CN104620324B - For the Enclosed flare system alleviated after coolant loss accident - Google Patents
For the Enclosed flare system alleviated after coolant loss accident Download PDFInfo
- Publication number
- CN104620324B CN104620324B CN201380042044.4A CN201380042044A CN104620324B CN 104620324 B CN104620324 B CN 104620324B CN 201380042044 A CN201380042044 A CN 201380042044A CN 104620324 B CN104620324 B CN 104620324B
- Authority
- CN
- China
- Prior art keywords
- containment
- gas
- primary
- burning
- flame arrester
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Active
Links
- 239000002826 coolant Substances 0.000 title claims description 20
- 239000007789 gas Substances 0.000 claims abstract description 55
- 239000001257 hydrogen Substances 0.000 claims abstract description 34
- 229910052739 hydrogen Inorganic materials 0.000 claims abstract description 34
- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 claims abstract description 32
- 239000000203 mixture Substances 0.000 claims abstract description 12
- 238000000034 method Methods 0.000 claims abstract description 10
- 238000001816 cooling Methods 0.000 claims abstract description 8
- 238000002955 isolation Methods 0.000 claims abstract description 6
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 17
- 230000003321 amplification Effects 0.000 claims description 4
- 238000003199 nucleic acid amplification method Methods 0.000 claims description 4
- 238000002485 combustion reaction Methods 0.000 claims description 3
- 230000005619 thermoelectricity Effects 0.000 claims description 3
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 abstract description 4
- 239000001301 oxygen Substances 0.000 abstract description 4
- 229910052760 oxygen Inorganic materials 0.000 abstract description 4
- 239000003795 chemical substances by application Substances 0.000 abstract 1
- 239000000446 fuel Substances 0.000 description 16
- 239000011162 core material Substances 0.000 description 14
- 230000004888 barrier function Effects 0.000 description 10
- 230000000694 effects Effects 0.000 description 8
- 238000006243 chemical reaction Methods 0.000 description 7
- IJGRMHOSHXDMSA-UHFFFAOYSA-N Atomic nitrogen Chemical compound N#N IJGRMHOSHXDMSA-UHFFFAOYSA-N 0.000 description 6
- 239000000047 product Substances 0.000 description 5
- 238000004891 communication Methods 0.000 description 3
- 239000000498 cooling water Substances 0.000 description 3
- 238000013461 design Methods 0.000 description 3
- 239000012530 fluid Substances 0.000 description 3
- 229910052757 nitrogen Inorganic materials 0.000 description 3
- 239000002918 waste heat Substances 0.000 description 3
- 238000010276 construction Methods 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 238000000605 extraction Methods 0.000 description 2
- 230000006870 function Effects 0.000 description 2
- 150000002431 hydrogen Chemical class 0.000 description 2
- 239000000463 material Substances 0.000 description 2
- 238000002156 mixing Methods 0.000 description 2
- 239000003758 nuclear fuel Substances 0.000 description 2
- 230000000630 rising effect Effects 0.000 description 2
- 238000003860 storage Methods 0.000 description 2
- QCWXUUIWCKQGHC-UHFFFAOYSA-N Zirconium Chemical compound [Zr] QCWXUUIWCKQGHC-UHFFFAOYSA-N 0.000 description 1
- 229910001093 Zr alloy Inorganic materials 0.000 description 1
- 238000009825 accumulation Methods 0.000 description 1
- 230000009471 action Effects 0.000 description 1
- 230000003190 augmentative effect Effects 0.000 description 1
- 230000006399 behavior Effects 0.000 description 1
- 238000009835 boiling Methods 0.000 description 1
- 238000009924 canning Methods 0.000 description 1
- 239000002775 capsule Substances 0.000 description 1
- 238000006555 catalytic reaction Methods 0.000 description 1
- 230000008859 change Effects 0.000 description 1
- 150000001875 compounds Chemical class 0.000 description 1
- 239000011258 core-shell material Substances 0.000 description 1
- 230000003247 decreasing effect Effects 0.000 description 1
- 238000004200 deflagration Methods 0.000 description 1
- 238000004146 energy storage Methods 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 238000003197 gene knockdown Methods 0.000 description 1
- 238000005338 heat storage Methods 0.000 description 1
- 238000002347 injection Methods 0.000 description 1
- 239000007924 injection Substances 0.000 description 1
- 230000001788 irregular Effects 0.000 description 1
- 239000007788 liquid Substances 0.000 description 1
- 238000012423 maintenance Methods 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 238000005259 measurement Methods 0.000 description 1
