CN201946323U - Emergency water supply system for nuclear power station - Google Patents

Emergency water supply system for nuclear power station Download PDF

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Publication number
CN201946323U
CN201946323U CN2011200014241U CN201120001424U CN201946323U CN 201946323 U CN201946323 U CN 201946323U CN 2011200014241 U CN2011200014241 U CN 2011200014241U CN 201120001424 U CN201120001424 U CN 201120001424U CN 201946323 U CN201946323 U CN 201946323U
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China
Prior art keywords
heat exchanger
nuclear power
water tank
condensing heat
power station
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Expired - Lifetime
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CN2011200014241U
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Chinese (zh)
Inventor
曹建华
卢冬华
傅先刚
陈海燕
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China General Nuclear Power Corp
China Nuclear Power Technology Research Institute Co Ltd
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Priority to CN2011200014241U priority Critical patent/CN201946323U/en
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    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Abstract

The utility model relates to an emergency water supply system for a nuclear power station, which is connected between the main steam pipeline of the steam generator of the nuclear power station and the main water supply pipeline. The emergency water supply system comprises an open condensate water tank and a condensing heat exchanger, wherein the open condensate water tank is arranged outside the containment of the nuclear power station and the condensing heat exchanger is arranged in the condensate water tank. Under accident conditions, steam in the main steam pipe of the steam generator enters the condensing heat exchanger and is condensed, water in the condensate water tank is continuously heated by the condensing heat exchanger, evaporated water vapor enters the atmosphere, the volume of water in the condensate water tank is continuously decreased till the condensing heat exchanger is exposed out of water surface, air is used for cooling the condensing heat exchanger at the moment, an effective air cooling circulation is formed, the heat of a reactor core is lead out a final heat sink (the atmosphere) outside the containment through the steam generator, functions of replenishing water to the steam generator of the nuclear power station and exhausting waste heat under the accident conditions are realized, and the reliability, the safety and the economy of the nuclear power station are improved.

