CN103871509A - Pressurized water reactor nuclear power plant reactor coolant system - Google Patents
Pressurized water reactor nuclear power plant reactor coolant system Download PDFInfo
- Publication number
- CN103871509A CN103871509A CN201210544043.7A CN201210544043A CN103871509A CN 103871509 A CN103871509 A CN 103871509A CN 201210544043 A CN201210544043 A CN 201210544043A CN 103871509 A CN103871509 A CN 103871509A
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- nuclear power
- accident
- waste heat
- isolation valve
- power plant
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D1/00—Details of nuclear power plant
- G21D1/02—Arrangements of auxiliary equipment
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/04—Safety arrangements
- G21D3/06—Safety arrangements responsive to faults within the plant
-
- 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
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- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Business, Economics & Management (AREA)
- Emergency Management (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention relates to an accident coping system of a pressurized water reactor nuclear power plant reactor coolant system. The pressurized water reactor nuclear power plant reactor coolant system includes an accident cooling water tank, an emergency waste heat discharge cooler is arranged in the accident cooling water tank, one end of the emergency waste heat discharge cooler is connected with a condensation water pipeline isolation valve, a condensation water pipeline interface is connected between the condensation water pipeline isolation valve and a supplement water pipeline isolation valve, the other end of the emergency waste heat discharge cooler is connected with a steam pipeline interface, and two ends of the emergency waste heat discharge cooler are connected with parallel emergency supplement water tanks respectively. The pressurized water reactor nuclear power plant reactor coolant system having a severe accident coping measure can pass theoretic analysis and experiment verification, and will be applied to design Chinese three-generation nuclear power plants.
Description
Technical field
The invention belongs to a kind of accident answering system of PWR nuclear power plant reactor coolant loop, be specifically related to a kind of PWR nuclear power plant reactor coolant loop that possesses major accident counter-measure.
Background technology
Nuclear power station was under major accident operating mode in the past, lack prevention and the mitigation strategy of major accident, this reactor coolant loop possesses perfect major accident prevention and mitigation strategy, specifically comprises: the high-order exhaust of reactor pressure vessel, a loop fast pressure relief, steam generator secondary side passive residual heat removal.
Under accident conditions, the high-order exhaust of reactor pressure vessel puts into operation, discharge the non-condensable gas that reactor pressure vessel top is gathered, thereby prevent the impact that these not concretive gas conduct heat on reactor core, guarantee to only have unique carbonated drink interface in reactor coolant loop, alleviate damage sequence.
One loop fast pressure relief is carried out rapid pressure relief function under major accident, reduces high-voltage fuse under major accident and piles the risk of bringing, and avoids occurring threatening the high-pressure smelting thing jet phenomenon of containment integrity.
Station blackout is occurring, and power plant loses under the accident conditions of active residual heat of nuclear core discharge ability simultaneously, and the operation of steam generator secondary side passive residual heat removal system, can derive residual heat of nuclear core for a long time, maintains reactor at safe condition.
Summary of the invention
The object of this invention is to provide a kind of PWR nuclear power plant reactor coolant loop that possesses major accident counter-measure and be applicable to domestic application PWR nuclear power plant (station) reactor coolant loop the most widely, can prevent and the consequence of alleviating major accident.
The present invention realizes like this, a kind of PWR nuclear power plant reactor coolant loop, it comprises accident cooling water tank, in accident cooling water tank, be provided with emergent waste heat and discharge refrigeratory, one end that emergent waste heat is discharged refrigeratory is connected with condensate piping isolation valve, condensate piping isolation valve is connected with moisturizing pipeline isolation valve, between condensate piping isolation valve and moisturizing pipeline isolation valve, be connected with condensate pipe line interface, the other end that emergent waste heat is discharged refrigeratory is connected with vapour line interface, the two ends that emergent waste heat is discharged refrigeratory are also connected with emergence compensating water case in parallel respectively.
Advantage of the present invention is, a kind of PWR nuclear power plant reactor coolant loop that possesses major accident counter-measure will be by theoretical analysis and experimental verification, and will be applied to the design of domestic three generations's nuclear power station.Analysis shows, in the time there is major accident, by the accident vent valve at reactor pressure vessel top, can discharge the hydrogen of reactor coolant loop total measurement (volume) half; The capacity of every a series of fast pressure relief valves is summations of three groups of safety valve capacity, can prevent high-voltage fuse heap accident; Station blackout is occurring, and power plant loses under the accident conditions of active residual heat of nuclear core discharge ability simultaneously, by steam generator secondary side Heat Discharging System of Chinese, derives for a long time residual heat of nuclear core, maintains reactor at safe condition.
Accompanying drawing explanation
Fig. 1 a kind of PWR nuclear power plant reactor coolant loop schematic diagram provided by the present invention.