- 230000007246 mechanism Effects 0.000 description 1
- 229910052751 metal Inorganic materials 0.000 description 1
- 239000002184 metal Substances 0.000 description 1
- 238000013508 migration Methods 0.000 description 1
- 230000005012 migration Effects 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 239000003607 modifier Substances 0.000 description 1
- 238000013021 overheating Methods 0.000 description 1
- 230000003647 oxidation Effects 0.000 description 1
- 238000007254 oxidation reaction Methods 0.000 description 1
- RVTZCBVAJQQJTK-UHFFFAOYSA-N oxygen(2-);zirconium(4+) Chemical compound [O-2].[O-2].[Zr+4] RVTZCBVAJQQJTK-UHFFFAOYSA-N 0.000 description 1
- 238000012856 packing Methods 0.000 description 1
- 230000000149 penetrating effect Effects 0.000 description 1
- 238000003825 pressing Methods 0.000 description 1
- 238000005086 pumping Methods 0.000 description 1
- 230000005258 radioactive decay Effects 0.000 description 1
- 230000003014 reinforcing effect Effects 0.000 description 1
- 238000007789 sealing Methods 0.000 description 1
- 238000000926 separation method Methods 0.000 description 1
- 239000000243 solution Substances 0.000 description 1
- 230000003068 static effect Effects 0.000 description 1
- 239000013589 supplement Substances 0.000 description 1
- 238000012546 transfer Methods 0.000 description 1
- 238000011144 upstream manufacturing Methods 0.000 description 1
- 239000002912 waste gas Substances 0.000 description 1
- 229910052726 zirconium Inorganic materials 0.000 description 1
- 229910001928 zirconium oxide Inorganic materials 0.000 description 1
- ATYZRBBOXUWECY-UHFFFAOYSA-N zirconium;hydrate Chemical compound O.[Zr] ATYZRBBOXUWECY-UHFFFAOYSA-N 0.000 description 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
- G21C9/04—Means for suppressing fires ; Earthquake protection
- G21C9/06—Means for preventing accumulation of explosives gases, e.g. recombiners
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/28—Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core
- G21C19/30—Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core with continuous purification of circulating fluent material, e.g. by extraction of fission products deterioration or corrosion products, impurities, e.g. by cold traps
- G21C19/317—Recombination devices for radiolytic dissociation products
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/18—Emergency cooling arrangements; Removing shut-down heat
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Physics & Mathematics (AREA)
- 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)
Abstract
A kind of method for controlling the burning-up of hydrogen in LOCA, including opening valve allows the first primary containment gas to flow.Second subprime containment gas is drawn by flame arrester.Burn the first and second containment gases in the quick burning region of isolation.Using the first and second containment gases after thermoelectric element cooling burning, and the non-combustible oxygen-enriched agent product gas mixture of cooling is discharged by the second flame arrester.Enclosed flare system for water-cooled reactor includes air inlet flame arrester and exhaust flame arrester, and they position the quick burning of the first primary containment gas and second subprime containment gas is limited in housing in the housing.
Description
Technical field
The disclosure is advocated to disclosing sequence number No.61/680,008's in US provisional patent filed in August in 2012 6 days
Priority.
The disclosure is related generally to after reactor emergency cut-off and concurrent website have a power failure for the closed of nuclear power plant
Torch (contained flare) system.
Background technology
The nuclear power plant of boiling water reactor (BWR) type is that many electric industries promote electric power production in the whole world.BWR nuclear reactions
Heap is typically designed as endangering containment (containment) method using radionuclide, according to " zero release design object base
Present principles, the method prevents the release of radionuclide by multibarrier.
The typical realisation of multibarrier method includes：By the of the design liaison of synthetic and fuel ball itself
One barrier, and the second barrier represented by the closed container of commonly referred to " fuel pencil ".By many fuel pins (pin)
Support and be positioned in the referred to as removable structure of fuel rod, and many adjacent fuel bar construction reactors " core ".