Description

A kind of emergency feedwater supply system that is used for nuclear power station
Technical field
The utility model relates to the security system of nuclear power station, more particularly, relates to a kind of emergency feedwater supply system that steam generator moisturizing under the nuclear power plant accident operating mode and waste heat are discharged that is used for.
Background technology
Improve constantly the construction of the nuclear power station important energy source guarantee that becomes national development gradually along with the security of the ripe nuclear power station of technology.
In the present nuclear power station, the structure of nuclear reactor is: form reactor cavity in containment, in the heap chamber pressure vessel is set.Pressure vessel is connected with cold leg and heat pipe section, and steam generator is connected between heat pipe section and the cold leg, injects cooling medium by cold leg, and pressure vessel (reactor core) is carried out conventional cooling, discharges by the heat pipe section then.
In order to realize steam generator moisturizing and the waste heat discharge function of presurized water reactor under accident conditions, Chinese Nuclear Power Design Academy has designed the secondary side passive residual heat and has discharged system: by an emergency feedwater case and the air cooling tower of being connected in parallel between main steam pipe and water-supply line, come to pay an overdue tax for steam generator stage by stage and the waste heat discharge.This system must increase the complicacy of system owing to be provided with independently emergency feedwater case and air cooling tower, has increased the construction of nuclear power station and operation expense; And when operation, need also reduce reliability of operation by complicated control.
The utility model content
The technical problems to be solved in the utility model is, provide a kind of simple in structure, can effectively be implemented in the emergency feedwater supply system that nuclear power station steam generator moisturizing under the accident conditions and waste heat are discharged.
The technical scheme that its technical matters that solves the utility model adopts is: a kind of emergency feedwater supply system that is used for nuclear power station is provided, be connected between the main steam pipe and main feed water pipe line of nuclear power station steam generator, this emergency feedwater supply system comprises and is arranged on the outer uncovered condensation water tank of nuclear power plant containment shell and is arranged on condensing heat exchanger in the described condensation water tank; The liquid level of the condensate water in the described condensing heat exchanger is higher than the secondary side of described steam generator;
The pipe side entrance of described condensing heat exchanger is connected with described main steam pipe by inlet pipeline, and on described inlet pipeline the import barrier valve is set;
The pipe side outlet of described condensing heat exchanger is connected with described main feed water pipe line by outlet conduit, and on described outlet conduit the outlet by-pass valve control is set.
In emergency feedwater supply system of the present utility model, described condensing heat exchanger tilts to be installed in the bottom of described condensation water tank.
In emergency feedwater supply system of the present utility model, described condensation water tank is provided with the air conducting dividing plate that the bottom communicates; The open side of described condensation water tank is stretched out at the top of described air conducting dividing plate.
In emergency feedwater supply system of the present utility model, described condensation water tank is arranged on the outer high position of described nuclear power plant containment shell.
In emergency feedwater supply system of the present utility model, the interface position of described inlet pipeline and described main steam pipe is positioned at the main steam isolation valve upstream of described main steam pipe;
The interface position of described outlet conduit and described main feed water pipe line is positioned at the main feed water isolating valve downstream of described main feed water pipe line.
In emergency feedwater supply system of the present utility model, described import barrier valve comprises the isolation valve of often opening;
Described control of export valve comprises the normally closed isolation valve of series connection and prevents that described main feed water pipe line from blowing back into the reverse checkvalve of described condensing heat exchanger.
