CN101908385B - Device for relieving serious accidents of nuclear power station by utilizing moisture absorption characteristic of saline solution - Google Patents
Device for relieving serious accidents of nuclear power station by utilizing moisture absorption characteristic of saline solution Download PDFInfo
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- CN101908385B CN101908385B CN2010102170598A CN201010217059A CN101908385B CN 101908385 B CN101908385 B CN 101908385B CN 2010102170598 A CN2010102170598 A CN 2010102170598A CN 201010217059 A CN201010217059 A CN 201010217059A CN 101908385 B CN101908385 B CN 101908385B
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- 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
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- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
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Abstract
The invention belongs to the technical field of safety equipment of a nuclear power station, in particular relates to a device for relieving serious accidents of a nuclear power station by utilizing the moisture absorption characteristic of a saline solution when the nuclear power station has serious accidents. Especially, under the conditions that an LOCA occurs or a steam pipeline in a safety shell is broken and high temperature and high pressure of the safety shell are caused, a steam explosion accident can be caused possibly, and meantime, a non-contact type temperature sensor and circuit connection are used for controlling a valve to be opened and closed to be arranged in the proper position. When a reactor has serious accidents, corresponding braking action is executed; and by utilizing the characteristic of stronger moisture absorption capacity of a lithium chloride solution, high temperature and high pressure wet steam in the safety shell under the accident conditions is absorbed to prevent steam explosion, thereby achieving the purpose of relieving the serious accidents of the reactor. A plurality of passive modes such as natural circulation, gravity effect, pressure effect and the like simultaneously exist in the system, thus the invention has the advantages of convenient implementation, simple control, high reliability, safety and stability.
Description
Technical field
The invention belongs to the nuclear plant safety equipment technical field, particularly a kind of device that utilizes the salt solusion moisture-absorption characteristics to alleviate nuclear plant severe accident during nuclear power station generation major accident.Specifically, be accident to occur at nuclear power station, particularly (cooling medium runs the accident event to LOCA; In light-water reactor, be also referred to as loss of-coolant accident (LOCA)) or the containment internal steam pipe road situation of breaking under, when causing the containment HTHP, just might cause the vapour explosion accident; At this moment, nuclear power station moisture absorption system auto-action utilizes the salt solusion with moisture-absorption characteristics; Absorb a large amount of damp steams, thereby reduce the pressure and temperature of containment, realize suppressing or slowing down accident; The harm of accident is reduced, ensure nuclear power station the 3rd road barrier enforcement normal function.
Background technology
Accident occurs at pressurized-water reactor nuclear power plant, after particularly LOCA accident or containment internal steam pipe road broke, the water of HTHP can become steam in the loop.Thus, a large amount of wet steams are sprayed and are got into containment, cause the rising of the pressure and temperature of containment.If deal with improperly, might cause the vapour explosion accident, accident will be worsened.At present in two generation presurized water reactors, main processing mode is, safety injection system, containment spray system and auxiliary feedwater system are set, and can realize the inhibition to accident, and can be in the harm that alleviates accident to a certain degree.Compare two generation presurized water reactor, three generations's nuclear power station AP1000 and EPR also are provided with corresponding incident management system to these major accidents.The outstanding feature of AP1000 is to introduce the non-activeization theory of security system, is provided with many passive safety systems such as non-active core cooling system, non-passive safety shell cooling system, the removal of non-passive safety shell shake sell of one's property thing and control system.And the design of EPR security system is simplified more, has realized that 4 is heavy redundant, and in design, has considered the alleviation of major accident prevention and damage sequence.The engineered safeguards features of EPR mainly comprises containment system, emergence core stacking cool system, emergency feedwater supply system etc.Though the current and even following presurized water reactor all is provided with to the engineered safeguards features of handling major accident; But mostly just through mode or non-active cooling alleviation accident process such as peace notes, sprays, technology path mainly is the thinking that cooling earlier causes step-down again to these facilities.But along with accident further develops, in fact, will be full of the wet steam of HTHP in the containment in a large number, wet steam is to cause new threat to dominate medium to reactor.So,, just can solve more effectively step-down under accident conditions, thereby must cause cooling if can remove wet steam.Therefore, must design a kind of novel step-down cooling system, to increase the safety coefficient of containment.This system must can absorb steam, directly handles the characteristic of accident conditions Fluid field, brings the variation in pressure field and temperature field.Can be directly triggering system apace, with effective alleviation accident, guarantee the safety of nuclear power station and even surrounding environment.