3rd barrier is by the closed primary cooling water hydraulic loop of encapsulating nuclear fuel " core " and by primary reaction pile structure bag
The charging of the primary cooling water of envelope is represented, and primary reaction pile structure is connected with the balance of primary return component, primary return component
Such as primary cooling pump, (multiple) are primary to secondary cooling agent loop heat exchanger, Interconnecting conduit system, instrument with subordinate control
Device and other primary return support equipments.Aqueous water in the big envelope of core be from core remove waste heat, and thus will construct core
Material is maintained at the essential characteristic of the layout strategy at a temperature of the operating limit less than them.
Term " LOCA " refers to when the heat provided by water removes the situation present in core when function is lost or damaged substantially.
The result of LOCA is the rising of core material heats and is finally that the core shell for overheating enters in the thermal region of design limit temperatures.
Sometimes, residual steam chemically reacts with fuel canning material, zirconium, to form zirconium oxide and hydrogen.Hydrogen and steam pair
Surrounding structure proposes pressurization challenge.
Primary return component is contained in the 4th barrier, and the 4th barrier prevents radionuclide release.4th barrier claims
It is " primary containment ", its whole primary return component of encapsulating.Typically, the atmosphere of primary containment is inactive gas, with
The burning of hydrogen is prevented when hydrogen release is put into the region.Primary containment is typically the concrete structure of reinforcing, its have to
Abundant but limited ability of the anti-internal pressurization without leakage.
5th barrier is the sealing structure of referred to as secondary security shell.Built for many BWR reactors and designed, the 5th screen
Barrier is equipped with air atmosphere, and is designed as resistance unlike the big too many internal pressure of exterior circumference pressure.If by fuel can
Hydrogen with the reaction generation of primary cooling steam destroys the 4th barrier, primary containment structure, then and then secondary security shell
Hydrogen concentration level in atmosphere will rise to the point that air, hydrogen, gas-vapor mix can become flammable.In this case, exist
The 5th and final barrier between the radionuclide stock of reactor core and external environment condition can be due to by some form of igniting
Excessive pressurization when lighting of the secondary security sheath gas atmosphere that source (such as electrical power spark or static discharge) causes and fail.
Even so, current water cooled nuclear reactor is also foolproof, and provide to supply of electric power, with water and behaviour
Work person's fail safe operation for minimal relying on of action, with close or " SCRAM " reactor core in nuclear reaction, and by hot merit
Rate level is reduced to the fraction of nominal operation power level.If the primary cooling stream through core is not kept or recovers, that
It is remaining compared with low-heat that the radioactive decay of the fission product material in by being still deposited in reactor core after the SCRAM causes
Power level is enough to overheat reactor core substantially.If not making the outer electrical power pause long period of the device from power network, with
Can become to exhaust or otherwise not available as backup electrical power source (such as battery or gen-set), then power plant
Website power failure can be experienced.
Nuclear reactor also slows down the slow accumulation of the hydrogen caused by other non-LOCA effects using various passive systems.In advance
Inerting, for example, before being initiated or start during together with continuous power generating operation, generated in primary containment and exhausted
The atmosphere of oxygen.When initially construction power plant, or during some not operation periods, inactive gas (usually nitrogen) is discharged into
Replace the air in the space in primary containment.Oxygen activity in torpescence space is had decreased below hydrogen burning by the method
Required level.Another passive system is catalysis hydrogen recombiner.Hydrogen recombiner by with the mixed proportion less than Flammability limits by hydrogen
It is compound with oxygen, to produce water and reduce the hydrogen concentration in containment.
In extremely rare website power-off condition, the hydrogen generation after LOCA is very quick and can flood some passive hydrogen
Relieving system.
Brief description of the drawings
From the detailed description of ensuing disclosed non-limiting embodiments, various features will for those skilled in the art
Become apparent.Can be briefly described below with the accompanying drawing for describing in detail：
Fig. 1 is the schematic diagram of reactor building of nuclear, and it illustrates amplification just like disclosed the Enclosed flare system placed
Multibarrier method for designing；And
Fig. 2 is according to an expanded schematic diagram for the Enclosed flare system of disclosed non-limiting embodiments.
Specific embodiment
Fig. 1 schematically illustrates the water cooled nuclear reactor 10 related to external environment condition.During and after power operation,
Water cooled nuclear reactor 10 transmits heat from the reactor core encapsulated from fuel can 12 to heat exchanger using primary return cooling agent,
Heat transfer is entered secondary cooling water aspiration circuit and the steamturbine of electrical power is produced to drive by the heat exchanger, and is removed and discharged
Waste heat.Temperature difference between the external environment condition of internal heat resource and release waste heat is bigger, then more effectively obtain turbomachinery work((example
Such as the rotation of generator).There is the demand of low temperature accordingly, there exist inside with high temperature and in external environment condition.This causes to expect
Water cooled nuclear reactor 10 is positioned adjacent to water source or other cold heat storages are produced for effective electrical power.