Enforcement the utlity model has following beneficial effect: under accident conditions, steam in the main steam line of steam generator enters condensation in the condensing heat exchanger, water in the condensation water tank heat interchanger that is condensed constantly heats, the water vapor of evaporation enters atmosphere, water yield continuous decrease in the condensation water tank, surface until condensing heat exchanger, at this moment, utilize air that condensing heat exchanger is cooled off, and then form effective air cool cycles, thereby the reactor core heat is exported in the outer ultimate heat sink (atmosphere) of containment by steam generator, realize the function that nuclear power station steam generator moisturizing under accident conditions and waste heat are discharged, improved the reliability of nuclear power station, security and economy.
Description of drawings
The utility model is described in further detail below in conjunction with drawings and Examples, in the accompanying drawing:
Fig. 1 is the synoptic diagram of an embodiment of emergency feedwater supply system of the present utility model.
Embodiment
As shown in Figure 1, be an embodiment of emergency feedwater supply system of the present utility model, the accident emergency that can be applicable to nuclear power station is handled.The nuclear reactor structure of this nuclear power station is: form reactor cavity in containment, in the heap chamber pressure vessel 11 is set.Pressure vessel 11 is connected with cold leg 12 and heat pipe section 13, steam generator 14 is connected between heat pipe section 13 and the cold leg 12, inject cooling medium by cold leg 12, to pressure vessel 11(reactor core) carry out conventional cooling, discharge by heat pipe section 13 then; Certainly, on heat pipe section 13 and cold leg 12, also be respectively equipped with equipment such as voltage stabilizer 15 and main pump 16.This steam generator 14 is connected with main steam pipe 17 and main feed water pipe line 18, and emergency feedwater supply system is connected between this main steam pipe 17 and the main feed water pipe line 18, uses as emergent safety equipment.Understandable, can dispose a series of above-mentioned emergency feedwater supply system of corresponding number according to steam generator 14 numbers of nuclear power station design employing.
As shown in the figure, this emergency feedwater supply system comprises uncovered condensation water tank 21 and condensing heat exchanger 22.The pipe side entrance of this condensing heat exchanger 22 is connected with main steam pipe 17 by inlet pipeline 23, and on inlet pipeline 23 import barrier valve 231 is set; The pipe side outlet of condensing heat exchanger 22 is connected with main feed water pipe line 18 by outlet conduit 24, and on outlet conduit 24 the outlet by-pass valve control is set.Utilize this emergency feedwater supply system the reactor core heat to be exported in the outer ultimate heat sink (atmosphere) of containment, realized the function that nuclear power station steam generator 14 moisturizings under accident conditions and waste heat are discharged by steam generator 14.
In the present embodiment, this uncovered condensation water tank 21 is placed on outside the nuclear power plant containment shell, directly communicates with atmosphere.This condensation water tank 21 can be the water tank of cylindrical water tank, square water tank or other shape; Can be placed on the outer safe factory building top of containment or other outer high positions of containment, realize security system entity insulation request.
Further, in order to increase the cross-ventilation ability, in condensation water tank 21, be provided with the air conducting dividing plate 25 that the bottom communicates.The open side of condensation water tank 21 is stretched out at the top of this air conducting dividing plate 25, thereby behind the water evaporate to dryness of condensation water tank 21, plays the guide functions of air chimney, to strengthen the cross-ventilation ability, improves heat exchange efficiency.Certainly, the height of air conducting dividing plate 25, quantity can require to carry out Change In Design according to reality.
This condensing heat exchanger 22 is arranged in the condensation water tank 21, carries out heat interchange with water, air in the condensation water tank 21, thereby the heat of steam generator 14 is derived.In the present embodiment, this condensing heat exchanger 22 tilts to be installed in the bottom of condensation water tank 21, can more effectively utilize the water in the condensation water tank 21, and can be under the situation that does not increase condensation water tank 21 height, effectively increased the heat interchanging area of condensing heat exchanger 22, weakened or the phenomenon of issuable steam hammer and flowing instability when avoiding system start-up.