In figure, 1 reactor pressure vessel; 2 voltage stabilizers; 3 steam generators; 4 main pumps; 5 main pipe hot legs; 6 main pipeline transition sections; Cold section of 7 main pipelines; 8 fluctuation pipes; 9 fast pressure relief valves; 10 accident vent valves; 11 normal exhaust valves; 12 accident cooling water tanks; 13 emergent waste heats are discharged refrigeratory; 14 emergence compensating water casees; 15 condensate piping isolation valves; 16 moisturizing pipeline isolation valves; 17 vapour line interfaces; 18 condensate pipe line interfaces; 19 release case interfaces; 20 containments.
Embodiment
Below in conjunction with drawings and Examples, the present invention is described in detail:
A kind of PWR nuclear power plant reactor coolant loop, under major accident operating mode, by reactor pressure vessel accident vent valve, is discharged the non-condensable gas of reactor roof, prevents that it from affecting the heat transfer of reactor core; By fast pressure relief valve, carry out rapid pressure relief function, prevent high-voltage fuse heap; By steam generator secondary side passive system, provide means for derive a loop heat under major accident operating mode.
A kind of PWR nuclear power plant reactor coolant loop is provided with the high-order vent valve of reactor pressure vessel at reactor pressure vessel top, be provided with fast pressure relief valve at voltage stabilizer top, in the steam generator secondary side of each loop, be provided with steam generator secondary side Heat Discharging System of Chinese, each series comprises (or many) water supply tank, a refrigeratory, refrigeratory is arranged in the bottom of accident cooling water tank.
A kind of PWR nuclear power plant reactor coolant loop, it comprises reactor pressure vessel 1, reactor pressure vessel 1 is connected with cold section 7 of main pipeline, main pipe hot leg 5 and normal exhaust valve 11 respectively; Normal exhaust valve 11 is connected with accident vent valve 10, and accident vent valve 10 is connected with release case interface 19; One end of fluctuation pipe 8 is connected with main pipe hot leg 5, the other end is connected with voltage stabilizer 2, voltage stabilizer 2 is connected with fast pressure relief valve 9, main pipe hot leg 5 is connected with steam generator 3, steam generator 3 is connected with main pipeline transition section 6, and main pipeline transition section 6 is connected with main pump 4, and main pump 4 is connected for cold section 7 with main pipeline, the top of steam generator 3 is also connected with vapour line interface 17 and condensate pipe line interface 18 respectively, and vapour line interface 17 and condensate pipe line interface 18 are all through containment 20.
Accident cooling water tank 12 comprises emergent waste heat discharge refrigeratory 13, one end that emergent waste heat is discharged refrigeratory 13 is connected with condensate piping isolation valve 15, condensate piping isolation valve 15 is connected with moisturizing pipeline isolation valve 16, between condensate piping isolation valve 15 and moisturizing pipeline isolation valve 16, be connected with condensate pipe line interface 18, the other end that emergent waste heat is discharged refrigeratory 13 is connected with vapour line interface 17, emergent waste heat discharge refrigeratory 13 two ends be also connected with emergence compensating water case 14 in parallel respectively.
Reactor coolant loop is carried out major accident prevention to be had with the key equipment of mitigation strategy:
1) accident cooling water tank
Accident cooling water tank provides hot trap for steam generator secondary side passive residual heat removal.Accident cooling water tank structure in the form of a ring, is arranged in containment outside and approaches position, its civil engineering structure and the containment Uniting at containment cylindrical shell top.And be designed with moisturizing interface and drainage interface, to be water tank water-filling and draining between turn(a)round before starting.
2) emergent waste heat is discharged refrigeratory
Emergent waste heat is discharged refrigeratory and has been comprised upper and lower two tube sheets, and tube sheet passes and is fixed on the tank wall of accident cooling water tank.Upper and lower tube sheet is connected with upper and lower end socket respectively.Upper cover is connected with main steam line by pipeline, and low head is connected with solidifying waterpipe by pipeline.
3) emergence compensating water case
Emergence compensating water case is a hydrostatic column with ellipse head.At system run duration, in the time that the reduction of steam generator secondary side water level reaches certain water level, the isolation valve injecting on pipeline is opened, the water steam injection generator secondary side in emergence compensating water case, the reduction of bucking-out system run duration steam generator secondary side water level.
4) fast pressure relief valve
During the normal operation of unit and design basis accident, fast pressure relief valve is in closed condition, by the overpressure protection of pressurizer safety valve realization response reactor coolant system.Under major accident operating mode, fast pressure relief valve is carried out discharge pressure relief, prevents high-voltage fuse heap.
