical length 10cm～200cm of containment, and the thickness of fin is 0.1～1cm
The complete Heat Discharging System of Chinese of reactor core after aforesaid a kind of For Power Station With The Pressurized Water Reactor accident, the thickness of its described steel containment vessel is 4～40cm; Spacing 10cm between the vertical precipitation groove of described phase neighboring trace～1000cm, phase neighboring trace tilt to catchment spacing between the groove at 10cm～1000cm; Spacing between described adjacent row's fin is at 10cm～200cm; Spacing between described adjacent row's heat exchange fan is at 10cm～200cm.
The complete Heat Discharging System of Chinese of reactor core after aforesaid a kind of For Power Station With The Pressurized Water Reactor accident is characterized in that: described vertical precipitation groove has 100～3000 roads, and the groove that tilts to catchment has 100～70000 roads; Described fin has 100～3000 rows, and described heat exchange fan has 100～3000 rows, and the quantity of heat exchange fan has 100～3000.
The complete Heat Discharging System of Chinese of reactor core after aforesaid a kind of For Power Station With The Pressurized Water Reactor accident, its described heat exchange fan is the low-power DC electric fan; It starts under accident conditions, and each power is 100W～300W; The distance of heat exchange fan and containment wall is 10cm～200cm.
The complete Heat Discharging System of Chinese of reactor core after aforesaid a kind of For Power Station With The Pressurized Water Reactor accident, its side wall upper part at the shielding factory building is offered the air intake of perforation.
The complete Heat Discharging System of Chinese of reactor core after aforesaid a kind of For Power Station With The Pressurized Water Reactor accident, its described air intake is offered 2～5 rows along the circumferencial direction of shielding factory building, and axis is inclined upwardly 50 °～80 ° from the sidewall of shielding factory building; The diameter of every air-discharging entrance is 7～20cm, and the center distance of adjacent air-discharging entrance is 12～24cm.
The complete Heat Discharging System of Chinese of reactor core after aforesaid a kind of For Power Station With The Pressurized Water Reactor accident, its described chimney exceed shielding factory building 0～150m.
The complete Heat Discharging System of Chinese of reactor core after aforesaid a kind of For Power Station With The Pressurized Water Reactor accident, its, containment arranged outside air baffle inboard at the shielding factory building.
The complete Heat Discharging System of Chinese of reactor core after aforesaid a kind of For Power Station With The Pressurized Water Reactor accident, the outer wall spacing of its described air baffle and containment: air baffle and inwall spacing=(0.15～1) that shields factory building: 1; The top of this air baffle is connected with the top of shielding factory building, and the bottom is with outward-dipping 20 °～60 ° outer; The bottom of air baffle extends to the bottom of equipment gate and access lock, and offers passage in the position corresponding with equipment gate and access lock.
Effect of the present invention is: the complete Heat Discharging System of Chinese of reactor core after a kind of For Power Station With The Pressurized Water Reactor accident that the present invention proposes, adopted Novel steel containment structure form, strengthen the heat-transfer capability of steel containment vessel, increased steel containment vessel air cooling power.Change the air flow channel between steel containment vessel and the shielding factory building into airflow design simultaneously, reduced air resistance.The present invention is changing the complete non-active cooling that has realized reactor core in the minimum situation, the security that has greatly improved For Power Station With The Pressurized Water Reactor to existing For Power Station With The Pressurized Water Reactor.
Description of drawings
Fig. 1 is the structural representation of the complete Heat Discharging System of Chinese of reactor core after a kind of For Power Station With The Pressurized Water Reactor accident of the present invention;
Fig. 2 is containment inwall netted groove synoptic diagram;
Fig. 3 is containment inner wall trench side view;
Fig. 4 is that containment inwall fin is arranged front elevation;
Fig. 5 is that containment inner and outer wall fin is arranged side view.
Fig. 6 is that containment inwall heat exchange fan is arranged front elevation;
Fig. 7 is that containment inwall heat exchange fan is arranged side view.