The pipe side entrance of this condensing heat exchanger 22 is connected with main steam pipe 17 by inlet pipeline 23, and on inlet pipeline 23 import barrier valve 231 is set; The pipe side outlet is connected with main feed water pipe line 18 by outlet conduit 24, and on outlet conduit 24 the outlet by-pass valve control is set.In the present embodiment, the interface position of inlet pipeline 23 and main steam pipe 17 is positioned at the main steam isolation valve upstream of main steam pipe 17; The interface position of outlet conduit 24 and main feed water pipe line 18 is positioned at the main feed water isolating valve downstream of main feed water pipe line 18.
In the present embodiment, the import barrier valve 231 on the inlet pipeline 23 comprises an isolation valve of often opening, to keep condensing heat exchanger 22 and manifold pressure and main steam line balance.The control of export valve of outlet conduit 24 comprises the normally closed isolation valve 241 and the reverse checkvalve 242 of series connection.This normally closed isolation valve 241 is in normally off as the starting switch of total system, disconnects the Natural Circulation path.Reverse checkvalve 242 plays and prevents that main feed water pipe line 18 from blowing back into the effect of condensing heat exchanger 22.
When the normal reactor operation of nuclear power station, import barrier valve 231 on the inlet pipeline 23 keeps often opening, to keep condensing heat exchanger 22 and manifold pressure and main steam pipe 17 balances, and the control of export valve on the outlet conduit 24 of condensing heat exchanger 22 is closed, and cuts off the Natural Circulation path.
When needs start action, the control of export valve of condensing heat exchanger 22 is opened, in the condensing heat exchanger 22 and the condensate water in the associated conduit owing to liquid level difference flows into steam generator 14 secondary sides, steam in the main steam line enters condensation in the condensing heat exchanger 22 simultaneously, condensate water continues to flow into steam generator 14 secondary sides, thereby drives this system's continuous service.
Water in the condensation water tank 21 heat interchanger 22 that is condensed constantly heat, and temperature continues rising, and until boiling, the water vapor of evaporation enters atmosphere.Along with system's continuous service, the water yield continuous decrease in the condensation water tank 21 surfaces until the inclination condensing heat exchanger 22 that is positioned at condensation water tank 21 bottoms.
After this, system's operation enters subordinate phase, i.e. air cooling stage.Heat interchanger 22 heating are risen because the air in the condensation water tank 21 center air baffles is condensed, and the air in the air baffle outside is flowed into by the fair water fin bottom, and then forms effective air cool cycles.
This emergency feedwater supply system has been realized the recycling of steam generator 14 secondary side water and steam under the accident conditions, contain the radiomaterial cooling medium in a loop when steam generator 14 secondary sides leak, as under accident conditions such as steam generator 14 heat-transfer pipes break, water or the steam that can effectively avoid containing radiomaterial are arranged to environment; Can also substitute the safe level auxiliary feedwater system of current lot of domestic and foreign pressurized-water reactor nuclear power plant complexity, reduce requirements such as emergent diesel engine capacity and startup are reduced the construction of nuclear power station and operation expense.
Further, this emergency feedwater supply system has been cancelled the safe level auxiliary feedwater system of traditional pressurized-water reactor nuclear power plant, only keeps non-safe level startup and stops water supply system.Without power drive, only rely on Natural Circulation, realize the condensation and steam generator 14 secondary sides that reflux of steam, realize the emergency feedwater function, do not exist driving mechanism to lose efficacy and influence the problem of systemic-function, improved system reliability greatly, improved npp safety;
By steam generator 14 the reactor core heat is exported in the outer ultimate heat sink (atmosphere) of containment, and can pass through controlling opening of valve, control reactor-loop system decrease temperature and pressure speed realizes the decrease temperature and pressure function controlled to reactor;
Design guarantees under the accident conditions that condensation water tank 21 water capacities are enough to bring the reactor-loop system into the waste heat guiding system and drop in the condition and range; And behind condensation water tank 21 evaporates to dryness, can continue to realize to derive residual heat of nuclear core, improve the reliability of long-term cooling after the accident by natural convection air by steam generator 14.