Summary of the invention
The deficiency that the purpose of this invention is to provide to prior art proposes a kind of device that utilizes the salt solusion moisture-absorption characteristics to alleviate nuclear plant severe accident; It is characterized in that the device of said alleviation nuclear plant severe accident is to utilize the moisture absorbing of salt solusion to realize also preventing vapour explosion to step-down in the npp safety shell, cooling; Alleviate the device of nuclear plant severe accident, this device is designed to external, thereby has saved the containment inner space effectively, also is convenient to the control to total system; Employing is with the operation of the form control circuit of thermal switch, realizes the running control to valve, be a kind of non-actively with the mode that actively combines; Concrete structure is the fixing first group of intelligent switch that is composed in series by temperature sensor 2, control circuit 3 and valve 4 at the top of containment 16, below first group of intelligent switch, connects air-breathing funnel 5; Valve 4 is connected with containment 16 outside aspiration pumps 6; Stuffing box 10 inserts salt solusion case 1 upper space through filler valve 9 and pipeline; The fixing salt solusion oven temperature, degree sensor 7 in the pipeline insert division on salt solusion case 1 top; Filler valve control circuit 8 is installed, the switch of the temperature signal control filler valve 9 of the salt solusion case 1 that filler valve control circuit 8 obtains through salt solusion oven temperature, degree sensor 7 on the filler valve 9; One side of salt solusion case 1 is connected with heat interchanger 12 through pipeline, and opposite side top connects aspiration pump 6; The bottom of salt solusion case 1 connects hydraulic regulation valve 11, bottom setting pressure container 13 in the containment 16; Steam generator 14 is connected in series with voltage stabilizer 15 and pressure vessel 13; The air that the last space of said salt solusion case 1 is, salt solusion case 1 lower half-space is injected the halogen family salt solusion.
It is lithium chloride solution or lithium-bromide solution that said salt solusion case 1 lower half-space is injected the halogen family salt solusion; Stuffing box 10 provides the lithium chloride solution of 67% volumetric concentration to inject salt solusion case 1; Lithium chloride solution and containment 16 heat exchange, chilled water carries out heat exchange through pipeline and heat interchanger 12.Because lithium chloride solution moisture absorption constantly during the course, concentration will be thinning gradually, and temperature also raises gradually; Thereby the density of causing and temperature difference produce Natural Circulation, reach a kind of non-active heat exchange effect; Therefore this relieving apparatus is through drawing and absorbing wet steam; Reduce system pressure, also reduce system temperature, very helpful to removing the containment endoparticle thing that reactor disaster produces simultaneously.
Said lithium chloride solution is contained in the containment internal box, and it is a kind of dehumidizier that is usually used in the solution damping air-conditioning, belongs to inorganic salt solution; Chemical property is stable, and boiling point is up to 1200 ℃ under the normal pressure, and along with the rising of temperature, the solubleness of lithium chloride can increase gradually, and lithium chloride solution concentration is big more, and temperature is low more, and wettability power is strong more, and effect on moisture extraction is good more.Can absorb in a large number and riddle HTHP damp steam in the containment, thereby effectively reduce containment internal pressure, temperature and humidity.
The sensitive element of said temperature sensor does not contact with measurand mutually, therefore, claims the contactless temperature-measuring instrument again, and this contactless temperature-measuring instrument is selected H-T series contactless temperature-measuring sensor for use.This instrument is used for measuring moving object, little target and thermal capacity is little or the surface temperature of temperature transient object, or is used for the Temperature Distribution of Temperature Field Measurement; Its advantage is to measure the restriction that the upper limit does not receive temperature-sensing element heatproof degree, thereby to the not restriction of the highest observable temperature.
