CN107845434A - A kind of passive reactor core auxiliary coolant system - Google Patents
A kind of passive reactor core auxiliary coolant system Download PDFInfo
- Publication number
- CN107845434A CN107845434A CN201711023772.7A CN201711023772A CN107845434A CN 107845434 A CN107845434 A CN 107845434A CN 201711023772 A CN201711023772 A CN 201711023772A CN 107845434 A CN107845434 A CN 107845434A
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- steam
- coolant system
- auxiliary coolant
- valve
- line
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Classifications
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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
-
- 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
-
- 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
The invention belongs to nuclear safety control technology field, is related to a kind of passive reactor core auxiliary coolant system.Described passive reactor core auxiliary coolant system includes pressure vessel, heat-insulation layer, annular space, built-in material-changing water tank, feed pump, steam turbine, water-supply line, flowing line, and the described annular space of closing is formed between the heat-insulation layer described in the outer wall of described pressure vessel and its periphery;For described built-in material-changing water tank by described water-supply line to described feedwater water supplying pump, described feed pump injects cooling water by described flowing line under the drive of described steam turbine to described annular space.Utilize the passive reactor core auxiliary coolant system of the present invention; by passive means reactor cavity can be accelerated to flood; the critical heat flux density of fused mass arresting device in heap is lifted, so as to avoid pressure vessel wall that boiling crisis occurs, it is ensured that IVR system is effective.
Description
Technical field
The invention belongs to nuclear safety control technology field, is related to a kind of passive reactor core auxiliary coolant system.
Background technology
After the serious nuclear accident of Three Mile Island and Chernobyl Plant, nuclear power circle starts to concentrate strength on to serious core
The prevention of accident and consequence, which are alleviated, to be studied and is tackled key problems, and many conclusions specify that strick precaution and alleviate serious nuclear accident, improve core
Security reliability and the requirement for improving Human Engineering etc..In order to avoid extensive radioactive substance caused by reactor core
Release, the relevant design of reactor core catcher gradually produce, and the autonomous Design in China's generation Ⅲ nuclear power system obtains stage
Under the background of achievement, the nuclear power plant such as ACP1000, CAP1400, ACPR1000 employs fused mass arresting device (IVR) in heap.
The presently disclosed technical scheme about reactor core catcher is a lot, such as US4442065 (Retrofittable
nuclear reactor core catcher)、US5263066(Nuclear reactor equipped with a core
catcher)、US 5343506(Nuclear reactor installation with a core catcher device
and method for exterior cooling of the latter by natural circulation)、
US6353651(Core catcher cooling by heat pipe)、US7558360(Core catcher Cooling)、
US8358732(Core catcher,manufacturing method thereof,reactor containment
Vessel and manufacturing method thereof), (bottom water injection superposition is outside cold by CN201310005308.0
But large-scale passive nuclear plant reactor core catcher), a kind of CN201310005342.8 (large-scale passive PWR nuclear power plant earthenwares
Crucible type reactor core catcher);CN20140268437.9 (fused mass gaseous-waste holdup system in heap after a kind of nuclear power plant accident) etc. has done phase
It should disclose, these technical schemes carry out passive cooling by gravity water filling by elevated tank to reactor core catcher.
But passive cooling water flow velocity is small in such scheme, reactor fused mass arresting device wall critical heat flux density
It is low.Accordingly it is contemplated that by other passive water filling means lifting cooling water flow velocities in addition to gravity water filling, and then lift wall
Critical heat flux density, avoid that boiling crisis occurs, it is ensured that system is effective.
The content of the invention
It is an object of the invention to provide a kind of passive reactor core auxiliary coolant system, so that passive hand can be passed through
Section accelerates reactor cavity to flood, and the critical heat flux density of fused mass arresting device in heap is lifted, so as to avoid pressure vessel wall
Boiling crisis occurs for face, it is ensured that IVR system is effective.