5) accident vent valve
When normal reactor operation, this valve closing, is the isolation valve on a border, loop; When accident, open this valve, discharge the non-condensable gas at reactor pressure vessel top.
Specific works flow process of the present invention is as follows:
In the time sending accident exhaust signal, open two serial accident vent valves, the incoagulability gas that accumulates in reactor pressure vessel top is discharged to reactor pressure vessel, alleviate damage sequence.
Under major accident operating mode, fast pressure relief valve is carried out discharge pressure relief, process rules manually opened valve by operator according to relevant major accident at master-control room or long-range shutdown station, complete the fast pressure relief of reactor coolant loop, thereby avoid the generation of high-voltage fuse heap and the direct heating of containment.
In the time sending steam generator secondary side passive system enabling signal, open the isolation valve of solidifying waterpipe, steam generator secondary side Heat Discharging System of Chinese is communicated with.After system drops into, the condensed water steam injection of cooler tube side generator secondary side, after the heating of primary side reactor coolant, become steam, enter the pipe side of refrigeratory through system jet chimney, after transferring heat to the water of accident cooling water tank, be again condensed into water, return to again steam generator secondary side, form Natural Circulation.System is delivered to refrigeratory by steam generator by the heat in reactor coolant, then passes to the water in cooling water tank, and then by evaporation of water in cooling water tank, heat is finally taken out of, maintains the safety of reactor.
After system puts into operation, if reducing, steam generator secondary side water level reach a certain height, the isolation valve of emergence compensating water pipeline, the water steam injection generator secondary side in water supply tank, the reduction of bucking-out system run duration steam generator secondary side water level.After water filling finishes, operator answers manual operation to close the isolation valve of moisturizing pipeline.
Claims (1)
1. a PWR nuclear power plant reactor coolant loop, it is characterized in that: it comprises accident cooling water tank (12), in accident cooling water tank (12), be provided with emergent waste heat and discharge refrigeratory (13), one end that emergent waste heat is discharged refrigeratory (13) is connected with condensate piping isolation valve (15), condensate piping isolation valve (15) is connected with moisturizing pipeline isolation valve (16), between condensate piping isolation valve (15) and moisturizing pipeline isolation valve (16), be connected with condensate pipe line interface (18), the other end that emergent waste heat is discharged refrigeratory (13) is connected with vapour line interface (17), the two ends that emergent waste heat is discharged refrigeratory (13) are also connected with emergence compensating water case (14) in parallel respectively.
Priority Applications (4)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201210544043.7A CN103871509A (en) | 2012-12-14 | 2012-12-14 | Pressurized water reactor nuclear power plant reactor coolant system |
| PCT/CN2013/089029 WO2014090144A1 (en) | 2012-12-14 | 2013-12-11 | Reactor cooling agent system of pressurized water reactor nuclear power plant |
| ARP130104687A AR093971A1 (en) | 2012-12-14 | 2013-12-13 | COOLING LIQUID SYSTEM FOR THE REACTOR OF A NUCLEAR PRESSURE WATER CENTER |
| ZA2015/05016A ZA201505016B (en) | 2012-12-14 | 2015-07-13 | Reactor cooling agent system of pressurized water reactor nuclear power plant |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201210544043.7A CN103871509A (en) | 2012-12-14 | 2012-12-14 | Pressurized water reactor nuclear power plant reactor coolant system |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN103871509A true CN103871509A (en) | 2014-06-18 |
Family
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Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201210544043.7A Pending CN103871509A (en) | 2012-12-14 | 2012-12-14 | Pressurized water reactor nuclear power plant reactor coolant system |
Country Status (4)
| Country | Link |
|---|---|
| CN (1) | CN103871509A (en) |
| AR (1) | AR093971A1 (en) |
| WO (1) | WO2014090144A1 (en) |
| ZA (1) | ZA201505016B (en) |
Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105895172A (en) * | 2014-12-26 | 2016-08-24 | 姚明勤 | Quick and effective design measure for passive safety of pressurized water reactor |
| CN105957567A (en) * | 2016-05-06 | 2016-09-21 | 中国核动力研究设计院 | Steam generator secondary side passive residual heat removal system |