The invention has the beneficial effects as follows provides a kind of device that utilizes the salt solusion moisture-absorption characteristics to alleviate nuclear plant severe accident, and compared with prior art, have outstanding advantage and effect: the present invention adopts non-contact temperature sensor; The thoughts and feelings element need not contact with measured medium, so just can not destroy the temperature field of medium, and its measurement upper limit does not receive the restriction of temperature-sensing element heatproof degree; Measurement range is wide; Response speed is fast, can in time provide signal and open the suction channel valve, carries out moisture absorption; Effective alleviation accident, the harm of reduction accident.Non-contacting sensor can make equipment operation steady in a long-term, dependable performance.This device control structure is highly sensitive, simple in structure, and can be under various pressure conditions uses effectively, and the harm that suppresses or slow down nuclear plant severe accident is had positive effect.Can be easier to carry out the marketization and be applicable, be one of important technology of the advanced reactor of development.
Description of drawings
Fig. 1 is a kind of device synoptic diagram that utilizes the salt solusion moisture-absorption characteristics to alleviate nuclear plant severe accident.
Embodiment
A kind of device that utilizes the salt solusion moisture-absorption characteristics to alleviate nuclear plant severe accident that The present invention be directed to the deficiency of prior art and propose is explained below in conjunction with accompanying drawing.
Fig. 1 is the device synoptic diagram that utilizes the salt solusion moisture-absorption characteristics to alleviate nuclear plant severe accident provided by the invention.Its adopts the operation with the form control circuit of thermal switch, realizes the running control to valve, be a kind of non-actively with the mode that actively combines; Concrete structure is the fixing first group of intelligent switch that is composed in series by temperature sensor 2, control circuit 3 and valve 4 at the top of containment 16, below first group of intelligent switch, connects air-breathing funnel 5; Valve 4 is connected with containment 16 outside aspiration pumps 6; Stuffing box 10 inserts salt solusion case 1 upper space through filler valve 9 and pipeline; The fixing salt solusion oven temperature, degree sensor 7 in the pipeline insert division on salt solusion case 1 top; Filler valve control circuit 8 is installed, the switch of the temperature signal control filler valve 9 of the salt solusion case 1 that filler valve control circuit 8 obtains through salt solusion oven temperature, degree sensor 7 on the filler valve 9; One side of salt solusion case 1 is connected with heat interchanger 12 through pipeline, and opposite side top connects aspiration pump 6; The bottom of salt solusion case 1 connects hydraulic regulation valve 11, bottom setting pressure container 13 in the containment 16; Steam generator 14 is connected in series with voltage stabilizer 15 and pressure vessel 13.The practical implementation process is following:
When the LOCA accident appears in presurized water reactor, break accident and possibly cause the accident of vapour explosion to take place of containment 16 internal steam pipe roads; Cooling medium or steam spurt; Make containment 16 interior temperature and pressures raise, at this moment, temperature sensor 2 inductions change and make valve 4 open through control circuit 3; Aspiration pump 6 is started working, and through air-breathing funnel 5 water vapour in the containment 16 is taken out toward salt solusion case 1.At this moment; High-temperature wet steam vapour gets into salt solusion case 1 makes pipe surface temperature rise; Cause 7 inductions of salt solusion oven temperature, degree sensor to change, make filler valve 9 open through filler valve control circuit 8, the lithium chloride solution in the stuffing box 10 flows to salt solusion case 1 under the effect of gravity.The lithium chloride solution height rises in the salt solusion case 1, and the pressure that bottom hydraulic pressure variable valve 11 receives increases gradually, opens voluntarily when reaching certain value, and the lithium chloride solution in the salt solusion case is arranged to liquid waste treatment system thereupon.When whole process is carried out; Chilled water in lithium chloride solution in the salt solusion case 1 and the heat interchanger 12 is owing to exist density difference and temperature difference; Meet the Natural Circulation condition; Thereby can be spontaneous carry out exchange heat, thereby guaranteed that also the salt solusion in the casing 1 remains on a relative stationary temperature and concentration.