In order to achieve this, in the embodiment on basis, it is cold that the present invention provides a kind of passive reactor core auxiliary
But system, described auxiliary coolant system include pressure vessel, heat-insulation layer, annular space, built-in material-changing water tank, feed pump, vapour
Turbine, water-supply line, flowing line,
The described annular space of closing is formed between heat-insulation layer described in the outer wall of described pressure vessel and its periphery;
Described built-in material-changing water tank is existed by described water-supply line to described feedwater water supplying pump, described feed pump
Cooling water is injected to described annular space by described flowing line under the drive of described steam turbine.
In a preferred embodiment, the present invention provides a kind of passive reactor core auxiliary coolant system, its
Described in feed pump and described steam turbine be coaxial horizontal connection.
In a preferred embodiment, the present invention provides a kind of passive reactor core auxiliary coolant system, its
Described in auxiliary coolant system also include release case and exhaust line, steam done work in described steam turbine after by described
Exhaust line be discharged into described release case.
In a kind of more preferred embodiment, the present invention provides a kind of passive reactor core supplement heat rejecter system
System, wherein described auxiliary coolant system also includes steam generator main steam pipe, steam generator branch road steam pipe line, steamed
Vapour injects pipeline, passes sequentially through described steam generator main steam pipe, steam generator branch road steam pipe line, steam injection
Pipeline, to described steam turbine steam supply.
In a kind of more preferred embodiment, the present invention provides a kind of passive reactor core supplement heat rejecter system
System, wherein described auxiliary coolant system also includes automatically unloading system, automatically unloading system branch pipeline, when described steam
When steam pressure in generator main steam pipe is less than 1MPa, switches to from described automatically unloading system, pass sequentially through institute
The automatically unloading system branch pipeline stated injects pipeline with described steam and carries out steam supply to described steam turbine.
In a kind of more preferred embodiment, the present invention provides a kind of passive reactor core supplement heat rejecter system
System, wherein described auxiliary coolant system also includes the first valve being arranged on described steam generator branch road steam pipe line
Door, the second valve being arranged on described automatically unloading system branch pipeline, it is arranged on described steam injection pipeline and uses
In the 4th valve for controlling the 3rd valve of described turbine speed, being arranged on described exhaust line.
In a kind of more preferred embodiment, the present invention provides a kind of passive reactor core supplement heat rejecter system
System, wherein described auxiliary coolant system also include being arranged on described flowing line the 5th valve, be arranged on it is described
The 6th valve on water-supply line.
In a kind of more preferred embodiment, the present invention provides a kind of passive reactor core supplement heat rejecter system
System, wherein the 4th described valve, the 5th valve are that (the 6th valve is normally opened to be used to make auxiliary cold normally opened valve with the 6th valve
But system is also filled with water in stand-by state, and water hammer damage occurs to shorten the startup time of auxiliary coolant system, when preventing from starting
Equipment and pipeline).
In a kind of more preferred embodiment, the present invention provides a kind of passive reactor core supplement heat rejecter system
System, wherein described auxiliary coolant system also includes battery, for providing power supply for all valves, and start described vapour
Turbine and the accessory power supply for described steam turbine.
In a kind of more preferred embodiment, the present invention provides a kind of passive reactor core supplement heat rejecter system
System, wherein described auxiliary coolant system also includes the valve opening trigger switch being arranged on valve, for controlling all valves
The unlatching of door, described valve opening trigger switch can manually or Remote manually triggers.
In a kind of more preferred embodiment, the present invention provides a kind of passive reactor core supplement heat rejecter system
System, wherein all valves are automatic braking valve or are combined with check-valves.
The beneficial effects of the present invention are, and can using the passive reactor core auxiliary coolant system of the present invention
Fused mass gaseous-waste holdup system (IVR) organically combines in the heap of generation Ⅲ nuclear power station, accelerates reactor cavity to flood by passive means,
The critical heat flux density of fused mass arresting device (lower head of pressure vessel) in heap is lifted, so as to avoid pressure vessel outside wall surface from sending out
Raw boiling crisis, it is ensured that IVR system is effective, further improves npp safety.
Brief description of the drawings
Fig. 1 is the composition figure of exemplary passive reactor core auxiliary coolant system of the invention.
Embodiment
The embodiment of the present invention is further illustrated below in conjunction with accompanying drawing.
