CN205582508U - A non - kinetic energy containment cooling system for PWR - Google Patents
A non - kinetic energy containment cooling system for PWR Download PDFInfo
- Publication number
- CN205582508U CN205582508U CN201620250428.6U CN201620250428U CN205582508U CN 205582508 U CN205582508 U CN 205582508U CN 201620250428 U CN201620250428 U CN 201620250428U CN 205582508 U CN205582508 U CN 205582508U
- Authority
- CN
- China
- Prior art keywords
- containment
- air
- condensing container
- outside
- water
- 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.)
- Expired - Fee Related
Links
Classifications
-
- 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
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The utility model discloses a non - kinetic energy containment cooling system for PWR, it more effectively contains the steam of the great volume of spurting through the structural change of steel containment (11) inside and outside, realization to the security improves. Through in the inside and/or outside increase of casing 2 of steel containment (11) 20 individual condensation container (3), and place the not saturated solution who dissolves the air in proportion in condensation container (3), play the control action to the dry air who absorbs in steel containment (11).
Description
Technical field
This utility model belongs to nuclear power plant containment shell design field, especially relates to a kind of non-kinetic containment cooling system for presurized water reactor.
Background technology
Containment in Generation Ⅲ, as the exterior shield structure of Nuclear Power Accident, is the important step of accident prevention and alleviation.The feature that the inside useful space according to passive type containment is proportional to thermal power, containment is all to be designed and safety analysis with the form of up-sizing all the time, the size of containment is increasing, its investment economy, safeguards that convenience and construction period etc. all vary considerably.According to M.Gavrilas and the sincere lattice of woods etc., the introduction of passive type containment and analysis are understood, the accident initial stage has substantial amounts of water and enters containment inside via break location with the form of jet and flash distillation from primary Ioops, only the pressure in 1-5 second inner containment rises violently rapidly and reaches maximum pressure in a short time, owing to devising a kind of pressure activated switch, cooling water system is triggered when containment internal pressure reaches certain high pressure, make outside containment, to start trickling cooling water, moisture film is produced outside containment, outside moisture film is dispelled the heat by heat of vaporization in the case of containment generates heat, with heat transfer type to cooling and steam condensation in shell, in the range of again the pressure limit in shell being scheduled on safe pressure.But, learn according to experimental data, there are 2 deficiencies in the mode that this heat radiation ensures safety: one is owing to primary Ioops enters inside containment via break location with the form of jet and flash distillation, only can take measures for people in 1-5 time second, time is the shortest, needs to extend in accident process in containment pressure from normal to the time that can bear maximum pressure;Two when be that in accident, in containment, pressure rises rapidly, and the temperature of containment can't rise rapidly, and it is inefficient that cooling water system starts as containment cooling.To this end, the problem that containment structure form emphasis should be resolved: one is that primary Ioops transient state is spurted pressure in steam does not cause containment and transfinited rapidly;Two is that the heat of containment sets out ability and needs to be greatly improved.
Utility model content
The purpose of this utility model is on the basis of input funds do not increase too much, it is possible to is changed by the structure of containment inside and outside, realizes the steam more effectively containing the amount of spurting more greatly to improve safety.
Technical scheme: the most comprehensively carry out the security fence to nuclear power plant containment shell.One is internal at containment shell and/or hull outside increases 2-20 condensing container;Two is the unsaturated solution placing dissolved air in proportion in condensing container, and the dry air in absorption safety shell is played control action.
Embodiment: nuclear power station is made up of steel containment vessel, reactor core melt pit, roof water tank and water knockout drum 12, deflector etc..Adding 2-20 condensing container Safety shell is inner and/or outer, also add 2-20 root air-flow skirt in Safety shell, air-flow skirt connection Safety shell is internal and inside condensing container;Having steam water interface in condensing container, steam water interface meets certain volume mass than relation, and each condensing container is internal also has an overflow pipe to communicate with outside condensing container, and water and/or air-flow can be introduced or discharge condensing container by air-flow skirt and overflow pipe;Overflow pipe is connected with liquidometer and electric switching valve outside condensing container, and is connected to reactor core melt pit by electric switching valve.