With regard to Fig. 1, when reactor generation major accident, because coolant temperature sharply raises or a large amount of discharge of steam in the containment; Cause the containment temperature to raise, possibly produce the high temperature more than 1800 ℃, the present invention adopts non-contact temperature sensor to experience the influence that temperature raises; Drive control circuit and open valve, the water vapour that the lithium chloride solution in the salt solusion lower box part space produces in the time of will absorbing major accident plays the effect of containment being fallen wet, cooling and step-down; The progress of alleviation accident thus can in time provide signal and open the suction channel valve, carries out moisture absorption; Effective alleviation accident, the harm of reduction accident.
The selective chlorination lithium salt solution, also halogen family salt solusion such as available lithium bromide, it is a kind of dehumidizier that is usually used in the solution damping air-conditioning, is inorganic salt solution, and chemical property is stable, and boiling point is up to 1200 ℃ under the normal pressure.Lithium chloride solution concentration is big more, and temperature is low more, and wettability power is strong more, and effect on moisture extraction is good more.Can absorb in a large number and riddle high-temperature high-pressure steam in the containment, thereby effectively reduce containment internal pressure, temperature and humidity.
Claims (4)
1. device that utilizes the salt solusion moisture-absorption characteristics to alleviate nuclear plant severe accident; It is characterized in that; The device of said alleviation nuclear plant severe accident is that the moisture absorbing that utilizes salt solusion is realized step-down in the npp safety shell, lowering the temperature also to prevent the device of the alleviation nuclear plant severe accident of vapour explosion; This device is designed to external, thereby has saved the containment inner space effectively, also is convenient to the control to total system; Employing is with the operation of the form control circuit of thermal switch, realizes the running control to valve, be a kind of non-actively with the mode that actively combines; Concrete structure is the fixing first group of intelligent switch that is composed in series by temperature sensor (2), control circuit (3) and valve (4) at the top of containment (16), below first group of intelligent switch, connects air-breathing funnel (5); Valve (4) is connected with the outside aspiration pump (6) of containment (16); Stuffing box (10) inserts salt solusion case (1) upper space through filler valve (9) and pipeline; The fixing salt solusion oven temperature, degree sensor (7) in the pipeline insert division on salt solusion case (1) top; Filler valve (9) go up to be installed filler valve control circuit (8), and the temperature signal of the salt solusion case (1) that filler valve control circuit (8) obtains through salt solusion oven temperature, degree sensor (7) is controlled the switch of filler valve (9); One side of salt solusion case (1) is connected with heat interchanger (12) through pipeline, and opposite side top connects aspiration pump (6); The bottom of salt solusion case (1) connects hydraulic regulation valve (11), containment (16) interior bottom setting pressure container (13); Steam generator (14) and voltage stabilizer (15) are connected in series with pressure vessel (13); The upper half-space of said salt solusion case (1) is an air, and salt solusion case (1) lower half-space is injected the halogen family salt solusion.
2. according to the said device that utilizes the salt solusion moisture-absorption characteristics to alleviate nuclear plant severe accident of claim 1, it is characterized in that it is lithium chloride solution or lithium-bromide solution that said salt solusion case (1) lower half-space is injected the halogen family salt solusion; Stuffing box (10) provides the lithium chloride solution of 67% volumetric concentration to inject salt solusion case (1); Lithium chloride solution and containment (16) heat exchange, chilled water carries out heat exchange through pipeline and heat interchanger (12), because lithium chloride solution moisture absorption constantly during the course; Concentration will be thinning gradually, and temperature also raises gradually, thus the density of causing and temperature difference; Produce Natural Circulation; Reach a kind of non-active heat exchange effect, so this relieving apparatus reduces system pressure through drawing and absorbing wet steam; Also reduce system temperature, very useful to removing the containment endoparticle thing that reactor disaster produces simultaneously.