The composition of exemplary passive reactor core auxiliary coolant system of the invention is as shown in figure 1, including pressure
Container 1, heat-insulation layer 2, annular space 3, voltage-stablizer 4, automatically unloading system 5 (pass through voltage-stablizer 4 and the phase of pressure vessel 1 through pipeline
Connection), steam generator main steam pipe 6, release case 7, built-in material-changing water tank 8, feed pump 9, steam turbine 10, steam generator
Branch road steam pipe line 11, automatically unloading system branch pipeline 12, steam injection pipeline 13, exhaust line 14, water-supply line 15, row
Water pipeline 16, the first valve 17, the second valve 18, the 3rd valve 19, check-valves 20, the 5th valve 22, the 6th valve the 23, the 4th
Valve 21, valve opening trigger switch 24, battery 25.
The annular of closing is formed between the outer wall for the pressure vessel 1 being placed in reactor pit and its peripheral heat-insulation layer 2
Space 3.
Built-in material-changing water tank 8 is supplied water by water-supply line 15 to feed pump 9, and (built-in material-changing water tank 8 also passes through tap line
Directly it is connected with annular space 3, valve is provided with tap line), feed pump 9 is being coaxial therewith steam turbine connected horizontally
10 axle driving drives the lower flowing line 16 that passes through to inject cooling water to annular space 3.
Pass sequentially through steam generator main steam pipe 6, steam generator branch road steam pipe line 11, steam injection pipeline
13, provide steam to steam turbine 10.And when the steam pressure in steam generator main steam pipe 6 is less than 1MPa, switch to
From first latter linked voltage-stablizer 4 (being used to stablize steam pressure) and automatically unloading system 5, automatically unloading system branch is passed sequentially through
Pipeline 12 injects pipeline 13 with steam and provides steam to steam turbine 10.Steam passes through exhaust line 14 after being done work in steam turbine 10
It is discharged into release case 7.
First valve 17 is arranged on steam generator branch road steam pipe line 11, and the second valve 18 is arranged on automatically unloading system
Unite tap line 12 on, the 3rd valve 19 be arranged on steam injection pipeline 13 on (the 3rd valve 19 is initially in returns seat completely
Open position, the rated speed of steam turbine 10 is adjusted in advance, steam turbine is adjusted by the 3rd valve 19 after the startup of feed pump 9
10 rotating speed), check-valves 20, the 4th valve 21 are arranged on exhaust line 14 (for normally opened valve), and the 5th valve 22 is (to be normally opened
Valve) it is arranged on flowing line 16, the 6th valve 23 is arranged on water-supply line 15 (for normally opened valve).All valves are certainly
Dynamic check valve is combined with check-valves, and valve opening trigger switch 24 is provided with all valves.
Battery 25 is used to provide power supply (valve can be made to keep work at least 8 hours) for all valves, and starts vapour
Turbine 10 and the accessory power supply for steam turbine 10.
The operation principle of the passive reactor core auxiliary coolant system of the invention of above-mentioned example is as follows.
When accident occurs for nuclear power station, primary Ioops pressure and temperature raises rapidly, after reaching setting pressure, the first valve 17
Open, first from steam generator main steam pipe 6 to the steam supply of steam turbine 10;When steam pressure is less than 1.0MPa herein, the
Two valves 18 are opened, and switch to automatically unloading system 5 to the steam supply of steam turbine 10.Pass through steam drive caused by reactor decay heat
Steam turbine 10, and drive feed pump 9 to operate.Exhaust steam after acting is injected in release case 7 by exhaust line 14, and exhaust steam is in release
Condensed in water in case 7.Feed pump 9 is fetched water from built-in material-changing water tank 8, and most cooling water injects the outer wall of pressure vessel 1 with protecting at last
Formed between warm layer 2 in annular space 3.Occur accident in nuclear power plant, during 1 superpressure of pressure vessel, passive reaction of the invention
Heap Core Auxiliary Cooling System can also be manually booted automatic start, supplement heat rejecter by operator.