There is 1/1st to three/5th steam water interface in the condensing container that Safety shell is internally and/or externally arranged and meets certain volume mass than relation, i.e. dissolve the unsaturated coolant of a certain amount of air.According to experimental analysis, it has been found that before breaking down, being completely filled with dry air in containment, the pressure in containment is less, and dry air is relatively low by the heat-sinking capability of containment shell;In vapours enters containment, the pressure in space rises rapidly, pressure in the condensing container that the inner and/or outer portion of containment is arranged rises the most at once, containment is internal creates pressure differential inside condensing container, effect due to this pressure differential, the vapours of gas-liquid mixed is entered by the air-flow skirt within Safety shell and connects the air-flow skirt within condensing container, and the pressure within containment obtains temporary transient buffering, and the pressure within condensing container rises;The vapours of gas-liquid mixed enters while condensing container also with partially dried air, and the speed making pressure in containment raise is delayed further;When the vapours of gas-liquid mixed is by condensed fluid, due to condensation, a part of drop enters among condensed fluid, under the effect of the pressure, among unsaturated liquid, also sub-fraction arrives the gas compartment of condensing container to portion of air, the pressure of the gas compartment rises, but the gas that this part is relatively dried is absorbed a part by liquid, when another part is diffused into the gas compartment, and normal condition compares and is also significantly compressed by volume;Water in the vapours of gas-liquid mixed is also cooled after liquid condensing and absorbs, liquid level in condensing container raises, liquidometer will be touched when liquid level reach a certain height, liquidometer is opened, the output signal of telecommunication, opens electric switching valve so that water unnecessary in condensing container directly trickles in the way of overflow to reactor core melt pit, reduced pressure inside condensing container, the vapours of gas-liquid mixed outside condensing container can be continued to.By the condensing container arranged, the pressure within containment can be made to enter the vapours stage within containment via break location with the form of jet and flash distillation at initial primary Ioops, extending the pressure in containment and be increased to the time of maximum pressure, the time making people carry out emergency processing is extended.
nullWhen starting falling liquid film along with the outside moisture film of containment,Moisture film interacts with outside air,Air is by the wet-well of deflector lower end and moisture film direct contact heat transfer,Air themperature increases、After water capacity increases, its density reduces,Flow up within the ascent stage outside containment under the common effect of buoyancy and gravity,Air current flow speed becomes big,Convection current evaporation and heat-exchange between moisture film and air strengthens,Vapours is penetrated into owing to containment is internal,Humidity in air is made to increase,Energy storage capability increases,When the outside water film evaporation of containment absorbs heat increase,Containment shell is lowered the temperature further,And reduce due to wall surface temperature inside containment,The state that the water vapour humidity that can be maintained at for more time in mixed gas inside containment is bigger,Although the outside moisture film evaporation endothermic amount of containment increases,Containment internal condensate is made to strengthen,But,According to the equation of gas state,In constant volume device,The humidity of air-flow increases,Quality increases,When reducing identical temperature,More heat energy can be absorbed.The radiating efficiency making the outer moisture film of containment is in a kind of higher state, enable the pressure of air-flow containment within for more time maintain a stable level, containment shell heat sets out ability to be strengthened.
This utility model, compared with existing presurized water reactor containment, has the following advantages:
Containment dischargeable capacity significantly reduces, and containment structure is more compact, reduces the investments such as processing, construction.
Below with volume 58300m free in the containment of AP10003Calculating, maximum working pressure during presurized water reactor accident is 0.5MPa, temperature peak 160 DEG C.When there being 50 tons of water in direct condenser, internal total measurement (volume) 7764m3, now can save the internal useful space 17%.If using the form of Fig. 2, direct condenser container is not limited by containment, and its structure is more reasonable.
In prototype, in containment wet-well, unevaporated cooling water effectively utilizes, and is completely used for shell interior-heat loading gage and goes out, and the steam after evaporation can be effectively increased the buoyancy of air.