Water cooled nuclear reactor 10 generally includes the fuel ball 5 universally in fuel can 12, the fuel can
12 have the structure of surrounding's primary coolant loop 14 being included in primary containment structure 16.Secondary security shell structure 18 around
Primary containment structure 16, and including secondary cooling agent loop 20, secondary cooling agent loop 20 and primary coolant loop with
And other machine space thermal communications, other machines space includes but is not limited to turbine, generator, refuelling compartment, steam-electric power
The (not shown)s such as machine capsule, pump chamber.
Coolant loss accident (" LOCA ") can cause exposing and fuel temperature rising as a result for fuel can 12,
The fuel temperature rises the oxidation of the zircaloy, fuel can 12 that can cause to react with residual superheated steam.The reaction is heat release
And produce hydrogen, if primary coolant loop 14 is damaged, then hydrogen can escape into primary containment structure together with steam
In 16.The quality rate of release of hydrogen may be about kilogram per second.As zirconium-water reaction is carried out, primary coolant loop 14 it is interior
Tolerant experience temperature rises, as a result, the pressure in primary coolant loop 14 rises, and setting for circuit elements can be exceeded so as to reach
Count the level of pressure.Operator can select：Surrounding is discharged to by by some in the content in primary coolant loop 14
The pressure in primary coolant loop is reduced in primary containment structure 16；Or wait until by reaching uncontrollably
The pressure of the degree being discharged into primary containment structure 16 around, makes some parts in primary coolant loop 14 damage to mistake
The degree of effect.At this point, due to introducing the steam and hydrogen of the mixing from primary coolant loop 14, therefore pressure is around just
Rise in level security shell structure 16.
Thus freeing that steam and hydrogen and the gained of the torpescence atmosphere generally remained in primary containment structure 16
The danger that mixture is not lighted, because lacking air within this space.But, when pressure rises, primary containment structure
16 same cases for experiencing the presence of primary coolant loop 14 a little earlier.Over-pressed result in primary containment structure 16 with plus
Pressure steam, hydrogen and inactive gas mixture are from primary coolant loop 14 to the release in primary containment structure 16 in type
Upper difference, and it is more serious than it.Because the release mixture gone in the air atmosphere of secondary security shell structure 18
Hydrogen content can produce flammable mixture in secondary security sheath gas atmosphere, and it can cause in putting from reactor fuel when lighting
The 5th and Quick-pressing and the failure of last containment boundary between penetrating property nucleic dispensing and outside atmosphere.Unless using
Hydrogen activity is maintained below flammable limits by system in secondary security sheath gas atmosphere, can otherwise be lighted there may be possible herein
Admixture of gas.
Enclosed flare system 30 is included in air inlet 32, secondary security shell structure 18 in primary containment structure 16
Air inlet 34 and return to the exhaust outlet 36 in secondary security shell structure 18.Valve system 38 (for example meets the strict demand of nuclear industry
With high expected core certification magnetic valve) control from primary containment structure 16 to the stream in Enclosed flare system 30.Should manage
Solution, can additionally provide various crash protection systems.Enclosed flare system 30 operates to prevent secondary security shell structure
Hydrogen burning situation after LOCA in 18.
Reference picture 2, under the background of Fig. 1, Enclosed flare system 30 generallys include housing 40, and housing 40 has for coming
Air inlet flame arrester 42 from the entrance gas of secondary security shell structure 18, for the entrance from primary containment mechanism 16
The air inlet flame arrester 53 of gas, inactive gas syringe 44, flame source 46, power source 48 and exhaust flame arrester
50.It should be appreciated that various other components and subsystem can be provided alternatively or additionally.