Among the figure: the 1-pressure vessel; 2-one circuit pressure border; The 3-containment; 4-shields factory building; 5-containment cooling water tank; 6-containment cooling water pipe; The 7-chimney; 8-chilled water distribution plate; The 9-air baffle; 10-equipment gate and access lock; 11-one loop steam release valve; The 12-reactor core; The 13-air intake; The 14-groove that tilts to catchment; The vertical precipitation groove of 15-; 16-heat exchange fan; The 17-fin; The 18-DC power source bus of meeting an urgent need.
Embodiment
Below in conjunction with accompanying drawing to a kind of For Power Station With The Pressurized Water Reactor accident of the present invention after reactor core fully non-active cooling system be described in further detail.
Embodiment 1
As shown in Figure 1, the complete non-active cooling system of reactor core after a kind of For Power Station With The Pressurized Water Reactor accident of the present invention, wherein steel containment vessel 3 is arranged in the shielding factory building 4 of steel concrete unitized construction.These steel containment vessel 3 thickness can bear the pressure of 0.2～2MPa at 4～40cm.
Top air flow channel at shielding factory building 4 connects chimney 7, and this chimney 7 extends upward shielding factory building 4 tops.Top at shielding factory building 4 is outer, chimney 75,2 of containment cooling water tanks are set on every side or 3 containment cooling water pipes 6 are arranged in the containment cooling water tank 5.In shielding factory building 4, the over top of containment 3 and chimney 7 below chilled water distribution plate 8 is set.The water inlet of above-mentioned every containment cooling water pipe 6 is connected with containment cooling water tank 5 bottoms, and its water delivering orifice extends downward the chilled water distribution plate 8 in the shielding factory building 4.Chimney 7 exceeds shielding factory building 0～150m, utilizes and pulls out the air cooling power that wind scorpion strengthens containment.It is identical with the diameter that shields factory building 4 that the diameter of containment cooling water tank 5 can increase to.
Side wall upper part at shielding factory building 4 is offered the air intake 13 of perforation.This air intake 13 is offered 2～5 rows (for example: 2 rows, 3 rows or 5 rows) along the circumferencial direction of shielding factory building 4.Air intake 13 axis are from the sidewall be inclined upwardly 50 °～80 ° (for example: 50 °, 65 ° or 80 °) of shielding factory building 4.The diameter of every air-discharging entrance 13 is 7～20cm (for example: 7cm, 10cm or 20cm), and the center distance of adjacent air-discharging entrance 13 is 12～24cm (for example: 12cm, 18cm or 24cm).
At shielding factory building 4 inboards, containment 3 arranged outside air baffles 9.The outer wall spacing of air baffle 9 and containment 3: air baffle 9 and inwall spacing=(0.15～1) that shields factory building 4: 1, for example 0.15: 1 or 0.5: 1 or 1: 1.The top of this air baffle 9 is connected with shielding factory building 4 tops, and the bottom is with outward-dipping 20 °～60 ° outer (for example: tilt 20 °, 45 ° or 60 °).The bottom of air baffle 9 extends to the bottom of equipment gate and access lock 10, and offers passage in the position corresponding with equipment gate and access lock 10.
As shown in Figures 2 and 3, on vertical section inwall of steel containment vessel 3, evenly suppress netted groove.Netted groove can be covered with vertical section inwall of containment 3, but also the interval is arranged in vertical section inwall of containment 3.
Above-mentioned netted groove is connected to form by the vertical precipitation groove 15 in 100～3000 roads and 100～70000 roads groove 14 that tilts to catchment.The vertically inner wall area of the concrete quantity basis containment 3 of precipitation groove 15 and the groove 14 that tilts to catchment and inner concrete structure and decide.