Obviously, those skilled in the art can carry out the essence of various changes and modification without departing from the present invention to the present invention
God and scope.So, if belonging to the model of the claims in the present invention and its equivalent technology to these modifications and variations of the present invention
Within enclosing, then the present invention is also intended to comprising including these changes and modification.Above-mentioned embodiment is illustrating to the present invention
Bright, the present invention can also be implemented with other ad hoc fashions or other particular forms, without departing from idea of the invention or originally
Matter feature.Therefore, it is regarded as from the point of view of the embodiment of description is in terms of any illustrative and non-limiting.The model of the present invention
Enclosing should be illustrated by appended claims, and any change equivalent with the intention of claim and scope should also be included in the present invention
In the range of.
Claims (10)
- A kind of 1. passive reactor core auxiliary coolant system, it is characterised in that:Described auxiliary coolant system includes pressure Container, heat-insulation layer, annular space, built-in material-changing water tank, feed pump, steam turbine, water-supply line, flowing line,The described annular space of closing is formed between heat-insulation layer described in the outer wall of described pressure vessel and its periphery;Described built-in material-changing water tank is by described water-supply line to described feedwater water supplying pump, and described feed pump is described Steam turbine drive under cooling water injected to described annular space by described flowing line.
- 2. auxiliary coolant system according to claim 1, it is characterised in that:Described feed pump is with described steam turbine Coaxial horizontal connection.
- 3. auxiliary coolant system according to claim 1, it is characterised in that:Described auxiliary coolant system also includes release Case and exhaust line, steam are discharged into described release case by described exhaust line after being done work in described steam turbine.
- 4. auxiliary coolant system according to claim 3, it is characterised in that:Described auxiliary coolant system also includes steam Generator main steam pipe, steam generator branch road steam pipe line, steam injection pipeline, pass sequentially through described steam generator Main steam pipe, steam generator branch road steam pipe line, steam injection pipeline, to described steam turbine steam supply.
- 5. auxiliary coolant system according to claim 4, it is characterised in that:Described auxiliary coolant system also includes automatic Depressurized system, automatically unloading system branch pipeline, when the steam pressure in described steam generator main steam pipe is less than During 1MPa, switch to from described automatically unloading system, pass sequentially through described automatically unloading system branch pipeline with it is described Steam injects pipeline and carries out steam supply to described steam turbine.
- 6. auxiliary coolant system according to claim 5, it is characterised in that:Described auxiliary coolant system also includes setting The first valve on described steam generator branch road steam pipe line, it is arranged on described automatically unloading system branch pipeline The second valve, be arranged on described steam injection pipeline and be used to control the 3rd valve of described turbine speed, set The 4th valve on described exhaust line.
- 7. auxiliary coolant system according to claim 6, it is characterised in that:Described auxiliary coolant system also includes setting The 5th valve on described flowing line, the 6th valve being arranged on described water-supply line,Described the 4th valve, the 5th valve and the 6th valve is normally opened valve.
- 8. auxiliary coolant system according to claim 7, it is characterised in that:Described auxiliary coolant system also includes electric power storage Pond, for providing power supply for all valves, and start described steam turbine and powered for the accessory of described steam turbine.
- 9. auxiliary coolant system according to claim 7, it is characterised in that:Described auxiliary coolant system also includes setting Valve opening trigger switch on valve, the valvular unlatching for controlling.
- 10. auxiliary coolant system according to claim 7, it is characterised in that:All valves be automatic braking valve or It is combined with check-valves.
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CN201711023772.7A CN107845434B (en) | 2017-10-27 | 2017-10-27 | Reactor core auxiliary cooling system of passive reactor |
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CN201711023772.7A CN107845434B (en) | 2017-10-27 | 2017-10-27 | Reactor core auxiliary cooling system of passive reactor |
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Cited By (3)
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CN109273109A (en) * | 2018-11-13 | 2019-01-25 | 中国核动力研究设计院 | A kind of fusant containment gaseous-waste holdup system |
CN109346196A (en) * | 2018-11-13 | 2019-02-15 | 中国核动力研究设计院 | Gaseous-waste holdup system in the fusant heap that a kind of active and passive cooling combines |
CN110890162A (en) * | 2018-09-07 | 2020-03-17 | 中广核(北京)仿真技术有限公司 | Core cooling system and method |
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