Air inlet flame arrester 53 in the downstream location of air inlet 32 in housing 40, in the primary pipeline 52 and to enclose
Sealed around it, the primary pipeline 52 connects hydrogen and vapour mixture from primary containment structure 16 by valve system 38
Pass to the inside of Enclosed flare system.Air inlet flame arrester 42 and 53, and exhaust flame arrester 50 catches as flame
Device (flame trap) is operated, and the flame arrestor is by forcing flame front through too narrow so that the logical of flame propagation can not be allowed
Road extinguishes fuel combustion.These passages can be rule, such as into silk screen or metal perforated plate, or be irregular, example
As into random packing elements.That is, air inlet flame arrester 42 and 53 and exhaust flame arrester 50 is by the quick burning in housing 40
(deflagration) the quick burning region 54 and hot product gas region 56 of limitation extremely isolation.By relative to closed type torch shell
The free convection of generally colder a large amount of secondary security sheath gas bodies in the outside of body 40, these hot quick burnings and product gas region change
It has been apt to the throughput of the secondary security sheath gas body of extraction.
Air inlet 32 is thus operated as extracting device, is taken out from secondary security shell structure 18 with by air inlet flame arrester 42
Air is taken, and then passes through the exhaust flame arrester 50 of the upstream of exhaust port 36 and discharged.The arrangement is by combustible gas mixture
Quick burning is limited in housing 40.Extracting device forms the suction to non-combustible secondary security sheath gas body from kinetic energy using hydrodynamics
Power, the kinetic energy is provided by the non-combustible primary containment gas jet of the high speed discharged by valve system 38.From the release of primary containment
Gas jet allow not by movable part occur pumping or mixing, and thus Maintenance free.The He of air inlet flame arrester 42
53, and exhaust flame arrester 50 is used as safety device, with knock down the flame, so as to prevent hydrogen quick burning from migrating to outside housing 40
Side.Furthermore, it is possible to prevent air inlet flame arrester 42 and 53, and exhaust flame arrester 50 from damaging.
Flame source 46 is set (for example to expand spark lighter (ASI:Augmented spark igniter)) constantly grasp
Make to light the hydrogen from primary containment structure 16 and the air from secondary security shell structure 18.Flame source 46 orientates neighbour as
Fetch the outlet of the primary pipeline 52 from primary containment.The pipeline 52 is also equipped with flame arrester 53, to prevent flame remote
From quick burning region 54 and towards the internal migration of primary cooling structure 16.
Enclosed flare system 30 can responsively run with control subsystem 54, and the control subsystem 54 includes control module
56 (schematically illustrating) and one group of multiple sensor 58 (schematically illustrating) along Enclosed flare system 30.Control subsystem
54 generally include processor, memory and interface.Processor can be any kind of known micro- with desired Performance Characteristics
Processor.Memory can be also with desired Performance Characteristics any computer-readable medium, its storage and release data and
Control algolithm (logic being for example described herein).Interface contribute to other components (such as valve system 38, flame source 46 and
Power source 48) communication.Control subsystem 54 performs control logic, is selected with by, for example, inactive gas syringe 44
Property ground injection inactive gas (such as nitrogen from liquid nitrogen source) control quick burning.
Power source 48 is operated and provides independent self-supporting work(with to such as valve system 38, flame source 46 and control subsystem 54
Rate.It should be appreciated that various other components and subsystem can alternatively or additionally by the energy supply of power source 48.In a disclosure
Non-limiting embodiments in, turbine 60 is positioned in the downstream of valve system 38 and is in fluid communication with primary pipeline 52.By primary pipeline
52 hydrogen steam and the of a relatively high pressure of inactive gas mixture and stream are the energy supply of turbine 60, with driving power source 48
Generator 62, and thus produce the closed type torch equipment energy supply that electrical power comes for flame source 46, control subsystem 54 and correlation.
Alternatively or additionally, thermoelectricity set (thermoelectric cuff) 64 provides power around quick burning region 54
Source.Thermoelectricity set 64 produces electrical power directly with the combustion heat discharged in quick burning region 54.It should be appreciated that can be real
The various additionally or alternatively power origin systems for now being aspirated using the energy discharged from LOCA situations, and the work(for so producing
Rate is used to operate Enclosed flare system equipment, is such as mechanical fans or air blast so as to improve flare system function and effect
Machine provide power, with supplement from secondary security shell be drawn out to Enclosed flare system in stream.
Hot product gas region 56 can be by one group of thermal diode 66 (sometimes referred to as heat pipe or return boiler) around heat two
Pole pipe 66 loads for being thermally coupled with hot product gas in housing 40, and extends out to the secondary security sheath gas atmosphere of surrounding
In, it is thermally coupled for the cooler gas mixture with the other side.Thermal diode 66 is substantially a series of heat pipe, and they are grasped
From housing 40 be dissipated in secondary security sheath gas atmosphere heat by work.Also, it is to be understood, that various other arrangements and combination can
Thus be benefited.