The width of above-mentioned vertical precipitation groove 15 is 10～100mm (for example: 10mm, 50mm or 100mm), tilt to catchment the width of groove 14 10～100mm (for example: 10mm, 50mm or 100mm), the angle of inclination is 20 °～80 ° (for example: 20 °, 50 ° or 80 °); Vertically the degree of depth of precipitation groove 15 is 1mm～10mm (for example: 1mm, 5mm or 10mm), and the degree of depth of the groove 14 that tilts to catchment is 1mm～10m (for example: 1mm, 5mm or 10mm).
Spacing 10cm between the vertical precipitation groove 15 of above-mentioned phase neighboring trace～1000cm (for example: 10mm, 100mm or 1000mm), phase neighboring trace tilt to catchment spacing between the groove 14 10cm～1000cm (for example: 10mm, 100mm or 1000mm).
Embodiment 2
In embodiment 2, as shown in Figure 4 and Figure 5, vertical section of steel containment vessel 3 and the inner and outer wall of dome are welded with respectively 100～3000 row's fins 17, and all the other are identical with embodiment 1.Fin 17 can be inside and outside containment all scopes of both sides arrange the inside and outside wall area of concrete quantity basis containment 3 and inside and outside concrete structure and decide.
Fin 17 adopts equal material with containment 3.Fin 17 is along the radical length 10cm～200cm (for example: 10mm, 100mm or 200mm) of containment, and the thickness of fin 17 is 0.1～1cm (for example: 0.1mm, 0.5mm or 1mm).Spacing between adjacent row's fin 17 is 10cm～200cm (for example: 10mm, 100mm or 200mm).
In embodiment 3, also be welded with 100～3000 row's heat exchange fans 16 on the inwall of vertical section of steel containment vessel 3 and dome, as shown in Figure 6 and Figure 7, all the other are identical with embodiment 1.Heat exchange fan 16 quantity have 100～3000, are specifically determined by the containment situation, play the effect of convection heat transfer in the shell that tightens security, and the layout scope can be in all positions of containment internal face.
Heat exchange fan 16 is the low-power DC electric fan of enhanced heat exchange, and each power is 100W～300W.Heat exchange fan 16 starts under accident conditions, controlled by safety control system, is its power supply by emergent DC power source bus 18.Heat exchange fan 16 is 10cm～200cm (for example: 10mm, 100mm or 200mm) with the distance of containment 3 walls.Spacing between adjacent row's heat exchange fan 16 is 10cm～200cm (for example: 10mm, 100mm or 200mm).
In embodiment 4, also be welded with some row's fins 17 on the inwall of vertical section of steel containment vessel 3 and dome, some row's heat exchange fans 16 are weldingly fixed on some row's fins 17, and as shown in Figure 4 to 7, all the other are identical with embodiment 1.
After reactor has an accident, as producing cut, break or break in a circuit pressure border 2 such as pressure vessel 1, the press water flash-off of steam in a loop is ejected in the containment 3; If system does not have cut, then system opens a loop steam release valve 11 automatically, system initiatively with the discharge of steam in a loop in the space of containment, the safety control system that is subject to nuclear power station triggers, emergent DC power source bus 18 is 16 power supplies of low-power DC fan, steam is subject to the disturbance of low-power DC fan 16, thereby strengthened convection heat transfer, be positioned at the fin 17 of the inside and outside wall of containment, increased the area of containment, make that steam is easier to be condensed, compile along the inclination groove 14 that catchments behind the steam condensation, flow back to simultaneously the bottom of containment 3 along the fin 17 of vertical precipitation groove 15 and vertical layout, be heated again evaporation and form Natural Circulation, constantly evaporative cooling, the heat transferred of reactor core 12 is extraneous, after receiving the high signal of containment internal pressure, containment cooling water pipe 6 begins to open, to 8 water fillings of chilled water distribution plate, chilled water distribution plate 8 divides flow on containment 3 chilled water equably, chilled water is taken away heat in containment 3 evaporations, and As time goes on, the chilled water of stream on containment is fewer and feweri, moisture film coverage rate on the containment is more and more less, at this moment the cooling effect of air becomes significantly gradually, and air enters in the shielding factory building 4 by air intake 13, and is downward along air baffle 9, after arriving the bottom, turnover makes progress along containment, in the air duct between containment 3 and air baffle 9, by the containment surface heating, flow velocity rises gradually, discharge from chimney 7 at last, the heat in the containment 3 is taken away, thereby reach the purpose of cooling off reactor core 12.Netted groove, fin and the heat exchange fan that arranges at containment strengthened the heat-transfer capability of containment, increased containment air cooling power.The mode of fin, netted groove, three kinds of augmentation of heat transfers of heat exchange fan can be used mutually simultaneously among the present invention, also can use separately.