Gas flow temperature in ascent stage increases so that the buoyancy increase of air-flow causes speed to increase, and steel containment vessel outside heat sets out capability improving.
Accompanying drawing explanation
Fig. 1 is the schematic diagram arranging condensing container inside containment;
Fig. 2 is the schematic diagram arranging condensing container outside containment;
In Fig. 3 is containment and outside arranges the schematic diagram of condensing container.
Illustrate: 1-air-flow skirt;House steward 2-;3-condensing container;4-set of heat exchange tubes;5-scatters device;6-reactor core melt pit;7-overflow pipe;8-liquidometer;9-electric switching valve;10-deflector;11-steel containment vessel;12-roof water tank and water knockout drum.
Detailed description of the invention
The most comprehensively carry out the security fence to nuclear power plant containment shell.One is at steel containment vessel 11 2 condensing containers 3 of inside and outside each increase;Two is the unsaturated solution placing dissolved air in proportion in condensing container 3, and the dry air in absorption safety shell is played control action.
Embodiment one: nuclear power station is made up of air-flow skirt 1, house steward 2, condensing container 3, set of heat exchange tubes 4, wandering device 5, reactor core melt pit 6, overflow pipe 7, liquidometer 8, electric switching valve 9, deflector 10, steel containment vessel 11, roof water tank and water knockout drum 12 etc..Respectively adding 2 condensing containers 3 inside and outside Safety shell, also add 4 air-flow skirts in Safety shell, air-flow skirt connection Safety shell is internal and condensing container 3 is internal;Steam water interface is had in condensing container 3, steam water interface meets certain volume mass and compares relation, each condensing container 3 is internal also has an overflow pipe 7 and condensing container 3 outside to communicate, and water and/or air-flow can be introduced or discharge condensing container 3 by air-flow skirt and overflow pipe 7;Overflow pipe 7 is connected with liquidometer 8 and electric switching valve 9 in condensing container 3 outside, and is connected to reactor core melt pit 6 by electric switching valve 9.
There is 1/1st to three/5th steam water interface in the condensing container 3 that Safety shell is internally and/or externally arranged and meets certain volume mass than relation, i.e. dissolve the unsaturated coolant of a certain amount of air.According to experimental analysis, it has been found that before breaking down, being completely filled with dry air in containment, the pressure in containment is less, and dry air is relatively low by the heat-sinking capability of steel containment vessel 11;In vapours enters containment, the pressure in space rises rapidly, pressure in the condensing container 3 that the inner and/or outer portion of containment is arranged rises the most at once, containment is internal and condensing container 3 is internal creates pressure differential, effect due to this pressure differential, the vapours of gas-liquid mixed is entered by the air-flow skirt within Safety shell and connects the air-flow skirt within condensing container 3, and the pressure within containment obtains temporary transient buffering, and the pressure within condensing container 3 rises;The vapours of gas-liquid mixed enters while condensing container 3 also with partially dried air, and the speed making pressure in containment raise is delayed further;When the vapours of gas-liquid mixed is by condensed fluid, due to condensation, a part of drop enters among condensed fluid, under the effect of the pressure, among unsaturated liquid, also sub-fraction arrives the gas compartment of condensing container 3 to portion of air, the pressure of the gas compartment rises, but the gas that this part is relatively dried is absorbed a part by liquid, when another part is diffused into the gas compartment, and normal condition compares and is also significantly compressed by volume;Water in the vapours of gas-liquid mixed is also cooled after liquid condensing and absorbs, liquid level in condensing container 3 raises, liquidometer 8 will be touched when liquid level reach a certain height, liquidometer 8 is opened, the output signal of telecommunication, opens electric switching valve 9 so that water unnecessary in condensing container 3 directly trickles in the way of overflow to reactor core melt pit 6, condensing container 3 is internal to be reduced pressure, and can continue to the vapours of gas-liquid mixed outside condensing container 3.By the condensing container 3 arranged, the pressure within containment can be made to enter the vapours stage within containment via break location with the form of jet and flash distillation at initial primary Ioops, extending the pressure in containment and be increased to the time of maximum pressure, the time making people carry out emergency processing is extended.