The hydrogen concentration that Enclosed flare system 30 can be adjusted into using the inactive gas steam injected in housing 40
And improve the effect of protected burning-up in quick burning region 54.Enclosed flare system 30 is independence and self energizing, and
Realize it using controlled extraction, waste gas circulation, stack effect and cold storage effect, and less need for or need not outside electric work
Rate helps operate, even in extremely rare website power-off condition.
In the context of explanation (especially in the context of following claims), term " " and " one " and " being somebody's turn to do "
Use with similar reference should be interpreted as both covering odd number and plural number, unless otherwise indicated herein or special by context
Do not deny.The modifier " about " being used in combination with amount includes the value of statement, and with the implication (example indicated by context
Such as, it includes the degree of error related to the measurement result of specified quantitative).All scopes disclosed herein include end points, and
And end points can be combined independently of one another.It should be appreciated that relative positional terms such as "front", "rear", " on ", D score,
" ... on ", " ... under " etc. be normal operating posture with reference to equipment and should not be considered as limitation in addition.
Although different non-limiting embodiments have the component for specifically exemplifying, embodiments of the invention are not limited to
These are specifically combined.It is possible to be used in combination with coming from from the feature of any one or component in other non-limiting embodiments
Some in the component of any one or feature in non-limiting embodiments.For example, based on the teaching, alternatively it is conceivable to, for electric work
The additional-energy of rate generation can be extracted from other energy storage devices for existing in this case, such as using installed in relief pipe
Turbine generation unit in road, the volume that the gas relief line encapsulates the primary coolant loop 14 with high-pressure fluid with have
The volume connection of the encapsulating of primary containment structure 16 of much lower Fluid pressure.
It should be appreciated that throughout some accompanying drawings, identical numeral indicates correspondence or similar element.It should also be understood that
It is that, although disclosing specific component arrangement in the embodiment for exemplifying, other arrangements will be benefited from it.
Although showing, describing and claimed specific sequence of steps it should be appreciated that unless otherwise noted, can
With (separation or combination) execution step in any order, and will be benefited from the disclosure.
Preceding description is exemplary without being limited by the limitation in it.Disclosed herein various unrestricted implementations
Example, but, it will be appreciated by persons skilled in the art that the various modifications and variations according to above-mentioned teaching will fall into appended claims
In the range of.It is, therefore, to be understood that within the scope of the appended claims, the disclosure can with as specific descriptions
It is practiced otherwise than.Thus, appended claims should be studied to determine real scope and content.
Claims (13)
1. it is a kind of in LOCA control hydrogen burning-up method, including：
Valve is opened to allow the first containment gas to flow；
Second containment gas is drawn by entrance flame arrester；
Burn the first and second containments gas in the quick burning region of isolation；
Using the first and second containment gases after thermoelectric element cooling burning；With
The product of the cooling produced by the burning of the mixture of the first and second containment gases is discharged by outlet flame arrester
Thing admixture of gas.
2. it is according to claim 1 in LOCA control hydrogen burning-up method, it is characterised in that be additionally included in institute
State burning described first and second in the quick burning region of the isolation between entrance flame arrester and the outlet flame arrester
Containment gas.
3. the method for controlling the burning-up of hydrogen in LOCA according to claim 1, it is characterised in that also including by institute
The quick burning zone location of isolation is stated in housing.
4. it is according to claim 1 in LOCA control hydrogen burning-up method, it is characterised in that also including from
The combustion heat next life success rate discharged in the quick burning region of the isolation.
5. a kind of Enclosed flare system for water cooled nuclear reactor, including：
Housing, and
Air inlet flame arrester and exhaust flame arrester, the quick burning of the first containment gas and the second containment gas is limited
System is in the housing；
Wherein, the Enclosed flare system also includes flame source, so that the first safe sheath gas from primary containment structure
Body and the second containment gas from secondary security the shell structure quick burning in the housing；
Wherein, the Enclosed flare system also includes primary pipeline, and the primary pipeline will be from the primary containment knot
The first containment gas connection of structure is in the housing；And
Wherein, the Enclosed flare system also includes valve system, for controlling first peace through the primary pipeline
The stream of full sheath gas body.
6. system according to claim 5, it is characterised in that the flame source is amplification spark lighter.