| CN106653109A (en) * | 2016-12-30 | 2017-05-10 | 福建福清核电有限公司 | Experimental research device for secondary side passive residual heat removal system (PRS) |
| CN107845436A (en) * | 2017-09-27 | 2018-03-27 | 中国核电工程有限公司 | Long-range shutdown station control method when PWR nuclear power plant main control room can not reside |
| CN113140338A (en) * | 2021-03-26 | 2021-07-20 | 中广核工程有限公司 | Emergency waste heat discharging and water supplementing system for nuclear power plant |
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| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN107195337A (en) * | 2017-06-05 | 2017-09-22 | 华北电力大学 | One kind is used for nuclear power plant's Surge line piping thermally stratified layer and alleviates equipment |
| CN109712726B (en) * | 2017-10-25 | 2024-03-26 | 中国船舶重工集团公司第七一九研究所 | Ocean nuclear power platform reactor waste heat discharge system |
| CN111755139B (en) * | 2020-04-20 | 2023-11-14 | 中国核电工程有限公司 | Design method of pressure vessel stack top exhaust control strategy under accident working condition |
| CN111785399B (en) * | 2020-07-06 | 2023-06-20 | 武汉第二船舶设计研究所(中国船舶重工集团公司第七一九研究所) | System for be used for ocean nuclear power platform heat to derive |
| CN112908500B (en) * | 2021-01-14 | 2024-05-10 | 中广核研究院有限公司 | Volume control method for non-condensable gas at top of pressure vessel |
| CN115196701A (en) * | 2022-06-23 | 2022-10-18 | 珠海格力电器股份有限公司 | Water treatment equipment for integrated cold station, integrated cold station and control method |
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| US3847735A (en) * | 1970-07-10 | 1974-11-12 | Babcock & Wilcox Co | Nuclear reactor safety system |
| US3865688A (en) * | 1970-08-05 | 1975-02-11 | Frank W Kleimola | Passive containment system |
| US4239596A (en) * | 1977-12-16 | 1980-12-16 | Combustion Engineering, Inc. | Passive residual heat removal system for nuclear power plant |
| CN201946323U (en) * | 2011-01-05 | 2011-08-24 | 中科华核电技术研究院有限公司 | Emergency water supply system for nuclear power station |
| CN203026169U (en) * | 2012-12-14 | 2013-06-26 | 中国核动力研究设计院 | Reactor cooling agent system of pressurized water reactor nuclear power plant |
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| US5377243A (en) * | 1993-10-18 | 1994-12-27 | General Electric Company | Passive containment cooling system with drywell pressure regulation for boiling water reactor |
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| CN201689688U (en) * | 2010-06-04 | 2010-12-29 | 中科华核电技术研究院有限公司 | System for cooling reactor core, filling water in reactor cavity and guiding out heat of containment |
| CN102169733B (en) * | 2011-02-14 | 2013-10-23 | 中国核电工程有限公司 | Passive and active combined special safety system for nuclear power plant |
-
2012
- 2012-12-14 CN CN201210544043.7A patent/CN103871509A/en active Pending
-
2013
- 2013-12-11 WO PCT/CN2013/089029 patent/WO2014090144A1/en active Application Filing
- 2013-12-13 AR ARP130104687A patent/AR093971A1/en active IP Right Grant
-
2015
- 2015-07-13 ZA ZA2015/05016A patent/ZA201505016B/en unknown
Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3847735A (en) * | 1970-07-10 | 1974-11-12 | Babcock & Wilcox Co | Nuclear reactor safety system |
| US3865688A (en) * | 1970-08-05 | 1975-02-11 | Frank W Kleimola | Passive containment system |
| US4239596A (en) * | 1977-12-16 | 1980-12-16 | Combustion Engineering, Inc. | Passive residual heat removal system for nuclear power plant |
| CN201946323U (en) * | 2011-01-05 | 2011-08-24 | 中科华核电技术研究院有限公司 | Emergency water supply system for nuclear power station |
| CN203026169U (en) * | 2012-12-14 | 2013-06-26 | 中国核动力研究设计院 | Reactor cooling agent system of pressurized water reactor nuclear power plant |
Cited By (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105895172A (en) * | 2014-12-26 | 2016-08-24 | 姚明勤 | Quick and effective design measure for passive safety of pressurized water reactor |
| CN105957567A (en) * | 2016-05-06 | 2016-09-21 | 中国核动力研究设计院 | Steam generator secondary side passive residual heat removal system |
| 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) |
| CN107845436A (en) * | 2017-09-27 | 2018-03-27 | 中国核电工程有限公司 | Long-range shutdown station control method when PWR nuclear power plant main control room can not reside |
| CN107845436B (en) * | 2017-09-27 | 2023-11-14 | 中国核电工程有限公司 | Remote shutdown station control method for main control room of pressurized water reactor nuclear power plant when not being resident |
| CN113140338A (en) * | 2021-03-26 | 2021-07-20 | 中广核工程有限公司 | Emergency waste heat discharging and water supplementing system for nuclear power plant |
Also Published As
| Publication number | Publication date |
|---|---|
| AR093971A1 (en) | 2015-07-01 |
| ZA201505016B (en) | 2016-10-26 |
| WO2014090144A1 (en) | 2014-06-19 |
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Application publication date: 20140618 |