nullWhen starting falling liquid film along with the outside moisture film of containment,Moisture film interacts with outside air,Air is by the wet-well of deflector 10 lower end and moisture film direct contact heat transfer,Air themperature increases、After water capacity increases, its density reduces,Flow up within the ascent stage outside containment under the common effect of buoyancy and gravity,Air current flow speed becomes big,Convection current evaporation and heat-exchange between moisture film and air strengthens,Vapours is penetrated into owing to containment is internal,Humidity in air is made to increase,Poultry can ability increase,When the outside water film evaporation of containment absorbs heat increase,Containment shell is lowered the temperature further,And reduce due to wall surface temperature inside containment,The state that the water vapour humidity that can be maintained at for more time in mixed gas inside containment is bigger,Although the outside moisture film evaporation endothermic amount of containment increases,Containment internal condensate is made to strengthen,But,According to the equation of gas state,In constant volume device,The humidity of air-flow increases,Quality increases,When reducing identical temperature,More heat energy can be absorbed.The radiating efficiency making the outer moisture film of containment is in a kind of higher state, enable the pressure of air-flow containment within for more time maintain a stable level, steel containment vessel 11 heat sets out ability to be strengthened.
In this utility model, in direct condenser, the initial proportion of gas and water is most important, effectively controls the effect of pressure in shell if out of proportion by causing not reaching.Provide below its calculating process: the initial air volume in direct condenser is Va, unit is m3, VaNeed to meet relation be:
In formula, m is the quality of initial water, and unit is kg;RaGas constant for air;hfgFor the latent heat of vaporization;ptFor the maximum absolute pressure in containment during accident, unit is atm;Maximum temperature when t is accident, unit is DEG C.
Now the volume of direct contact type condensing container 3 is:
This utility model, compared with existing presurized water reactor containment, has the following advantages:
Containment dischargeable capacity significantly reduces, and containment structure is more compact, reduces the investments such as processing, construction.
With volume (58300m free in the containment of AP10003) calculate, maximum working pressure during presurized water reactor accident is 0.5MPa, temperature peak 160 DEG C.When there being 50 tons of water in direct condenser, internal total measurement (volume) 7764m3, now can save the internal useful space 17%.
If using the outside form arranging condensing container 3 of Fig. 2 steel containment vessel 11, condenser container is not limited by containment, and its structure is simpler rationally.
It is outside that condensing container 3 has part to be arranged on steel containment vessel 11, has the inside of a connection steel containment vessel 11 of fraction skirt 1 in the 2-20 root air-flow skirt 1 of increase, and the inside of the condensing container 3 outside other end and steel containment vessel 11 is connected;If taking this outlet structure, its reactor core melt pit 6 is necessary for the closed melt pit of deep layer.
In prototype, in steel containment vessel 11 wet-well, unevaporated cooling water effectively utilizes, and is completely used for shell interior-heat loading gage and goes out, and the steam after evaporation can be effectively increased the buoyancy of air.
Gas flow temperature in ascent stage increases so that the buoyancy increase of air-flow causes speed to increase, and steel containment vessel 11 outside heat sets out capability improving.
Claims (3)
1., for a non-kinetic containment cooling system for presurized water reactor, there is steel containment vessel (11), reactor core melt pit (6), roof water tank and water knockout drum (12), deflector (10);It is characterized in that adding 2-20 condensing container (3) in steel containment vessel (11), also add 2-20 root air-flow skirt (1) in steel containment vessel (11), air-flow skirt (1) connection steel containment vessel (11) is internal and condensing container (3) is internal;Each condensing container has steam water interface in (3), and also an overflow pipe (7) communicates with condensing container (3) outside, and water and/or air-flow can be introduced or discharge condensing container (3) by air-flow skirt (1) and overflow pipe (7);Overflow pipe (7) is connected with liquidometer (8) and electric switching valve (9) in condensing container (3) outside, and is connected to reactor core melt pit (6) by electric switching valve (9);/ to three/5th steam water interface coolant is had in each condensing container (3).