7. system according to claim 6, it is characterised in that it is the flame source energy supply also to come including power source.
8. system according to claim 7, it is characterised in that the power source is turbine, the turbine and described first
Containment gas connection.
9. system according to claim 7, it is characterised in that the power source is thermoelectricity set.
10. system according to claim 5, it is characterised in that also including loading the thermal diode in the housing.
A kind of 11. water cooled nuclear reactors, including：
Primary containment structure；
Secondary security shell structure, it is around the primary containment structure；With
Enclosed flare system, during coolant loss accident (" LOCA "), to make from the primary containment structure
First containment gas quick burning together with the second containment gas from the secondary security shell structure；
Wherein, the water cooled nuclear reactor also includes primary pipeline, and the primary pipeline will be from the primary containment structure
The first containment gas connection in the Enclosed flare system；
Wherein, the water cooled nuclear reactor also includes valve system, for controlling first safety through the primary pipeline
The stream of sheath gas body.
12. water cooled nuclear reactors according to claim 11, it is characterised in that also including amplification spark lighter, to open
Begin the first containment gas and the second containment gas mixture quick burning.
13. water cooled nuclear reactors according to claim 12, it is characterised in that also including power source, think the valve system
System and the amplification spark lighter energy supply.
Applications Claiming Priority (3)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| US201261680008P | 2012-08-06 | 2012-08-06 | |
| US61/680008 | 2012-08-06 | ||
| PCT/US2013/043647 WO2014025446A1 (en) | 2012-08-06 | 2013-05-31 | Contained flare system for post loss-of-coolant accident mitigation |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN104620324A CN104620324A (en) | 2015-05-13 |
| CN104620324B true CN104620324B (en) | 2017-05-31 |
Family
ID=50068476
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201380042044.4A Active CN104620324B (en) | 2012-08-06 | 2013-05-31 | For the Enclosed flare system alleviated after coolant loss accident |
Country Status (4)
| Country | Link |
|---|---|
| JP (1) | JP6340003B2 (en) |
| KR (1) | KR102083508B1 (en) |
| CN (1) | CN104620324B (en) |
| WO (1) | WO2014025446A1 (en) |
Families Citing this family (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105225587B (en) * | 2015-10-29 | 2017-12-19 | 苏州热工研究院有限公司 | A kind of popular science teaching aid and science popularization method on nuclear power plant reactor safety |
| DE102016202452B4 (en) * | 2016-02-17 | 2018-06-21 | Areva Gmbh | Ignition system for ignition of flammable gas mixtures |
| KR102715303B1 (en) | 2016-12-28 | 2024-10-11 | 한화오션 주식회사 | CO2 snuffing system with atmospheric vent structure |
| US10839966B2 (en) * | 2017-05-10 | 2020-11-17 | Westinghouse Electric Company Llc | Vortex driven passive hydrogen recombiner and igniter |
| DE102020003894A1 (en) * | 2020-06-29 | 2021-12-30 | Cellcentric Gmbh & Co. Kg | Pressurized gas storage facility and method for operating a pressurized gas storage facility |
Family Cites Families (13)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE3143989C1 (en) * | 1981-11-05 | 1983-02-03 | Kraftwerk Union AG, 4330 Mülheim | Nuclear power plant with a containment |
| US4780271A (en) * | 1985-10-02 | 1988-10-25 | Westinghouse Electric Corp. | Process and apparatus for burning gases containing hydrogen and for cooling resulting combustion gases |
| JPS62179694A (en) * | 1986-02-03 | 1987-08-06 | 株式会社東芝 | Hydrogen-gas concentration controller in nuclear reactor container |
| DE8816470U1 (en) * | 1988-05-17 | 1989-09-07 | Siemens AG, 1000 Berlin und 8000 München | Device for the controlled combustion of an ignitable hydrogen-air mixture in a nuclear facility |
| JPH06214078A (en) * | 1993-01-14 | 1994-08-05 | Toshiba Corp | Pressure releasing device for nuclear reactor containment vessel |
| JPH0763891A (en) * | 1993-08-27 | 1995-03-10 | Mitsubishi Heavy Ind Ltd | Catalyst type hydrogen igniter |