3. according to the said device that utilizes the salt solusion moisture-absorption characteristics to alleviate nuclear plant severe accident of claim 2, it is characterized in that said lithium chloride solution is contained in the containment internal box, it is a kind of dehumidizier that is usually used in the solution damping air-conditioning, belongs to inorganic salt solution; Chemical property is stable, and boiling point is up to 1200 ℃, and along with the rising of temperature under the normal pressure; The solubleness of lithium chloride can increase gradually, and lithium chloride solution concentration is big more, and temperature is low more; Wettability power is strong more; Effect on moisture extraction is good more, and a large amount of the absorption riddles HTHP damp steam in the containment, thereby effectively reduces containment internal pressure, temperature and humidity.
4. according to the said device that utilizes the salt solusion moisture-absorption characteristics to alleviate nuclear plant severe accident of claim 1; It is characterized in that; The sensitive element of said temperature sensor does not contact with measurand mutually; Therefore, claim the contactless temperature-measuring instrument again, this contactless temperature-measuring instrument is selected H-T series contactless temperature-measuring sensor for use; This instrument is used for measuring moving object, little target and thermal capacity is little or the surface temperature of temperature transient object, or is used for the Temperature Distribution of Temperature Field Measurement; Its advantage is to measure the restriction that the upper limit does not receive temperature-sensing element heatproof degree, and therefore can in time provide signal with non-contact temperature sensor opens the suction channel valve, carries out moisture absorption, effectively alleviation accident, the harm of reduction accident.
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| Application Number | Priority Date | Filing Date | Title |
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| CN2010102170598A CN101908385B (en) | 2010-07-02 | 2010-07-02 | Device for relieving serious accidents of nuclear power station by utilizing moisture absorption characteristic of saline solution |
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| CN2010102170598A CN101908385B (en) | 2010-07-02 | 2010-07-02 | Device for relieving serious accidents of nuclear power station by utilizing moisture absorption characteristic of saline solution |
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| CN101908385A CN101908385A (en) | 2010-12-08 |
| CN101908385B true CN101908385B (en) | 2012-11-21 |
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| Publication number | Priority date | Publication date | Assignee | Title |
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| KR101161677B1 (en) * | 2010-12-28 | 2012-07-02 | 임주혁 | Steam generator for automatic water supply which uses vapor pressure |
| CN104751906A (en) * | 2015-02-13 | 2015-07-01 | 中国科学院近代物理研究所 | Heat exchange system and nuclear reactor system |
| CN108563840B (en) * | 2018-03-23 | 2019-02-26 | 西安交通大学 | A kind of nuclear reactor vapour explosion comprehensive analysis method |
| CN110444301B (en) * | 2019-08-13 | 2022-07-01 | 中国核动力研究设计院 | Experimental device and experimental method for simulating supercritical pressure transient working condition |
Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO1990016071A1 (en) * | 1988-05-09 | 1990-12-27 | Siemens Aktiengesellschaft | Nuclear power station with a safety shell and pressure-relieving process |
| US20080137796A1 (en) * | 2005-12-06 | 2008-06-12 | General Electric Company | Method for reducing carbon steel corrosion in high temperature, high pressure water |
| CN101477842A (en) * | 2009-01-13 | 2009-07-08 | 华北电力大学 | Steam pressure tablet, thin-film and metal mesh type nuclear plant severe accident relieving apparatus |
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| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS54114695A (en) * | 1978-02-27 | 1979-09-06 | Toshiba Corp | Pressure suppressor |
| JP2915012B2 (en) * | 1989-08-30 | 1999-07-05 | 株式会社日立製作所 | Nuclear power plant |
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Patent Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO1990016071A1 (en) * | 1988-05-09 | 1990-12-27 | Siemens Aktiengesellschaft | Nuclear power station with a safety shell and pressure-relieving process |
| US20080137796A1 (en) * | 2005-12-06 | 2008-06-12 | General Electric Company | Method for reducing carbon steel corrosion in high temperature, high pressure water |
| CN101477842A (en) * | 2009-01-13 | 2009-07-08 | 华北电力大学 | Steam pressure tablet, thin-film and metal mesh type nuclear plant severe accident relieving apparatus |
Non-Patent Citations (2)
| Title |
|---|
| JP平3-85493A 1991.04.10 |
| JP昭54-114695A 1979.09.06 |
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