Claims (10)
1. the complete Heat Discharging System of Chinese of reactor core after the For Power Station With The Pressurized Water Reactor accident, wherein steel containment vessel (3) is arranged in the shielding factory building (4), top air flow channel at shielding factory building (4) arranges chimney (7), and chimney (7) extends upward shielding factory building (4) top; Top at shielding factory building (4) is outer, chimney (7) containment cooling water tank (5) is set on every side, some containment cooling water pipes (6) are arranged in the containment cooling water tank (5); In shielding factory building (4), the over top of containment (3) and the below of chimney (7) arrange chilled water distribution plate (8); The water inlet of above-mentioned some containment cooling water pipes (6) is connected with containment cooling water tank (5) bottom, and its water delivering orifice extends downward the chilled water distribution plate (8) in the shielding factory building (4); It is characterized in that:
Vertical section inwall at containment (3) is furnished with netted groove;
And/or---be fixed with some row's fins (17) at vertical section of containment (3) and/or inwall and/or the outer wall of dome;
And/or---be fixed with some row's heat exchange fans (16) at vertical section of containment (3) and/or the inwall of dome.
2. the complete Heat Discharging System of Chinese of reactor core after a kind of For Power Station With The Pressurized Water Reactor accident according to claim 1 is characterized in that: described some row's heat exchange fans (16) can be fixed on some row's fins (17) that containment (3) inwall arranges.
3. the complete Heat Discharging System of Chinese of reactor core after a kind of For Power Station With The Pressurized Water Reactor accident according to claim 1 and 2 is characterized in that:
Described netted groove is connected to form by the vertical precipitation grooves in some roads (15) and the some roads groove (14) that tilts to catchment; Wherein, vertically the width of precipitation groove (15) is at 10～100mm, and the width of the groove (14) that tilts to catchment is at 10～100mm, and the angle of inclination is at 20 °～80 °; Vertically the degree of depth of precipitation groove (15) is 1mm～10mm, and the degree of depth of the groove (14) that tilts to catchment is 1mm～10m;
Described fin (17) material is identical with steel containment vessel (3), is welded on the interior and/or outer wall of containment (3); Wherein, fin (17) is along the radical length 10cm～200cm of containment, and the thickness of fin (17) is 0.1～1cm.
4. the complete Heat Discharging System of Chinese of reactor core after a kind of For Power Station With The Pressurized Water Reactor accident according to claim 3 is characterized in that:
The thickness of described steel containment vessel is 4～40cm;
Spacing 10cm between the vertical precipitation groove of described phase neighboring trace (15)～1000cm, phase neighboring trace tilt to catchment spacing between the groove (14) at 10cm～1000cm;
Spacing between described adjacent row's fin (17) is at 10cm～200cm;
Spacing between described adjacent row's heat exchange fan (16) is at 10cm～200cm.
5. the complete Heat Discharging System of Chinese of reactor core after a kind of For Power Station With The Pressurized Water Reactor accident according to claim 4 is characterized in that:
Described vertical precipitation groove (15) has 100～3000 roads, and the groove (14) that tilts to catchment has 100～70000 roads;
Described fin (17) has 100～3000 rows,
Described heat exchange fan (16) has 100～3000 rows, and the quantity of heat exchange fan (16) has 100～3000.