| DE69611621T2 (en) * | 1995-10-31 | 2001-05-03 | Atomic Energy Of Canada Ltd., Ottawa | SYSTEM FOR PASSIVE EMERGENCY REMOVAL OF HYDROGEN FOR WATER-COOLED CORE REACTORS |
| DE19704608C1 (en) * | 1997-02-07 | 1998-06-10 | Siemens Ag | Convection-driven hydrogen recombination chimney within nuclear power plant containment |
| JP2000009873A (en) * | 1998-06-22 | 2000-01-14 | Toshiba Corp | Hydrogen treatment facility in reactor container |
| DE19846058C1 (en) * | 1998-10-07 | 2000-05-31 | Forschungszentrum Juelich Gmbh | Device for removing hydrogen |
| JP2005043131A (en) * | 2003-07-24 | 2005-02-17 | Hitachi Ltd | Reactor building exhaust treatment equipment |
| JP2007010457A (en) * | 2005-06-30 | 2007-01-18 | Toshiba Corp | Reactor containment apparatus and boiling water type nuclear power plant |
| JP2009257925A (en) * | 2008-04-16 | 2009-11-05 | Toshiba Corp | Hydrogen disposal device |
-
2013
- 2013-05-31 KR KR1020157002881A patent/KR102083508B1/en active Active
- 2013-05-31 WO PCT/US2013/043647 patent/WO2014025446A1/en active Application Filing
- 2013-05-31 JP JP2015526530A patent/JP6340003B2/en active Active
- 2013-05-31 CN CN201380042044.4A patent/CN104620324B/en active Active
Also Published As
| Publication number | Publication date |
|---|---|
| WO2014025446A1 (en) | 2014-02-13 |
| CN104620324A (en) | 2015-05-13 |
| JP6340003B2 (en) | 2018-06-06 |
| JP2015524569A (en) | 2015-08-24 |
| KR20150039764A (en) | 2015-04-13 |
| KR102083508B1 (en) | 2020-03-02 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN1892922B (en) | Reactor containment shell and boiling water reactor power plant | |
| CN104620324B (en) | For the Enclosed flare system alleviated after coolant loss accident | |
| US9697914B2 (en) | Nuclear power plant and passive containment cooling system | |
| EP2839480B1 (en) | Defense in depth safety paradigm for nuclear reactor | |
| RU2666790C2 (en) | Method and system for emergency and back-up cooling of nuclear fuel and reactors | |
| Zuying et al. | Thermal hydraulic transient analysis of the HTR-10 | |
| Zheng et al. | Water-ingress analysis for the 200áMWe pebble-bed modular high temperature gas-cooled reactor | |
| JPH0734040B2 (en) | Preliminary safety injection system for a reactor plant | |
| JP2019074534A (en) | Method for supplying backup power | |
| CN104979020A (en) | Hydrogen risk control system and control method for small-power nuclear reactor containment | |
| Kim et al. | Systematic hydrogen risk analysis of OPR1000 containment before RPV failure under station blackout scenario | |
| JP2004333357A (en) | Reactor containment vessel | |
| JP3182208B2 (en) | Propellant operated reactor steam pressure reducing valve | |
| JP6466704B2 (en) | Fuel / coolant interaction impact mitigation system and nuclear power plant equipped with the same | |
| KR102295087B1 (en) | system for reducing the release of radioactive material to the atmosphere under severe accident | |
| US11355255B2 (en) | System and method for reducing atmospheric release of radioactive materials caused by severe accident | |
| KR102113284B1 (en) | system and a method for reducing the release of radioactive material to the atmosphere under severe accident | |
| Snell et al. | Chernobyl: A Canadian Perspective | |
| CN104361912B (en) | It is applicable to caisson type marine nuclear power station water inlet system in emergency circumstances | |
| JP3248044B2 (en) | Plasma emergency shutdown device for fusion reactor | |
| Nakamura et al. | Progress in thermohydraulic analysis of accident scenarios of a water-cooled fusion DEMO reactor | |
| Uspuras et al. | The specifics of RBMK core cooling at overheated conditions | |
| Kessler et al. | Severe accident containment loads and possible design concepts of future large pressurized water reactors | |
| Barbier et al. | Massive H2 production (I/S cycle) with VHTR heating: preliminary designs & safety approach for coupling | |
| Bassi et al. | Massive H2 production with nuclear heating, safety approach for coupling A VHTR with an Iodine Sulfur process cycle |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C06 | Publication | ||
| PB01 | Publication | ||
| C10 | Entry into substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| GR01 | Patent grant | ||
| GR01 | Patent grant |