A kind of non-kinetic containment cooling system for presurized water reactor the most according to claim 1, it is characterized in that condensing container (3) has part to be arranged on steel containment vessel (11) outside, 2-20 root air-flow skirt (1) increased there are the inside of connection steel containment vessel (11) of fraction skirt (1), the inside of the condensing container (3) of other end and steel containment vessel (11) outside are connected.
A kind of non-kinetic containment cooling system for presurized water reactor the most according to claim 2, it is characterised in that reactor core melt pit (6) is the closed melt pit of deep layer.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN201620250428.6U CN205582508U (en) | 2016-03-29 | 2016-03-29 | A non - kinetic energy containment cooling system for PWR |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN201620250428.6U CN205582508U (en) | 2016-03-29 | 2016-03-29 | A non - kinetic energy containment cooling system for PWR |
Publications (1)
Publication Number | Publication Date |
---|---|
CN205582508U true CN205582508U (en) | 2016-09-14 |
Family
ID=56866433
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
CN201620250428.6U Expired - Fee Related CN205582508U (en) | 2016-03-29 | 2016-03-29 | A non - kinetic energy containment cooling system for PWR |
Country Status (1)
Country | Link |
---|---|
CN (1) | CN205582508U (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN105741888A (en) * | 2016-03-29 | 2016-07-06 | 中国人民解放军92609部队 | Non-kinetic energy containment cooling system for pressurized water reactor |
-
2016
- 2016-03-29 CN CN201620250428.6U patent/CN205582508U/en not_active Expired - Fee Related
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN105741888A (en) * | 2016-03-29 | 2016-07-06 | 中国人民解放军92609部队 | Non-kinetic energy containment cooling system for pressurized water reactor |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
CN104979023B (en) | Passive containment thermal conduction system and its control method and pressurized water reactor | |
CN202855316U (en) | Containment cooling system for PWR (pressurized water reactor) nuclear power plant | |
CN103325427B (en) | A kind of Passive containment cooling system and method | |
CN206210405U (en) | Nuclear reactor safety system | |
CN107393605A (en) | The passive air-cooling apparatus and method of a kind of modular small nuclear reactor | |
CN102549674A (en) | Two-fluid molten-salt reactor | |
CN106328223B (en) | A kind of novel passive containment energy management system | |
CN105047236A (en) | Passive cooling system for retention of melts in serious accident state of reactor | |
CN103165199A (en) | Emergency core cooling system (eccs) for nuclear reactor employing closed heat transfer pathways | |
CN112071451B (en) | Multifunctional double-layer concrete containment system of pressurized water reactor | |
CN107123448B (en) | A kind of containment cooling system that coolant utilization rate can be improved | |
CN205582508U (en) | A non - kinetic energy containment cooling system for PWR | |
CN204178729U (en) | A kind of long-term passive containment thermal conduction system | |
CN203839055U (en) | Passive containment external cooling system | |
CN106251918B (en) | A kind of long timeliness Passive containment cooling system | |
CN107093470A (en) | A kind of constrain system of containment for strengthening cooling | |
CN105741888A (en) | Non-kinetic energy containment cooling system for pressurized water reactor | |
CN107648999A (en) | A kind of sterilization oxirane emission control technology and device | |
CN103523842B (en) | Deaerator exhaust steam recovery device and recovery process | |
CN108877966A (en) | A kind of enclosed Passive containment cooling system for floating type nuclear power station | |
JPH085772A (en) | Reactor containment | |
CN106128526B (en) | A kind of ellipsoid formula underground nuclear power station containment system | |
CN207676666U (en) | A kind of band is connected to the passive double containment of lateral water tank up and down | |
CN106517243B (en) | A kind of high temperature ammonia recycling device | |
CN206168175U (en) | Modular graphite absorbs cooling tower |
Legal Events
Date | Code | Title | Description |
---|---|---|---|
C14 | Grant of patent or utility model | ||
GR01 | Patent grant | ||
CF01 | Termination of patent right due to non-payment of annual fee |
Granted publication date: 20160914 Termination date: 20210329 |
|
CF01 | Termination of patent right due to non-payment of annual fee |