6. the complete Heat Discharging System of Chinese of reactor core after a kind of For Power Station With The Pressurized Water Reactor accident according to claim 3 is characterized in that: described heat exchange fan (16) is the low-power DC electric fan; It starts under accident conditions, and each power is 100W～300W; Heat exchange fan (16) is 10cm～200cm with the distance of containment (3) wall.
7. the complete Heat Discharging System of Chinese of reactor core after a kind of For Power Station With The Pressurized Water Reactor accident according to claim 1 and 2 is characterized in that: offer the air intake (13) of perforation in the side wall upper part that shields factory building (4).
8. the complete Heat Discharging System of Chinese of reactor core after a kind of For Power Station With The Pressurized Water Reactor accident according to claim 7, it is characterized in that: described air intake (13) is offered 2～5 rows along the circumferencial direction of shielding factory building (4), and axis is inclined upwardly 50 °～80 ° from the sidewall of shielding factory building (4); The diameter of every air-discharging entrance (13) is 7～20cm, and the center distance of adjacent air-discharging entrance is 12～24cm.
9. the complete Heat Discharging System of Chinese of reactor core after a kind of For Power Station With The Pressurized Water Reactor accident according to claim 1 and 2 is characterized in that:, containment (3) arranged outside air baffle (9) inboard at shielding factory building (4); Described chimney (7) exceeds shielding factory building (4) 0～150m.
10. the complete Heat Discharging System of Chinese of reactor core after a kind of For Power Station With The Pressurized Water Reactor accident according to claim 9 is characterized in that: the outer wall spacing of described air baffle (9) and containment (3): air baffle (9) and inwall spacing=(0.15～1) that shields factory building (4): 1; The top of this air baffle (9) is connected with the top of shielding factory building (4), and the bottom is with outward-dipping 20 °～60 ° outer; The bottom of air baffle (9) extends to the bottom of equipment gate and access lock (10), and offers passage in the position corresponding with equipment gate and access lock (10).
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| CN103730170A (en) * | 2013-12-31 | 2014-04-16 | 国家核电技术有限公司 | Accident mitigation device capable of reinforcing heat-removal performance of containment vessel |
| CN104934078A (en) * | 2015-05-11 | 2015-09-23 | 中国核电工程有限公司 | Passive containment cooling system keeping dynamic circulation of cooling water |
| CN105489258A (en) * | 2016-01-04 | 2016-04-13 | 上海核工程研究设计院 | Non-kinetic energy containment vessel cooling system of floating nuclear power plant |
| CN107039093A (en) * | 2017-03-31 | 2017-08-11 | 哈尔滨工程大学 | Three generations's Power Station With The Pressurized Water Reactor containment isolation design structure |
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| CN103730170A (en) * | 2013-12-31 | 2014-04-16 | 国家核电技术有限公司 | Accident mitigation device capable of reinforcing heat-removal performance of containment vessel |
| CN103730170B (en) * | 2013-12-31 | 2016-08-17 | 国家核电技术有限公司 | A kind of accident mitigation device of intensified safety shell heat extraction |
| CN104934078A (en) * | 2015-05-11 | 2015-09-23 | 中国核电工程有限公司 | Passive containment cooling system keeping dynamic circulation of cooling water |
| CN105489258A (en) * | 2016-01-04 | 2016-04-13 | 上海核工程研究设计院 | Non-kinetic energy containment vessel cooling system of floating nuclear power plant |
| CN107039093A (en) * | 2017-03-31 | 2017-08-11 | 哈尔滨工程大学 | Three generations's Power Station With The Pressurized Water Reactor containment isolation design structure |
| CN111599498A (en) * | 2020-04-14 | 2020-08-28 | 中国核电工程有限公司 | Passive containment air-water long-term cooling system |
| CN111599498B (en) * | 2020-04-14 | 2022-11-18 | 中国核电工程有限公司 | Passive containment air-water long-term cooling system |
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| CN103377733B (en) | 2016-01-27 |
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