Claims (6)

1. emergency feedwater supply system that is used for nuclear power station, be connected between the main steam pipe and main feed water pipe line of nuclear power station steam generator, it is characterized in that this emergency feedwater supply system comprises and is arranged on the outer uncovered condensation water tank of nuclear power plant containment shell and is arranged on condensing heat exchanger in the described condensation water tank; The liquid level of the condensate water in the described condensing heat exchanger is higher than the secondary side of described steam generator;
The pipe side entrance of described condensing heat exchanger is connected with described main steam pipe by inlet pipeline, and on described inlet pipeline the import barrier valve is set;
The pipe side outlet of described condensing heat exchanger is connected with described main feed water pipe line by outlet conduit, and on described outlet conduit the outlet by-pass valve control is set.
2. emergency feedwater supply system according to claim 1 is characterized in that, described condensing heat exchanger tilts to be installed in the bottom of described condensation water tank.
3. emergency feedwater supply system according to claim 1 is characterized in that, described condensation water tank is provided with the air conducting dividing plate that the bottom communicates; The open side of described condensation water tank is stretched out at the top of described air conducting dividing plate.
4. emergency feedwater supply system according to claim 1 is characterized in that, described condensation water tank is arranged on the outer high position of described nuclear power plant containment shell.
5. emergency feedwater supply system according to claim 1 is characterized in that, the interface position of described inlet pipeline and described main steam pipe is positioned at the main steam isolation valve upstream of described main steam pipe;
The interface position of described outlet conduit and described main feed water pipe line is positioned at the main feed water isolating valve downstream of described main feed water pipe line.
6. according to each described emergency feedwater supply system of claim 1 to 5, it is characterized in that described import barrier valve comprises the isolation valve of often opening;
Described control of export valve comprises the normally closed isolation valve of series connection and prevents that described main feed water pipe line from blowing back into the reverse checkvalve of described condensing heat exchanger.
CN2011200014241U 2011-01-05 2011-01-05 Emergency water supply system for nuclear power station Expired - Lifetime CN201946323U (en)

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Cited By (21)

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CN102522127A (en) * 2011-12-23 2012-06-27 中国核电工程有限公司 Passive containment thermal conduction system
CN103000234A (en) * 2011-09-08 2013-03-27 韩电原子力燃料株式会社 Passive auxiliary condensation apparatus for atomic power plant
CN103187110A (en) * 2012-01-03 2013-07-03 陈光焕 Nuclear energy steam self-compression water adding rod
CN103247356A (en) * 2012-02-07 2013-08-14 韩国原子力研究院 Water-spray residual heat removal system for nuclear power plant
CN103295656A (en) * 2012-02-29 2013-09-11 上海核工程研究设计院 Diversified engineered safety system for nuclear reactor
CN103295657A (en) * 2012-02-29 2013-09-11 上海核工程研究设计院 Residual heat removal system of nuclear reactor
CN103295655A (en) * 2012-02-29 2013-09-11 上海核工程研究设计院 Water logging and air cooling combined passive containment cooling system and method
CN103325427A (en) * 2012-03-19 2013-09-25 中科华核电技术研究院有限公司 Passive containment cooling system and method
CN103413581A (en) * 2013-07-31 2013-11-27 中科华核电技术研究院有限公司 Passive containment cooling system
CN103456375A (en) * 2013-07-31 2013-12-18 中科华核电技术研究院有限公司 Secondary-side residual heat removal system with passive flow control device
WO2014029306A1 (en) * 2012-08-20 2014-02-27 中国核动力研究设计院 Secondary-side passive residual heat discharge system for nuclear power plant steam generator
CN103871509A (en) * 2012-12-14 2014-06-18 中国核动力研究设计院 Pressurized water reactor nuclear power plant reactor coolant system
CN104021823A (en) * 2014-05-23 2014-09-03 中国核动力研究设计院 Waste heat long-term passive lead-out system of floating-type nuclear power station
CN104167230A (en) * 2014-07-30 2014-11-26 中科华核电技术研究院有限公司 Passive concrete containment cooling system
CN104167231A (en) * 2014-07-30 2014-11-26 中科华核电技术研究院有限公司 Concrete containment passive cooling system
CN104205239A (en) * 2012-01-18 2014-12-10 原子能技术公司 System for discharging residual power of pressurized water nuclear reactor
CN104205238A (en) * 2012-01-18 2014-12-10 原子能技术公司 System for discharging the residual power of a pressurised water nuclear reactor
CN104882169A (en) * 2014-02-27 2015-09-02 韩国原子力研究院 Air-water Combined Cooling Passive Feedwater Device And System
CN104979024A (en) * 2015-05-20 2015-10-14 中国核动力研究设计院 Passive pressure-relief, water-injection and cooling system for floating nuclear power plant and operation method therefor
WO2016078285A1 (en) * 2014-11-19 2016-05-26 中科华核电技术研究院有限公司 Secondary side passive waste heat removal system
CN106124076A (en) * 2016-07-06 2016-11-16 中国核动力研究设计院 Steam generator heat-transfer pipe refluence monitoring device

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CN103000234A (en) * 2011-09-08 2013-03-27 韩电原子力燃料株式会社 Passive auxiliary condensation apparatus for atomic power plant
CN103000234B (en) * 2011-09-08 2015-09-02 韩电原子力燃料株式会社 The passive type auxiliary condensing plant of nuclear power station
CN102522127A (en) * 2011-12-23 2012-06-27 中国核电工程有限公司 Passive containment thermal conduction system
CN102522127B (en) * 2011-12-23 2014-07-30 中国核电工程有限公司 Passive containment thermal conduction system
CN103187110A (en) * 2012-01-03 2013-07-03 陈光焕 Nuclear energy steam self-compression water adding rod
CN103187110B (en) * 2012-01-03 2015-11-25 陈光焕 Nuclear steam dead weight water-adding rod
CN104205238A (en) * 2012-01-18 2014-12-10 原子能技术公司 System for discharging the residual power of a pressurised water nuclear reactor
CN104205239A (en) * 2012-01-18 2014-12-10 原子能技术公司 System for discharging residual power of pressurized water nuclear reactor
CN104205239B (en) * 2012-01-18 2017-05-10 原子能技术公司 System for discharging residual power of pressurized water nuclear reactor
CN103247356B (en) * 2012-02-07 2016-03-16 韩国原子力研究院 The water of nuclear power plant sprays residual heat removal system
CN103247356A (en) * 2012-02-07 2013-08-14 韩国原子力研究院 Water-spray residual heat removal system for nuclear power plant
CN103295656A (en) * 2012-02-29 2013-09-11 上海核工程研究设计院 Diversified engineered safety system for nuclear reactor
CN103295655A (en) * 2012-02-29 2013-09-11 上海核工程研究设计院 Water logging and air cooling combined passive containment cooling system and method
CN103295657A (en) * 2012-02-29 2013-09-11 上海核工程研究设计院 Residual heat removal system of nuclear reactor
CN103325427B (en) * 2012-03-19 2016-06-01 中科华核电技术研究院有限公司 A kind of Passive containment cooling system and method
CN103325427A (en) * 2012-03-19 2013-09-25 中科华核电技术研究院有限公司 Passive containment cooling system and method
GB2520455A (en) * 2012-08-20 2015-05-20 Nuclear Power Inst China Secondary-side passive residual heat discharge system for nuclear power plant steam generator
WO2014029306A1 (en) * 2012-08-20 2014-02-27 中国核动力研究设计院 Secondary-side passive residual heat discharge system for nuclear power plant steam generator
GB2520455B (en) * 2012-08-20 2018-01-10 Nuclear Power Inst China A secondary-side passive residual heat discharge system for a nuclear power plant steam generator
CN103871509A (en) * 2012-12-14 2014-06-18 中国核动力研究设计院 Pressurized water reactor nuclear power plant reactor coolant system
CN103413581B (en) * 2013-07-31 2016-03-23 中科华核电技术研究院有限公司 passive containment cooling system
CN103456375A (en) * 2013-07-31 2013-12-18 中科华核电技术研究院有限公司 Secondary-side residual heat removal system with passive flow control device
CN103413581A (en) * 2013-07-31 2013-11-27 中科华核电技术研究院有限公司 Passive containment cooling system
CN103456375B (en) * 2013-07-31 2016-05-25 中广核研究院有限公司 With the secondary side residual heat removal system of non-active volume control device
CN104882169B (en) * 2014-02-27 2018-07-17 韩国原子力研究院 Water-air combined passive is to water-cooling apparatus and system
CN104882169A (en) * 2014-02-27 2015-09-02 韩国原子力研究院 Air-water Combined Cooling Passive Feedwater Device And System
CN104021823A (en) * 2014-05-23 2014-09-03 中国核动力研究设计院 Waste heat long-term passive lead-out system of floating-type nuclear power station
CN104167231A (en) * 2014-07-30 2014-11-26 中科华核电技术研究院有限公司 Concrete containment passive cooling system
GB2531190A (en) * 2014-07-30 2016-04-13 China Nuclear Power Technology Res Inst Co Ltd Passive concrete containment cooling system
GB2531489A (en) * 2014-07-30 2016-04-20 China Nuclear Power Technology Res Inst Co Ltd Passive cooling system for concrete containment vessel
WO2016015474A1 (en) * 2014-07-30 2016-02-04 中科华核电技术研究院有限公司 Passive concrete containment cooling system
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WO2016015475A1 (en) * 2014-07-30 2016-02-04 中科华核电技术研究院有限公司 Passive cooling system for concrete containment vessel
CN104167230A (en) * 2014-07-30 2014-11-26 中科华核电技术研究院有限公司 Passive concrete containment cooling system
GB2531190B (en) * 2014-07-30 2021-06-16 China Nuclear Power Tech Research Institute Co Ltd Passive concrete containment cooling system
GB2535848A (en) * 2014-11-19 2016-08-31 China Nuclear Power Technology Res Inst Co Ltd Secondary side passive waste heat removal system
WO2016078285A1 (en) * 2014-11-19 2016-05-26 中科华核电技术研究院有限公司 Secondary side passive waste heat removal system
GB2535848B (en) * 2014-11-19 2020-05-06 China Nuclear Power Tech Research Institute Co Ltd Secondary side passive residual heat removal system
CN104979024A (en) * 2015-05-20 2015-10-14 中国核动力研究设计院 Passive pressure-relief, water-injection and cooling system for floating nuclear power plant and operation method therefor
CN106124076A (en) * 2016-07-06 2016-11-16 中国核动力研究设计院 Steam generator heat-transfer pipe refluence monitoring device
CN106124076B (en) * 2016-07-06 2017-03-08 中国核动力研究设计院 Steam generator heat-transfer pipe flows backwards monitoring device

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CP03 "change of name, title or address"

Address after: 518000 Guangdong province Futian District Shangbu Road West of the city of Shenzhen Shenzhen science and technology building 15 layer (1502-1504, 1506)

Patentee after: CHINA NUCLEAR POWER TECHNOLOGY RESEARCH INSTITUTE

Patentee after: China General Nuclear Power Corporation

Address before: 518000 Guangdong, Futian District, Yitian Road, building A, block, building on the whole floor of A1301-1320 13

Patentee before: Zhongkehua Nuclear Power Technology Institute Co., Ltd.

Patentee before: China Guangdong Nuclear Power Group Co., Ltd.

Address after: 518000 Guangdong province Futian District Shangbu Road West of the city of Shenzhen Shenzhen science and technology building 15 layer (1502-1504, 1506)

Patentee after: CHINA NUCLEAR POWER TECHNOLOGY RESEARCH INSTITUTE

Patentee after: China General Nuclear Power Corporation

Address before: 518000 Guangdong, Futian District, Yitian Road, building A, block, building on the whole floor of A1301-1320 13

Patentee before: Zhongkehua Nuclear Power Technology Institute Co., Ltd.

Patentee before: China Guangdong Nuclear Power Group Co., Ltd.

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Granted publication date: 20110824

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